Nuclear Regulatory Commission · Appendix C Facility: Oyster Creek Job Performance Measure WORKSHEET Task No.: 2230101504 Form ES-C-1 Task Title: Determine Bulk Drywell Temperature

Appendix C

Facility: Oyster Creek

Job Performance Measure WORKSHEET

Task No.: 2230101504

Form ES-C-1

Task Title: Determine Bulk Drywell Temperature lAW EMG-SP26

Job Performance Measure No.: NRC RO Admin JPM 1

K/A Reference: _2_._1._2_0~(4_.6._~.) _______ _

Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Performance Actual Performance X -----

Classroom X Simulator Plant ----- -----

Read to the Examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. The plant was at rated power when an event occurred which required entry into the Primary Containment Control EOP

2. Computer point DWTEMP is questionable

3. Recorder IA55 has lost power

4. Recorder TR-1 OOA is operable

5. EMG-SP26, Determining Bulk Drywell Temperature has been completed through step 3.1.2

Task Standard: Determines bulk Drywell temperature lAW Support Procedure 26, Determining Bulk Drywell Temperature

Required Materials: Calculator

General References:

1. EMG-SP26, Determining Bulk Drywell Temperature, Rev 1

Initiating Cue: Determine bulk Drywell temperature lAW Support Procedure 26, Determining Bulk Drywell Temperature, starting at step 3.2

NRC RO Admin JPM 1 Page 1 of 10

Appendix C

Time Critical Task: No.


Validation Time: 10 Minutes

NRC RO Admin JPM 1

Form ES-C-1

Page 2 of 10

Appendix C Job Performance Measure WORKSHEET

Performance Information

Form ES-C-1

Denote critical steps with a check mark ,/

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

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Performance Step: 1

Procedure Step: Provides repeat back of initiating cue.

JPM Start Time: ____ _

Provides repeat back of initiating cue. Evaluator acknowledges the repeat back.

Performance Step: 2

Procedure Step: Verifies Prerequisites

There are no prerequisites to verify for this procedure


Appendix C

Standard:

Cue:

NOTE:

Comment:

SAT/UNSAT



Performance Step: 3

Procedure Step: 3.1.2

DETERMINE drywell bulk temperature by using the

appropriate calculation and the following recorders:

• RecorderTR-100A (RB 51' Elev.)

• Recorder IA55 (Panel 8R)

Form ES-C-1

From the initial conditions, determines TR-100A is available and IA55 is NOT available. Directs an EO to obtain temperature readings on TR-1 OOA using EMG-SP26 attachment EMG-SP26-1.

Provide a copy of the JPM Data Sheet with temperature values from TR-1 OOA.

If this JPM is to be performed as a Group, DELETE this step and handout the Date Sheet at the start of the JPM.


Appendix C

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Performance Step: 4

Procedure Step: 3.2.2.1

Using Attachment EMG-26-1, calculates T Avg Is

Determines T Avg Is is 204°F

Performance Step: 5


Using Attachment EMG-26-1, calculates T Avg II

Determines T Avg II is 215°F

Performance Step: 6


Using Attachment EMG-26-1, calculates T Avg Ill.

Determines T Avg Ill is 241°F

NRC RO Admin JPM 1

Form ES-C-1

Page 5 of 10

Appendix C

Standard:

Comment:

SAT/UNSAT



Performance Step: 7


Form ES-C-1

Using Attachment EMG-26-1, calculates T s (Bulk Drywell Temperature).

Determines T 8 (Bulk Drywell Temperature) is 206°F (+ 1 °F)

Task Standard: Bulk Drywell Temperature has been calculated.

JPM Stop Time: ___ _


Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response:

Result:


Validation of Completion

NRC RO Admin JPM 1

Satisfactory/Unsatisfactory

Examiner's Signature and Date:

NRC RO Admin JPM 1

Form ES-C-1

Page 7 of 10


JPM Setup

1. J PM Data Sheet with recorder TR-1 OOA on RB 51' filled out.

Form ES-C-1

2. Copy of procedure EMG-SP26, Rev 1, Determining Bulk Drywell Temperature


Appendix C

Initial Conditions:


STUDENT HANDOUT

Form ES-C-1

1. The plant was at rated power when an event occurred which required entry into the Primary Containment Control EOP

2. Computer point DWTEMP is questionable

3. Recorder IA55 has lost power

4. Recorder TR-1 OOA is operable

5. EMG-SP26, Determining Bulk Drywall Temperature has been completed through step 3.1.2

Task Cue:

Determine bulk Drywall temperature lAW Support Procedure 26, Determining Bulk Drywall Temperature, beginning at step 3.2



Data Sheet

TR-100A on RB 51'

Recorder Point Come ID PT

PT.1 TE-100A, El50' TE103A

PT. 2 TE-1008, El50' TE1038

PT. 3 TE-1 OOC, El 50' TE103C

PT. 4 TE-1000, El50' TE103D

PT. 5 TE-100E, El50' TE103E


PT. 6 TE-1 04A, El 93' TE104A

PT. 7 TE-1048, E193' TE1048

PT. 8 TE-104C, El93' TE104C

PT. 9 TE-1040, El93' TE104D

PT. 10 TE-104E, El93' TE104E


PT. 11 TE-105A, El95' TE105A

PT. 12 TE-1058, El95' TE1058

PT. 13 TE-105C, El95' TE105C

NRC RO Admin JPM 1

Form ES-C-1

Value {°F}

205

203

204

205

203

Value {°F}

214

216

215

214

216

Value {°F}

Upscale

240

242

Page 10 of 10


Facility: Oyster Creek Task No.: 2000101408

Task Title: Plot Heatup Rate


K/ A Reference: _2_. _1 .-'-25--'--'--(3-'-.9-'-) _______ _

Examinee: Examiner:


Method of Testing:

Simulated Performance Actual Performance -----

Classroom X Simulator __ .:....:__ __ Plant -----


Form ES-C-1

X


Initial Conditions:

1. The plant is starting-up after a refuel outage

2. The plant has been heating up for the last 2 hours during control rod withdrawals

3. Control rod withdrawals will be continuing at the start of the third hour (time 1000)

Task Standard: Heatup rate has been calculated lAW the JPM key

Required Materials: None.

General References:

1. 201, Plant Startup, Rev 73


Appendix C

Initiating Cue:


Form ES-C-1

Given RPV pressures/temperatures over the last 2 hours, perform the following:

1. Plot the RPV heatup rate lAW Procedure 201, Plant Startup, step 5.34 (see attached data)

2. Determine the hourly heatup rate between 0800 and 0900. Determine if the hourly heatup limit in procedure 201, HAS/HAS NOT been exceeded. If the limit has been exceeded, state what actions can be done to reduce the heatup rate.

3. Determine the hourly heatup rate between 0900 and 1000. Determine if the hourly heatup limit in procedure 201, HAS/HAS NOT been exceeded. If the lim it has been exceeded, state what actions can be done to reduce the heatup rate.






Form ES-C-1

Denote critical steps with a check mark ./

Standard:

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Performance Step: 1




Performance Step: 2

Procedure Step: Determine the Tsat by converting Reactor Pressure to its corresponding saturation temperature using the provided Temp/Press table

Determines the Tsat by converting Reactor Pressure to its corresponding saturation temperature using using the provided Temp/Press table and records the supplied table


Appendix C

Standard:

Comment:

SAT/UNSAT



Performance Step: 3

Form ES-C-"1

Procedure Step: Plot the heatup on the attached graph

Plots the heatup on the attached graph as shown in the Key

NRC RO Admin JPM 2 Page 4 of "14

Appendix C

Standard:

Comment:

SAT/UNSAT



Performance Step: 4

Form ES-C-1

Procedure Step: Determine the heatup rate for the first hour (time 0800- 0900)

Determines the heatup rate for the first hour (0800- 0900). The heatup rate is 79 °F/hr.


Appendix C

Standard:

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Standard:

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Performance Step: 5

Form ES-C-1

Procedure Step: Determine the heatup rate for the first hour (time 0800- 0900) is less than the procedural limit of 90 °F/hr (no actions are required)

Determines the heatup rate for the first hour (time 0800- 0900) is less than the procedural limit of 90 °F/hr (no actions are required)

Performance Step: 6

Procedure Step: Determine the heatup rate for the second hour (time 0900- 1 000)

Determines the heatup rate for the second hour (0900- 1 000). The heatup rate is 96.6 °F/hr.


Appendix C

Standard:

Comment:

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Standard:

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Performance Step: 7

Form ES-C-1

Procedure Step: Determine the heatup rate for the second hour (time 0900- 1 000) is greater than the procedural limit of 90 °F/hr

Determines the heatup rate for the second hour (time 0900-1 000) is greater than the procedural limit of 90 oF/hr. The heatup rate is 96.6 °F/hr.

Performance Step: 8

Procedure Step: Determine that the withdrawal of control rods should be delayed or performed more slowly (to reduce the heatup rate) or similar.

Determines that the withdrawal of control rods should be delayed or performed more slowly (to reduce the heatup rate) or similar.

Terminating Cue: Determines heatup rate for the 2nd hour is greater than procedural limit. Recommends action to reduce heatup rate.



KEY ....-... 630 LL

0 L- ;:~ -+--....._... Q) ~ 540 ::::J -co ~ 1------ ~ I c.--Q) ~

c.. 450 E Q) I ~j --+--1-- 360 c co 0 0 0 270 ~

0 1------(.) co

180 Q)

0: ~-

==rso::: I ~ -~-

!:;mri~ ·-

90 - - - -----I t="..-:= E:::::: I -----r- ~ ........... 1----~-:y I I """"..............:........,.- .

0 0 0.5 1 1.5 2 2.5 3 3.5 4

Hours

Time 0800 0810 0820 0830 0840 0850 0900 0910 0920 0930 0940 0950 1000

Press NA NA NA NA NA 27 30 60 80 110 130 144 160

Tsat. 195 208 229.8 247.8 2605 269.8 274.0 307.3 323.9 344.2 355.6 362.9 370.6 1


Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response:

Result:



NRC RO Admin JPM 2

--------------------



NRC RO Admin JPM 2

Form ES-C-1

Page 9 of 14


Simulator Setup

Form ES-C-1

1. Have a copy of procedure 201, Plant Startup, available upon request

2. Have a calculator for the applicant


Appendix C

Initial Conditions:


STUDENT HANDOUT

1 . The plant is starting-up after a refuel outage

Form ES-C-1

2. The plant has been heating up for the last 2 hours during control rod withdrawals

3. Control rod withdrawals will be continuing at the start of the third hour (time 1000)

Task Cue:

Given RPV pressures/temperatures over the last 2 hours, perform the following:

1. Plot the RPV heatup rate lAW Procedure 201, Plant Startup, step 5.34 (see attached data)





Provide your answers below and on the attached graph.

1. Provide the plot the attached graph.

2. Hourly heatup rate from 0800 - 0900 is: ______ _

Form ES-C-1

The hourly heatup limit in procedure 201, HAS/HAS NOT been exceeded. (circle one)

If exceeded, what actions can be done to reduce the heatup rate (be specific):

3. Hourly heatup rate from 0900 - 1000 is: ______ _

The hourly heatup limit in procedure 201, HAS/HAS NOT been exceeded. (circle one)

If exceeded, what actions can be done to reduce the heatup rate (be specific):


630 -lL t--- +--::;iii' 0 ..._.... ---1-----

<D 540 1-.

::J ~- 1------- ---...... ~ <D

450 a. E

-~ -;;;;iii' f----1--

~ 1---------

<D 1---

I-...... 360 c co -- f-------t------

0 0 () 270 1-.

0 ......

...... {) co

180 <D a: ~ ---- f---·

~-1--------

90 """ 1-

1-------1-- ~- -

0 0 0.5 1 1.5

Time 0800 0810 0820 0830 0840 0850 0900 0910 0920

Press NA NA NA NA NA 27 30 60 80

Tsat 195 208 229.8 247.8 260.5 ' -

NRC RO Admin JPM 2

f-- ----+ -- ---------,---

-- f---

-- f----

t--~

2

Hours

0930 0940

110 130

. ===t _...

-.;;

i----

2.5

0950 1000

144 160

Page 13 of 14

-.....;

f-----

---- f----

-- ------ -;;;;iii' --.......: --

--

--

.....,;;;: --

---

---+--- ===1

~

~ ....,.; -....;;.

3 3.5 4


Form ES-C-1

Saturation Temperature (degrees F) from Pressure (PSIG) in one pound increments To read temperature at 108 psig go to row iOx and column 8.

Note: 0 psig = 14.7 psi a 9 ~ 012 3 4 56 7 8

Ox 212.0 215.4 218.5 221.5 224.4 227.2 229.8 232.3 234.8 237.1 1x 239.4 241.6 243.7 245.8 247.8 249.8 251.7 253.5 255.3 257.1 2x 258.8 260.5 262.1 263.7 265.3 266.8 268.3 269.8 271.2 272.6 3x 274.0 275.4 276.7 278.1 279.4 280.6 281.9 283.1 284.4 285.6 4x 286.7 287.9 289.0 290.2 291.3 292.4 293.5 294.5 295.6 296.6 5x 297.7 298.7 299.7 300.7 301.7 302.6 303.6 304.6 305.5 306.4 6x 307.3 308.2 309.1 310.0 310.9 311.8 312.6 313.5 314.3 315.2 7x 316.0 316.8 317.7 318.5 319.3 320.1 320.8 321.6 322.4 323.2 8x 323.9 324.7 325.4 326.1 326.9 327.6 328.3 329.0 329.8 330.5 9x 331.2 331.9 332.6 333.2 333.9 334.6 335.3 335.9 336.6 337.2

1 Ox 337.9 338.5 339.2 339.8 340.5 341.1 341.7 342.3 342.9 343.6 11 X 344.2 344.8 345.4 346.0 346.6 347.2 347.7 348.3 348.9 349.5 12x 350.1 350.6 351.2 351.8 352.3 352.9 353.4 354.0 354.5 355.1 13x 355.6 356.2 356.7 357.2 357.8 358.3 358.8 359.3 359.8 360.4 14x 360.9 361.4 361.9 362.4 362.9 363.4 363.9 364.4 364.9 365.4 15x 365.9 366.4 366.8 367.3 367.8 368.3 368.8 369.2 369.7 370.2 16x 370.6 371.1 371.6 372.0 372.5 372.9 373.4 373.9 374.3 374.8 17x 375.2 375.6 376.1 376.5 377.0 377.4 377.8 378.3 378.7 379.1 18x 379.6 380.0 380.4 380.8 381.3 381.7 382.1 382.5 382.9 383.3 19x 383.8 384.2 384.6 385.0 385.4 385.8 386.2 386.6 387.0 387.4 20x 387.8 388.2 388.6 389.0 389.4 389.8 390.2 390.5 390.9 391.3 21 X 391.7 392.1 392.5 392.8 393.2 393.6 394.0 394.3 394.7 395.1 22x 395.5 395.8 396.2 396.6 396.9 397.3 397.7 398.0 398.4 398.7 23x 399.1 399.4 399.8 400.2 400.5 400.9 401.2 401.6 401.9 402.3 24x 402.6 403.0 403.3 403.7 404.0 404.3 404.7 405.0 405.4 405.7 25x 406.0 406.4 406.7 407.0 407.4 407.7 408.0 408.4 408.7 409.0 26x 409.4 409.7 410.0 410.3 410.7 411.0 411.3 411.6 411.9 412.3 27x 412.6 412.9 413.2 413.5 413.8 414.2 414.5 414.8 415.1 415.4 28x 415.7 416.0 416.3 416.6 417.0 417.3 417.6 417.9 418.2 418.5 29x 418.8 419.1 419.4 419.7 420.0 420.3 420.6 420.9 421.2 421.5 30x 421.8 422.1 422.3 422.6 422.9 423.2 423.5 423.8 424.1 424.4 31x 424.7 425.0 425.2 425.5 425.8 426.1 426.4 426.7 426.9 427.2 32x 427.5 427.8 428.1 428.4 428.6 428.9 429.2 429.5 429.7 430.0 33x 430.3 430.6 430.8 431.1 431.4 431.7 431.9 432.2 432.5 432.7 34x 433.0 433.3 433.5 433.8 434.1 434.3 434.6 434.9 435.1 435.4 35x 435.7 435.9 436.2 436.4 436.7 437.0 437.2 437.5 437.7 438.0 36x 438.3 438.5 438.8 439.0 439.3 439.5 439.8 440.0 440.3 440.6 37x 440.8 441.1 441.3 441.6 441.8 442.1 442.3 442.6 442.8 443.1 38x 443.3 443.5 443.8 444.0 444.3 444.5 444.8 445.0 445.3 445.5 39x 445.7 446.0 446.2 446.5 446.7 447.0 447.2 447.4 447.7 447.9 40x 448.2 448.4 448.6 448.9 449.1 449.3 449.6 449.8 450.0 450.3 41x 450.5 450.7 451.0 451.2 451.4 451.7 451.9 452.1 452.4 452.6 42x 452.8 453.1 453.3 453.5 453.7 454.0 454.2 454.4 454.6 454.9 43x 455.1 455.3 455.5 455.8 456.0 456.2 456.4 456.7 456.9 457.1 44x 457.3 457.6 457.8 458.0 458.2 458.4 458.7 458.9 459.1 459.3 45x 459.5 459.8 460.0 460.2 460.4 460.6 460.8 461.1 461.3 461.5 46x 461.7 461.9 462.1 462.3 462.6 462.8 463.0 463.2 463.4 463.6 47x 463.8 464.0 464.2 464.5 464.7 464.9 465.1 465.3 465.5 465.7 48x 465.9 466.1 466.3 466.5 466.7 467.0 467.2 467.4 467.6 467.8 49x 468.0 468.2 468.4 468.6 468.8 469.0 469.2 469.4 469.6 469.8 50x 470.0 470.2 470.4 470.6 470.8 471.0 471.2 471.4 471.6 471.8 51x 472.0 472.2 472.4 472.6 472.8 473.0 473.2 473.4 473.6 473.8 52x 474.0 474.2 474.4 474.6 474.8 475.0 475.2 475.3 475.5 475.7




Task Title: Perform a Reactor Heat Balance Manually


K/ A Reference: _2_._2._1_2 -'-(3_.__,7)'----------

Examinee: Examiner:


Method of Testing:


Classroom X Simulator --~--

Plant -----


Form ES-C-1

X



Appendix C

Initial Conditions:


1. The reactor has been steady at full power for several hours

Form ES-C-1

2. The most recent stable PPC Core Thermal Power (15-minute average) was 1928 MWth

3. All prerequisites to perform this procedure have been met

4. Calculating RWCU system differential temperature is not required

5. The following indications are provided:

a. APRMs indicate 1 00% power

b. RPV water level instrument NR GEMAC indicates 161"

c. Local total Feedwater ~P from the venturi transmitter (FT-422-1) indicates 491.0 inches of water

d. Core ~P indicates 16.5 psid

e. Reactor pressure (NR recorder Panel 5F/6F) indicates 1020 psig

f. Feedwater temperature (recorder Panel 5F/5F) indicates 312 oF

g. Total steam flow (recorder Panel 5F/6F) indicates 7.1 Mlb/hr

h. Total recirculation flow (recorder Panel 3F) indicates 15 x 104 gpm

i. RWCU flow (recorder Panei3F) indicates 400 gpm

Task Standard: Determines bulk Drywell temperature lAW Support Procedure 26, Determining Bulk Drywell Temperature

Required Materials: Calculator

General References:

1. 1001.6, Core Heat Balance and Feedwater Flow Calculation, Rev 29

Initiating Cue: Calculate core thermal power (CTP) lAW Procedure 1001.6, Core Heat Balance and Feedwater Flow Calculation - Power Range. Report if it is conservative or not.






Form ES-C-1

Denote critical steps with a check mark -/

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

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Performance Step: 1




Performance Step: 2

Procedure Step: Verifies Prerequisites and reviews Precautions and Limitations.

All prerequisites to perform this procedure have been met and is stated in the Initial Conditions.


Appendix C

Standard:

Comment:

SAT/UNSAT



Performance Step: 3

Procedure Step:

Form ES-C-1

Calculates feedwater flow per Method 1 by performing the following:

1. Record local total Feedwater ~P in inches of water from the venturi transmitter (FT-422-1) in the Feedwater Pump Room.

2. Records feedwater temperature from 5F/6F Recorder (1001 01 ), rounded to nearest whole degree (critical task).

3. Obtain the specific volume (v) of the Feedwater at 11 00 psia and the temperature above from Attachment 1001.6-3 and records (critical task).

4. Calculates total Feedwater flow: F = 0.0429387 SQRT (L~P/v) (critical task).

Calculates feedwater flow per Method 1 by performing the following:

1. Record local total Feedwater ~P in inches of water from the venturi transmitter (FT-422-1) in the Feedwater Pump Room. (491.0)

2. Records feedwater temperature from 5F/6F Recorder (100101), rounded to nearest whole degree (critical task). (312 OF)

3. Obtains the specific volume (v) of the Feedwater at 11 00 psia and the temperature above from Attachment 1001.6-3 and records (critical task). (0.01749)

4. Calculates total Feedwater flow (critical task). (F = 7 .19)


Appendix C

Standard:

Comment:

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Standard:

Comment:

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Performance Step: 4

Procedure Step:

Form ES-C-1

Record reactor pressure to the nearest whole pound. (Narrow range recorder on Panel 5F/6F.

Records reactor pressure to the nearest whole pound. (Narrow range recorder on Panel 5F/6F. (1 020 psig)

Performance Step: 5

Procedure Step:

Record feedwater temperature to the nearest whole degree. (Recorder on Panel 5F/6F)

Records feedwater temperature to the nearest whole degree. (Recorder on Panei5F/6F (312 °F)


Appendix C

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT



Performance Step: 6

Procedure Step:

Form ES-C-1

Record recirculation flow to the nearest thousand gpm. (Recorder on Panei3F)

Records recirculation flow to the nearest thousand gpm. (Recorder on Panel 3F) (15)

Performance Step: 7

Procedure Step:

Calculate the reactor absolute pressure by adding the value of step 4 (procedure step 5.2.1) + 14.7 pounds pressure

Calculates the reactor absolute pressure by adding the value of step 4 (procedure step 5.2.1) + 14.7 pounds pressure (1034.7 psia)


Appendix C

Standard:

Comment:

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Standard:

Comment:

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Performance Step: 8

Procedure Step:

Form ES-C-1

Record Main Steam enthalpy from Attachment 1001.6-5, at saturated conditions using calculated absolute pressure.

Records Main Steam enthalpy from Attachment 1001.6-5, at saturated conditions using calculated absolute pressure. (1191.61)

Performance Step: 9

Procedure Step:

Record the Feedwater enthalpy from Attachment 1001.6-6 for compressed water at 1100 psia using Feedwater temperature.

Records the Feedwater enthalpy from Attachment 1001.6-6 for compressed water at 1100 psia using Feedwater temperature. (283.94)


Appendix C

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Standard:

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Standard:

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Performance Step: 10

Procedure Step:

Form ES-C-1

Calculate the difference of the Main Steam and Feedwater enthalpies.

Calculates the difference of the Main Steam and Feedwater enthalpies and records. (1191.61 - 283.94 = 907.67)


Procedure Step:

Record Total Flow Venturi method FLO (tot) from line (D) of the Feedwater flow calculation worksheet.

Records Total Flow Venturi method FLO (tot) from line (D) of the Feedwater flow calculation worksheet. (7.19 Mlbm/hr)


Appendix C

Standard:

Comment:

SAT/UNSAT

-----

Standard:

Comment:

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Procedure Step:

Form ES-C-1

Calculate the product of the Feedwater flow and the enthalpy difference to obtain MBTU/hr.

Calculates the product of the Feedwater flow and the enthalpy difference to obtain MBTU/hr and record. (6526.15)


Procedure Step:

Convert MBTU/hr to Megawatts. (MBTU/hr x 0.293) and record.

Converts MBTU/hr to Megawatts. (MBTU/hr x 0.293) and record. (1912.16)


Appendix C

-----

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT




Procedure Step:

Form ES-C-1

Record RWCU flow to the nearest gpm (recorder panel 3F) on line (K) of Attachment 1001.6-2.

Records RWCU flow to the nearest gpm (recorder panel 3F) on line (K) of Attachment 1001.6-2. (400 gpm)


Procedure Step:

Calculate the CRD, recirc. pump power, RWCU and ambient losses adjustment (Fixed Losses), per the following equation.

Fixed Losses= [(K) x 0.0136] + 9.0

Calculate the CRD, recirc. pump power, RWCU and ambient losses adjustment (Fixed Losses), per the following equation.

Fixed Losses= [(K) x 0.0136] + 9.0 (400 x 0.0136] + 9.0 = 14.44)


Appendix C

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT




Procedure Step:

Form ES-C-1

Add the Fixed Losses from line (L) to the Megawatts from Line (J) and record the Calculated (CTP) on line (N).

Add the Fixed Losses from line (L) to the Megawatts from Line (J) and record the Calculated (CTP) on line (N). (1926.60 MW)


Procedure Step:

Record PPC Core Thermal Power (CTP) on Line M. (Use the 15 min. average value after reactor power is stable for at least 15 minutes.)

Records PPC Core Thermal Power (CTP) on Line M. (1928)


Appendix C

-----

Standard:

Comment:

SAT/UNSAT




Procedure Step:

Form ES-C-1

Subtract the Calculated CTP from the PPC Core Thermal Power [Line (M)- line (N)].

Subtracts the Calculated CTP from the PPC Core Thermal Power [Line (M)- line (N)]

(1.4)

Task Standard: Core Thermal Power is calculated



KEY

Pre parer: Date: Time: Prerequisites met: BB

Initials

Method 1: Total Flow Venturi Calculation

A 5.1.1.1 DP From Total Flow Venturi Transmitter (FT-422-1) Local Transmitter DP Reading 491.0 in H20

B 5.1.1.2 Feed water Temperature (ID 101 ) Panel 5F/6F Recorder 312 deg F

c 5.1.1.3 Specific Volume at 1100 psia and (B) Attachment 1001.6-3 or ASME Steam Tables 0.01749 ft3/lbm

D 5.1.1.4 TOTAL FEEDWATER FLOW FT = 0.0429387 x SQRT[(AJ I (C)] 7.19 Mlbm/hr

Metlwd 2: 3 Loop Flow Calculation A Loop BLoop CLoop I

IE D = :N:A A= :N:A B = :N:A E = :N:A c = :N:A F = :N:A 5.1.2.1 Feedwater Pump Room Nozzle DP Gauges (RV45) in H20

F 5.1.2.2 Average Nozzle DP in H20

Pos 15 = :N:A Pos 16 = :N:A Pos 17 = :N:A G 5.1.2.3 Loop Temperature: Recorder 13R-005 dcg F

Loop Specific Volume at 1400 psia: :N:A :N:A :N:A H 5.1.2.4

Attachment 1001.6-4 or ASME Steam Tables ft'/Ibm

I 5.1.2.5 Nozzle Discharge Coefficient x Conversion Factor 0.02252 0.02291 0.02269

J 5.1.2.5 Loop Flow:

FA= :N:A FE= :N:A Fe= :N:A Mlbm/hr = (/) x SQRT[I F) I (H)]

K 5.1.2.6 TOTAL FEEDWATER FLOW FT =FA+ FE+ Fe :N:A Mlbm/hr


KEY A 5.2.1 Reactor Pressure {lD-45) Panel5F/6F Narrow Range Recorder 1020 psig

B 5.2.2 Feed water Temperature (lD 101) Panel 5F/6F Recorder 312 degF

c 5.2.3 Recirculation Row Panel 3F Recorder 15 104 gpm

D 5.2.4 Reactor Absolute Pressure (A)+ 14.7 1034.7 psia

E 5.2.5 Main Steam Enthalpy (hMs) Attachment 1001.6-5 or ASME Steam Tables 1191.61 BTU/Ibm

F 5.2.6 Feedwater Enthalpy (hpw) Attachment 1001.6-6 or ASME Steam Tables 283.94 BTU/Ibm

G 5.2.7 Enthalpy Difference (hMs- hFw) (E)-(F) 907.67 BTU/lbm

H 5.2.8 Total Feedwater How Attachment 1001.6-L iDJ or (K) 7.19 Mlbmlhr

I 5.2.9 Feedwater Flow x Enthalpy Difterence (Hi x (G) 6526.15 MBTU/hr

J 5.2.10 Conversion to MWm 0.293 X ( [) 1912.16 MWm

K 5.2.11 RWCUFlow Panel 3F Recorder 400 gpm

L 5.2.12 Fixed Losses [(K) x 0.0136) + 9.0 14.44 MWm

M 5.2.14 PPC Core Thermal Power (CTP) PPC CTP 15 Minute Average 1928 Ivi\Vm

N 5.2.13 Calculated Core Thermal Power (l) + (L) 1926.60 MWm

1.4

f-=-0 5.2.15 Core Them1al Power Comparison (M)- (NI X Positive Value-+ MWm

Conservative t--

Negative Value-+ Non-Consen•ative

Comments:


Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response:

Result:



NRC RO Admin JPM 3



NRC RO Admin JPM 3

Form ES-C-1

Page 15 of 17


JPM Setup

Form ES-C-1

1. Have a marked up copy of procedure 1001.6 rev 29 for the applicant 2. Have a calculator for the applicant


Appendix C

Initial Conditions:


STUDENT HANDOUT

1. The reactor has been steady at full power for several hours

Form ES-C-1

2. The most recent stable PPC Core Thermal Power (15-minute average) was 1928 MWth

3. All prerequisites to perform this procedure have been met

4. Calculating RWCU system differential temperature is not required

5. The following indications are provided:

j. APRMs indicate 1 00% power

Task Cue:

k. RPV water level instrument NR GEMAC indicates 161"

I. Local total Feedwater LlP from the venturi transmitter (FT -422-1) indicates 491.0 inches of water

m. Core LlP indicates 16.5 psid

n. Reactor pressure (NR recorder Panel 5F/6F) indicates 1020 psig

o. Feedwater temperature (recorder Panel 5F/5F) indicates 312 oF

p. Total steam flow (recorder Panel 5F/6F) indicates 7.1 Mlb/hr

q. Total recirculation flow (recorder Panel 3F) indicates 15 x 104 gpm

r. RWCU flow (recorder Panel 3F) indicates 400 gpm

Calculate core thermal power (CTP) lAW Procedure 1001.6, Core Heat Balance and Feedwater Flow Calculation- Power Range. Report if it is conservative or not.



Form ES-C-1

Facility: Oyster Creek Task No.: EPAA105101

Task Title: Review a Completed State/Local Notification Form


K/ A Reference: _8_2_._4._3_9_,_(3_.~9)'----------

Examinee: Examiner:


Method of Testing:


Classroom X Simulator -----'--- Plant -----



Initial Conditions:

1. The plant was at rated power when an event occurred

2. The Shift Manager has assumed the role of Shift Emergency Director (SED)

3. The SED has made his initial emergency declaration of an Unusual Event 4 minutes ago (EAL MU4: UNPLANNED loss of safety system annunciation or indication in the control room for 15 minutes or longer.)

4. No radiological release is in progress or expected

5. You are fulfilling the role as Shift Communicator

6. Wind direction is from 215 o

7. Wind speed is 18 MPH

Initiating Cue: The SED has just handed you the completed State/Local Notification Form. Review the State/Local Notification Form (page 1 only). State if the Form is ready to make notifications, or not ready. If not ready to make notifications, state all reasons why.

Required Materials: None


Appendix C

General References:


1. EP-MA-114-100-F-03, State/Local Notification Form, Rev H

Form ES-C-1

2. EP-AA-1 010, Radiological Emergency Plan Annex for Oyster Creek Station, Rev 7

3. EP-MA-114-1 00, Mid-Atlantic State/Local Notifications

4. EP-AA-112-1 00-F-05, Mid-Atlantic Shift Communicator (CR) Checklist

Task Standard: Reviews the completed State/Local Notification Form (page 1 only), and notes the discrepancies as stated in this JPM.






Form ES-C-1


Standard:

Comment:

SAT/UNSAT

Performance Step: 1




NOTE: The following steps may be performed in any order.

Standard:

Comment:

SAT/UNSAT

Performance Step: 2

Procedure Step:

Review the State/Local Notification Form (page 1 ). Recognizes the Form is not ready to make notifications for the following reasons:

• It is not signed by the Shift Emergency Director (SED)

Reviews the State/Local Notification Form (page 1 ). Recognizes the Form is not ready to make notifications for the following reasons:

• It is not signed by the Shift Emergency Director (SED)


Appendix C

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT



Performance Step: 3

Procedure Step:

Form ES-C-1


• "Initial Declaration" is not selected but should be selected


• "Initial Declaration" is not selected but should be selected

Performance Step: 4

Procedure Step:


• "DECLARED AT" Time is incorrect. It should be 4 minutes, NOT 8 minutes.


• "DECLARED AT" Time is incorrect. It should be 4 minutes, NOT 8 minutes.


Appendix C

Standard:

Comment:

SAT/UNSAT



Performance Step: 5

Procedure Step:

Form ES-C-1


• "No Non-routine Radiological Release" should be selected, but is not selected


• "No Non-routine Radiological Release" should be selected, but is not selected


Appendix C

Standard:

Comment:

SAT/UNSAT



Performance Step: 6

Procedure Step:

Form ES-C-1


• Wind speed and wind direction values are reversed on the form


• Wind speed and wind direction values are reversed on the form


Appendix C

Standard:

Comment:

SAT/UNSAT



Performance Step: 7

Procedure Step:

Form ES-C-1


• The "Verified With" block is not filled out.


• The "Verified With" block is not filled out.

Terminating Cue: Reviews the completed State/Local Notification Form (page 1 only), and notes the discrepancies as stated in this JPM.

JPM Stop Time: ____ _


Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response:

Result:



NRC RO Admin JPM 4



NRC RO Admin JPM 4

Form ES-C-1

Page 8 of 12


JPM Setup

1. Have a copy of the following to hand out to the applicant:

a. EP-MA-114-1 00, Mid-Atlantic State/Local Notifications

Form ES-C-1

b. EP-AA-112-1 00-F-05, Mid-Atlantic Shift Communicator (CR) Checklist


Appendix C

Initial Conditions:


STUDENT HANDOUT

1. The plant was at rated power when an event occurred

Form ES-C-1


3. The SED has made his initial emergency declaration of an Unusual Event 4 minutes ago (EAL MU4: UNPLANNED loss of safety system annunciation or indication in the control room for 15 minutes or longer.)

4. No radiological release is in progress or expected

5. You are fulfilling the role as Shift Communicator

6. Wind direction is from 215 o

7. Wind speed is 18 MPH

Task Cue:

The SED has just handed you the completed State/Local Notification Form. Review the State/Local Notification Form (page 1 only). State if the Form is ready to make notifications, or not ready. If not ready to make notifications, state all reasons why.



STUDENT HANDOUT

Form ES-C-1

EP-MA-114-1 00-F-03 Revision H Page 1 of 2

STATE I LOCAL NOTIFICATION FORM (Or Electronic Facsimile)

MESSAGE NO. 1

VERIFIED WITH: EMERGENCY DIRECTOR APPROVAL:

1 . CALL STATUS is: 2. This is* at Oyster Creek Generating Station.

[ ] This is a DRILL. My phone number is * The current time is * ---(X] This is an ACTUAL EVENT *Completed by Communicator at time notification is performed: use PPC time

24-hour clock

3. EMERGENCY CLASSIFICATION: DECLARED AT: THIS REPRESENTS A/AN:

[X] UNUSUAL EVENT [ ]INITIAL DECLARATION

[ ] ALERT TIME: 8 minutes ago [ ] ESCALATION

[ ] SITE AREA EMERGENCY (use PPC time in 24-hour clock) []NO CHANGE

[ ]GENERALEMERGENCY [ ] REDUCTION

[]RECOVERY DATE: Today IN CLASSIFICATION STATUS

[ ] TERMINATION

4. EMERGENCY ACTION LEVEL (EAL) NUMBER IS: Unusual Event: MU4

BRIEF NON-TECHNICAL DESCRIPTION:

MU4: UNPLANNED loss of safety system annunciation or indication in the control room for 15 minutes or longer.)

5. NON-ROUTINE RADIOLOGICAL RELEASE STATUS:

[ ] NO non-routine radiological release in progress

[ ] AIRBORNE non-routine radiological release in progress

[ ] LIQUID non-routine radiological release in progress

[ ] Non-routine radiological release TERMINATED

6. METEOROLOGY:

Wind Direction is FROM: 18 (degrees)

Wind Speed is: 215° (miler per hour)

7. CONCLUSION: [ ] This is a DRILL. [X] This is an ACTUAL EVENT.

• PERFORM final roll call (General Emergency Only)

• ASK if there is any questions about the information provided and PROVIDE clarification as needed .

• READ: "This concludes the notification message"



Form ES-C-1

EP-MA-114-100-f-03 Re\llSfOn H Page~ of::

STATE /LOCAL NOTIFICATION FORM

Mt:SSAGE NO ----

1S Mu•Hdl' Notifu:.ihqan, , ) Mcnutt Motlfte.tltons UNUSUAL EVENT~ AlERT or :Stl( AAEA GEN£RAL EMERGENCY

EUERGENC Y "f '""'" ~:':'~~;:.'f...,.; ;:'4 ·hour d~k l ., t¥ .r (,;)f!t;v.~M :::!4-hour c-Jcoek)

NJSP Off1~ of EmergHiey Manageme-nt

~·~-.te ::-.e-;: ~ QL.oO·~·Gc.3-c·;.~.::

lnft.&Jil Roll C.~!! !Twr·~!

Final Roll CJill

.,. ff.i- -----

VERIACATION CALL RECEIVED

·rr~: -----

fOllOW-UP NQt1FICATIONS

NR{. R•,_lld>tnt ll'l'iiP'-'d~

r ~;:, '"' · :t:c • ~! -; \ ~· ,t9a .:~os r

NRC RO Admin JPM 4

VERifiCATION CAll RECEIVED

Ff!-'~on C:.;r1x1e-: -------

FOLLOW-UP NOTIFICATIONS.

NRC Rt:-s.'ll..,.r;: ~s.r-e-;::or

e.·c'"!'·f;·-::t:,D:? ~ 215~~-tOs7

Tn1.,~: -----

I, ;

Page 12 of 12



Task Title: Determine Operator Qualifications Using LMS

Job Performance Measure No.: NRC SRO Admin JPM 1

K/ A Reference: _8_2_._1 . ...:..8_,_(_4._1 '-) _______ _

Examinee: Examiner:


Method of Testing:




Form ES-C-1

X


Initial Conditions:

1. The plant is at rated power

Task Standard: Determines which Operators are qualified to perform the tasks using LMS


General References:

1. NGET

Initiating Cue: Given the LMS sheets and the tasks required, determine which Operator is qualified to perform the tasks. Today's date is June 20, 2014.


Validation Time: 9 minutes

NRC SRO Admin JPM 1 Page 1 of 7



Form ES-C-1

Denote critical steps with a check mark ../

Standard:

Comment:

SAT/UNSAT

Standard:

NOTE:

Comment:

SAT/UNSAT

Performance Step: 1




Performance Step: 2

Procedure Step:

Reviews the tasks and the LMS sheets and determines who is qualified to perform the tasks as shown on the KEY.

Reviews the tasks and the LMS sheets and determines who is qualified to perform the tasks as shown on the KEY.

Even though this JPM only has one (1) critical step, it is a multipart JPM and all parts must be correct for this critical step to be SAT.

Terminating Cue: Determines which Operators are qualified to perform the tasks using LMS



Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:



NRC SRO Admin JPM 1

Number of Attempts: __________ _

Time to Complete:

Question:

Response:

Result: Satisfactory/Unsatisfactory


NRC SRO Admin JPM 1

Form ES-C-1

Page 3 of 7


Setup

Form ES-C-1

1. Have LMS sheets (RO 1.doc, RO 2.doc, RO 3.doc, EO 4.doc, EO 5.doc, and EO 6.doc).


Appendix C

Task Number

1

2

3

4

5


Task Descrigtion

Form ES-C-1

Write a clearance (tagout) for a system (which will include disabling fire suppression systems)

Qualification required:

• Clearance and Tagging Writer (Oyster Creek)

• N-OC-SA-CT _WRITER

Review and approve the clearance

• Clearance and Tagging Approver (Oyster Creek)

• N-OC-SA-CT _APPROVE A

Hang/remove the tags and align the systems lAW the clearance

• Clearance and Tagging Applier/Remover(Oyster Creek)

• N-OC-SA-CT _APPLIERREMOVER

Perform the duties of a fire watch while the clearance is active

• Fire Extinguisher (Fire Watch)

• N-AN-SA-FI REWATCH

Once the clearance is removed and the system is pressurized, perform a VT-2 inspection

• •

VT2 QUALIFIED AT OC

N-OC-NDE-VT2 QUAL

EXAM KEY

NRC SAO Admin JPM 1 Page 5 of 7

Appendix C

Oeerator Task 1

RO 1 No

R02

R03

E04 No

E05 No

E06 No

NRC SRO Admin JPM 1


Task 2

No

No

No

No

No No

EXAM KEY

Form ES-C-1

Task4

No

No No

No

No

No

Page 6 of 7

Appendix C

Facility:

Task Title:

Oyster Creek


Task No.:

Applying Work Hour Rules


K/ A Reference: _G_._2_.1_.5__,__(3_.9--'-) _______ _

Examinee: Examiner:


Method of Testing:




Form ES-C-1

X


Initial Conditions:

1. The plant is at reduced power during coastdown at the end of the operating cycle and is preparing for a refuel outage starting in a few days

2. The Operators shown have been off for the 6-day period (MondaySaturday) prior to the schedule provided

3. The schedule shows the Reactor Operator work schedule for the next 9 days in order to support outage readiness for 3 Reactor Operators

4. Shift turnover is NOT included in the schedule shown [each turnover (oncoming and off-going) is 15 minutes in length]

5. The average minimum days-off rule and 54-hr rule has already been verified as satisfactory

Task Standard: The 10CFR26 Work Hour Limits are violated by Hyman Rickover and Albert Einstein, but NOT violated by Robert Oppenheimer, for the reasons given.



Appendix C

General References:


Form ES-C-1

1. LS-AA-119, Fatigue management and Work Hour Limits, revision 10

2. LS-AA-119-1003, Calculating Work Hours, Revision 2

Initiating Cue: lAW LS-AA-119-1003, Calculating Work Hours, determine for each Operator if the schedule violates the 1 OCFR26 Work Hour Limits. For any violations, state the work hour limit that will be exceeded.






Form ES-C-1


Standard:

Comment:

SAT/UNSAT

Performance Step: 1




Note: The steps may be completed in any order.

./ Performance Step: 3

Standard:

Comment:

SAT/UNSAT

Procedure Step: Determine that Work Hour Limits for Hyman Rickover is violated

Determines that Work Hour Limits Waiver for Hyman Rickover is violated


Appendix C

Standard:

Comment:

SAT/UNSAT

-----

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:



Performance Step: 4

Form ES-C-1

Procedure Step: Determine that Work Hour Limits violation for Hyman Rickover is due to less than a 10-hour break between successive work periods

Determine that Work Hour Limits violation for Hyman Rickover is due to less than a 1 0-hour break between successive work periods

Performance Step: 5

Procedure Step: Determine that Work Hour Limits for Albert Einstein is violated

Determines that Work Hour Limits for Albert Einstein is violated

Performance Step: 6

Procedure Step: Determine that Work Hour Limits violation for Albert Einstein is due more than 26 hours in a 48 hour period

Determines that Work Hour Limits violation for Albert Einstein is due more than 26 hours in a 48 hour period


Appendix C

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT



Performance Step: 7

Form ES-C-1

Procedure Step: Determine that Work Hour Limits for Robert Oppenheimer is not violated

Determines that Work Hour Limits for Robert Oppenheimer is not violated

Terminating Cue: The 1 OCFR26 Work Hour Limits are violated by Hyman Rickover and Albert Einstein, but NOT violated by Robert Oppenheimer, for the reasons given.



Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:



NRC SAO Admin JPM 2


Time to Complete:

Question:

Response:



NRC SAO Admin JPM 2

Form ES-C-1

Page 6 of 10


EXAM KEY

Form ES-C-1

Hyman Rickover: Worr<.. Hour LimitS IS VIOlated due to ess than a 1 0-hour break between successive work periods (between completing shift at 2400 on July 9 and starting shift at 0800 on July 1 0).

~ Sunda~ Monda~ Tuesda~ Wednesda~ Thursda~ Fridax Saturda~

Jui~S Jul~6 Jul~7 Jul~ 8 Jul~9 Jul~ 10 Jul~ 11

Hyman On-shift On-shift On-shift On-shift On-shift On-shift JIT Rickover

0800-2000 0800-2000 0800-2000 0800-1600 1600-2400 0800- Training 1600 0800-1600

Total 12 24 36 44 52 60 68 Hours

(Daily) (12) (12) (12) (8) (8) (8) (8)

Albert Einstein: Work Hour Limits is violated due to exceeding 26 hours in a 48 hour period (28 hours worked on July 6 and July 7)

~ Sunda~ Monda~ Tuesda~ Wednesda~ Thursda~ Frida~ Saturda~

Jui~S Jul~ 6 Jul~7 Jul~ 8 Jul~9 Jul~ 10 Jul~ 11

Albert On-shift On-shift On-shift On-shift

JIT On-shift On-shift Einstein Training

0800-1600 0800-2200 0800-2200 0800-2000 0800-1600

0800-1600 0800-1400

Total 8 22 36 48 56 64 72 Hours

(Daily) (8) (14) (14) (12) (8) (8) (8)

Robert Oppenheimer: No Work Hour Limits is exceeded.

~ Sunda~ Monda~ Tuesda~ Wednesda~ Thursda~ Frida~ Saturda~

Jul~5 Jul~6 Ju1~7 Jul~ 8 Jul~9 Jul~ 10 Jul~ 11

Robert On-shift On-shift On-shift JIT On-

Oppenheimer On-shift shift Sick 0800- 0800- 0800- Training

0800-2000 0800- Day 2000 2000 2000 0800-1600 2000

Total Hours 12 24 36 44 56 68 68 (Daily)

(12) (12) (12) (8) (12) ( 12) (0)



Simulator/JPM Setup

Form ES-C-1

1. Provide a copy of LS-AA-119-1 003, Calculating Work Hours, to the applicant

2. Have a copy of LS-AA-119, Fatigue Management and Work Hour Limits, available on request


Appendix C

Initial Conditions:


STUDENT HANDOUT

Form ES-C-1

1. The plant is at reduced power during coastdown at the end of the operating cycle and is preparing for a refuel outage starting in a few days

2. The Operators shown have been off for the 6-day period (MondaySaturday) prior to the schedule provided

3. The schedule shows the Reactor Operator work schedule for the next 9 days in order to support outage readiness for 3 Reactor Operators

4. Shift turnover is NOT included in the schedule shown [each turnover (oncoming and off-going) is 15 minutes in length]

5. The average minimum days-off rule and 54-hr rule has already been verified as satisfactory

Task Cue:

lAW LS-AA-119-1003, Calculating Work Hours, determine for each Operator if the schedule violates the 1 OCFR26 Work Hour Limits. For any violations, state the work hour limit that will be exceeded.


Appendix C

Name Sunda~

Jul~ 5

Hyman On-shift

Rickover 0800-2000

Albert On-shift

Einstein 0800-1600

Robert On-shift

Oppenheimer 0800-2000

NRC SAO Admin JPM 2


Form ES-C-1

STUDENT HANDOUT

Monda~ Tuesda~ Wednesda~ Thursda~ Frida~

Jul~6 Jul~7 Jul~8 Jul~9 Jul~ 10

On-shift On-shift On-shift On-shift On-shift

0800-0800-2000 0800-1600 1600-2400

0800-2000 1600

On-shift On-shift On-shift JIT On-shift

0800- Training 0800-2200

0800-2200 0800-2000 0800-1600 1600

On-shift On-shift JIT On-shift On-shift

0800- Training 0800-2000

0800-2000 0800-1600

0800-2000 2000

Page 10 of 10

Saturda~ Sunda~ Monda~

Jul~ 11 Jul~ 12 Jul~ 13

JIT Training OFF OFF 0800-1600

On-shift OFF OFF

0800-1600

Sick OFF OFF

Day

Appendix C



Task No.: 3420302026

Form ES-C-1

Task Title: Review Surveillance Test 619.3.016, High Drywall Pressure Scram Test and Calibration

Job Performance Measure No.: NRC SRO ADMIN JPM3

K/ A Reference: _G;::_2.:...:.·=2 . .:...:.1=2_._( 4.:...:.·~1 ),___ ______ _

Examinee: Examiner:


Method of Testing:





Initial Conditions:

1 . The plant is at rated power

2. Surveillance Test 619.3.016, High Drywall Pressure Scram Test and Calibration, was just completed

Task Standard: Section 7.0, Acceptance Criteria, is reviewed and found to be unsatisfactory due to sensor RE04A not meeting the criteria. Tech Spec required actions are stated.

Required Materials: A completed 619.3.016


Appendix C

General References:


Form ES-C-1

1. 619.3.016, High Drywell Pressure Scram Test and Calibration, Revision 33

2. Tech Spec Table 3.1.1

3. GE 237E566, Reactor Protection System, sheets 1 and 5

4. 420, Instrumentation Setpoints, Revision 13

5. LS-AA-125, Corrective Action Program (CAP) Procedure, Revision 17

Initiating Cue: Perform the Acceptance Criteria review of 619.3.016, High Drywell Pressure Scram Test and Calibration. Note any discrepancies, and state the required actions, if any.






Form ES-C-1

Denote critical steps with a check mark ~

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT

Performance Step: 1




Performance Step: 2

Procedure Step: 7.1

If the following criteria are met, components tested by this procedure meet Technical Specifications requirements for operability.

As-Left trip value for all sensors is:

1. Unadjusted: 2.9 ± 0.1 psig (2.8 to 3.0) OR

2. Adjusted: 2.9 ± 0.05 psig (2.85 to 2.95)

Reviews Acceptance Criteria of 619.3.016, High Drywell Pressure Scram Test and Calibration, Attachment 619.3.016-2, Test Data Sheet




Form ES-C-1

Note: The following steps are not required to be performed in the order provided .


Standard:

Comment:

SAT/UNSAT

Procedure Step: 7.2

If any criteria of Step 7.1 are not met, declare the affected components inoperable and follow the requirements of Technical Specifications and Procedure LS-AA-125.

Notes that sensor RE04A is outside of the allowed band (actual value of 2.98 with the allowed band of 2.85- 2.95). Declares sensor RE04A inoperable.


Appendix C

Standard:

Note 1:

Note 2:

Comment:

SAT/UNSAT



Performance Step: 4

Procedure Step: 7.2

Determine Tech Spec applicability

Form ES-C-1

Determines that, with in 12 hours, either restore the inoperable channel or place the inoperable channel and/or that Trip System in the tripped condition, or take the action to insert control rods.

The failed instrument inputs into the reactor scram circuit.

Determines sensor loss on Tech Spec applicability. Determines that sensor RN04A only affects a single Trip System. TS Table 3.1.1.A (Scram) requires the minimum number of Instrument Channels per Operable Trip System as 2. One Trip System only has 1 operable instrument.

TS Table 3.1.1.A (Scram) requires the minimum number of Operable or Operating (tripped) Trip System as 2. There is currently only 1 operable or operating (tripped) Trip System.

Note nn applies:

With one required channel inoperable in one Trip System, within 12 hours, restore the inoperable channel or place the inoperable channel and/or that Trip System in the tripped• condition. • An inoperable channel or Trip System need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, if the inoperable channel is not restored to OPERABLE status within the required time, the Action Required shall be taken.

Otherwise, take the Action Required.

The Applicant may also state that an IR/CR (incident report/condition report) be generated and that notifications to Plant Management are required. (Not required for Critical Step)


Appendix C

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT



Performance Step: 5


Form ES-C-1

As Found trip point for the following is less than or equal to 3.5 psig:

• RE04A

• RE04C

Verifies sensor trip as-found setpoints < 3.5 psig (no problems)

Performance Step: 6


Control Room alarms perform as specified

Verifies alarms performed as specified (no problems)


Appendix C

Standard:

Comment:

SAT/UNSAT



Performance Step: 7


Plant Computer PIDs perform as specified

Form ES-C-1

Verify plant computer PIDs performed as specified (no problems)

Terminating Cue: Section 7.0, Acceptance Criteria, is reviewed and found to be unsatisfactory due to sensor RE04A not meeting the criteria. Tech Spec required actions are as stated.



Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response:

Result:



NRC SRO Admin JPM 3



NRC SRO Admin JPM 3

Form ES-C-1

Page 8 of 10


JPM Setup

Form ES-C-1

1. A completed surveillance procedure 619.3.016, High Drywell Pressure Scram Test and Calibration, with instrument RE04A setting outside of the allowed adjusted band of 2.85-2.95 (ie, 2.98).

2. Allow the Applicants access to RAPs, 420, and Tech Specs.


Appendix C

Initial Conditions:


STUDENT HANDOUT


Form ES-C-1

2. Surveillance Test 619.3.016, High Drywell Pressure Scram Test and Calibration, was just completed

Task Cue:

Perform the Acceptance Criteria review of 619.3.016, High Drywell Pressure Scram Test and Calibration. Note any discrepancies, and state the required actions, if any.



Form ES-C-1

Facility: Oyster Creek Task No.: EPAA101013

Task Title: Determine Recommendation of Kl Issuance During an Emergency

Job Performance Measure No.: NRC SRO ADMIN JPM4

K/ A Reference: _G_2_._3._1_4_._(3_.__,8).___ ______ _

Examinee: Examiner:


Method of Testing:




X


Initial Conditions:

1. The plant was at rated power when a LOCA occurred inside the Primary Containment

2. The reactor scrammed 20 minutes ago

3. RPV water level is -30" and steady

4. Stack RAGEMS has risen from 2.1 E+OO 11CI/CC HRM to 2.7 E+01 11CIICC HRM over the last 15 minutes

5. Containment Hi-Range Radiation Monitors indicate 585 R/hr

6. The RB Vent Radiation Monitors indicate 8 mr/hr


8. The Emergency Response Facilities (TSC, EOF) have not been activated yet

Task Standard: Kl issuance should be recommended for the off-site Field Monitoring Team, and to the on-site emergency workers.

NRC SRO ADMIN JPM4 Page 1 of 11

Appendix C


General References:


1. EP-AA-113, Personnel Protective Actions, Revision 10

Form ES-C-1

2. EP-AA-1010, Radiological Emergency Plan Annex for Oyster Creek Station, Revision 2

3. EP-AA-114-F-01, Release In Progress Determination, Revision D

Initiating Cue: With only the information provided, and lAW EP-AA-113, Personnel Protective Actions, determine if the SED shall recommend Kl issuance to:

1) Off-site Field Monitoring Teams, and/or

2) On-site Emergency Teams

Time Critical Task: No





Form ES-C-1


Standard:

Comment:

SAT/UNSAT

Performance Step: 1





Appendix C

Standard:

Comment:

SAT/UNSAT



Performance Step: 2

Procedure Step: 4.4.1.1.A (EP-AA-113)

Form ES-C-1

Assess the potential of high thyroid exposure to emergency workers in, or projected to be sent into, areas where the possibility exists of exposure to radioactive iodine as follows: For Field Monitoring Teams or other Exelon emergency workers working offsite, determine if either of the following conditions exist: Condition 1

• There is an Offsite Release in Progress And

• There has been a loss or potential loss of the Fuel Clad Barrier

Or Condition 2

• Dose Assessments project iodine thyroid exposure for emergency workers will be ~50 Rem Committed Dose Equivalent (CDE)

Determines that an offsite release is in progress (as evidenced by the Stack RAGEMS)

This meets the first bullet of Condition 1.

NRC SAO ADMIN JPM4 Page 4 of 11

Appendix C

Standard:

Comment:

SAT/UNSAT



Performance Step: 3

Procedure Step: Procedure Step: 4.4.1.1.A

Form ES-C-1




Or Condition 2

Dose Assessments project iodine thyroid exposure for emergency workers will be 2:.. 50 Rem Committed Dose Equivalent (CDE)

Determines either that a loss or potential loss of Fuel Clad Barrier exists (as evidenced by RPV water level at -30")

This meets the second bullet of Condition 1.


Appendix C

Standard:

Note:

Comment:

SAT/UNSAT



Performance Step: 4

Procedure Step: 4.4.1.1.A

Form ES-C-1




Or Condition 2

Dose Assessments project iodine thyroid exposure for emergency workers will be .2:_50 Rem Committed Dose Equivalent (CDE)

Determines the indications meet the 2 parts of Condition 1 to recommend issuance of Kl to the off-site Field Monitoring Teams.

Thus, with the information provided, Kl issuance to off-site Field Monitoring Teams should be recommended.

The Station (Shift) Emergency Director must authorize issuance of Kl to Exelon emergency workers


Appendix C

Standard:

Comment:

SAT/UNSAT



Performance Step: 5

Procedure Step: 4.4.1.1.8

Form ES-C-1

For OSC Emergency Teams and other onsite workers,

determine if either of the following conditions exist:

Condition 1

• Workers will be entering an unknown radiological atmosphere that is suspected to have a high iodine concentration. Loss of the Fuel Clad barrier is a good indication of possible high iodine concentrations.

OR

Condition 2

• The calculated iodine thyroid exposure (actual or projected) for emergency workers, base on station Radiation Protection procedures or use of the DAPAR Program, will be ::::_50 Rem Committed Dose Equivalent (CDE).

Determines there is currently a loss of the Fuel Clad Barrier, which is a good indication of possible high iodine concentrations


Appendix C

Standard:

Comment:

SAT/UNSAT



Performance Step: 6

Procedure Step: 4.4.1.1.8

Form ES-C-1

For OSC Emergency Teams and other onsite workers, determine if either of the following conditions exist:

Condition 1

• Workers will be entering an unknown radiological atmosphere that is suspected to have a high iodine concentration. Loss of the Fuel Clad barrier is a good indication of possible high iodine concentrations.

OR

Condition 2

• The calculated iodine thyroid exposure (actual or projected) for emergency workers, base on station Radiation Protection procedures or use of the DAPAR Program, will be ;:::_50 Rem Committed Dose Equivalent (CDE).

Determines the indications meet Condition 1 to recommend issuance of Kl to the on-site Emergency Teams.

Thus, with the information provided, Kl issuance to on-site Emergency Teams should be recommended.

Terminating Cue: Kl issuance should be recommended for the off-site Field Monitoring Team, and to the on-site emergency workers.



Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response:

Result:



NRC SRO ADMIN JPM4

---------------------



NRC SRO ADMIN JPM4

Form ES-C-1

Page 9 of 11


JPM Setup

Form ES-C-1

1. Have a copy of the EAL Hot Matrix from E P-AA-1 010 for each candidate.


Appendix C

Initial Conditions:


STUDENT HANDOUT

Form ES-C-1

1. The plant was at rated power when a LOCA occurred inside the Primary Containment

2. The reactor scrammed 20 minutes ago

3. RPV water level is -30" and steady

4. Stack RAGEMS has risen from 2.1 E+OO 11CI/CC HRM to 2.7 E+01 11CI/CC HRM over the last 15 minutes

5. Containment Hi-Range Radiation Monitors indicate 585 R/hr

6. The RB Vent Radiation Monitors indicate 8 mr/hr


8. The Emergency Response Facilities (TSC, EOF) have not been activated yet

Task Cue:

With only the information provided, and lAW EP-AA-113, Personnel Protective Actions, determine if the SED shall recommend Kl issuance to:

1) Off-site Field Monitoring Teams, and/or

2) On-site Emergency T earns


Appendix C



Task No.: 2000502401

Task Title: Classify an Emergency or Abnormal Event


K/ A Reference: _2_._4._4_1 _,_( 4_.6_,)'---------

Examinee: Examiner:


Method of Testing:




Form ES-C-1

X


Initial Conditions:

1. You are the Unit Supervisor for the operating shift 2. The plant is operating at 1 00% power. 3. Wind Speed is 5mph 4. Wind direction is 1 00 degrees 5. The following conditions are reported from the Site Protection Shift

Supervisor;

• Received valid Aircraft threat notification from the NRC

• An explosion occurred in the Recirc pump MG set room

• An unauthorized vehicle has gained access to the site

• Security has disabled and surrounded the vehicle in the employee parking lot

• The driver of the vehicle has not surrendered and the threat is unknown but is considered a hostile action condition as determined by Station Security lAW Security Procedures

Task Standard: The event is classified as an Alert (HA 1) and the State/Local Notification Form is correctly filled out lAW the key.


Appendix C


General References:


1. EP-AA-1 010, Exelon EP Annex for Oyster Creek, Rev 7

Form ES-C-1

2. EP-MA-114-1 00, Mid-Atlantic State/Local Notifications, Rev 19

3. EP-MA-114-100-F-03, State/Local Notification Form, Rev F

Initiating Cue: State the minimum classification for these conditions and complete the State and Local Notification Form for Shift Manager approval.






Form ES-C-1

Denote critical steps with a check mark ,/

Standard:

Comment:

SAT/UNSAT

-----

Standard:

Comment:

SAT/UNSAT

Performance Step: 1




Performance Step: 2

Procedure Step: Determined Emergency Classification and associated EAL.

Declares "ALERT"- Cat. HA1.

Notified by Station Security that this is a Security Condition with hostile action (owner controlled)

Time Critical Portion of JPM complete

Time Complete (<15 minutes)


Appendix C

Standard:

Comment:

SAT/UNSAT



Performance Step: 3

Procedure Step: Completes Status block

Fill in the block with:

Check the line that states "This is a Drill"

NRC SRO Admin JPM 5

Form ES-C-1

Page 4 of 12

Appendix C

-----

Standard:

Comment:

SAT/UNSAT



Performance Step: 4

Form ES-C-1

Procedure Step: Completes Emergency Classification block


Check the line that states "ALERT"


Appendix C

Standard:

Comment:

SAT/UNSAT

-----

Standard:

Comment:

SAT/UNSAT



Performance Step: 5

Procedure Step: Completes Declaration block


Form ES-C-1

An "ALERT" was declared at "current time" on "current date". The EAL is "HA1"

Performance Step: 6

Procedure Step: Completes Represents AlAN block


Check the line that states "Initial declaration"


Appendix C

-----

Standard:

Comment:

SAT/UNSAT

-----

Standard:

Comment:

SAT/UNSAT



Performance Step: 7

Form ES-C-1

Procedure Step: Completes EAL number and Event Description block


The EAL is "HA 1"

Description similar to; "Notified by Station Security that this is a Security Condition with hostile action (owner controlled)"

Performance Step: 8

Procedure Step: Completes Radioactive Release Status block


Check the line that states that "There is no abnormal radiological release in progress"


Appendix C

Standard:

Comment:

SAT/UNSAT



Performance Step: 9

Form ES-C-1

Procedure Step: Completes Meteorological Condition block


From the Weather screen record; Wind direction is from " " degrees and wind speed is" "miles per hour (use 380' elevation data)


Appendix C

Standard:

Comment:

SAT/UNSAT




Procedure Step: Completes Conclusion block


Check the line that states "This is a Drill"

Form ES-C-1

Terminating Cue: An Alert (HA 1) is declared and the State/Local Notification Form is filled out lAW the JPM key.



Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:



NRC SRO Admin JPM 5


Time to Complete:

Question:

Response:



NRC SRO Admin JPM 5

Form ES-C-1

Page 10 of 12


Simulator Setug

1. Have a copy of EALs for the applicant

2. Have a blank State/Local Notification Form for the applicant

3. Have a copy of EP-AA-114-1 00 available on request

NRC SRO Admin JPM 5

Form ES-C-1

Page 11 of 12

Appendix C

Initial Conditions:


STUDENT HANDOUT

1. You are the Unit Supervisor for the operating shift 2. The plant is operating at 100% power. 3. Wind Speed is 5mph 4. Wind direction is 100 degrees

Form ES-C-1

5. The following conditions are reported from the Site Protection Shift Supervisor;

• Received valid Aircraft threat notification from the NRC

• An explosion occurred in the Recirc pump MG set room

• An unauthorized vehicle has gained access to the site

• Security has disabled and surrounded the vehicle in the employee parking lot

• The driver of the vehicle has not surrendered and the threat is unknown but is considered a hostile action condition as determined by Station Security lAW Security Procedures

Task Cue:

State the minimum classification for these conditions and complete the State and Local Notification Form for Shift Manager approval.


Appendix C



Task No.: 2040101412

Form ES-C-1

Task Title: Shutdown the Second RWCU Pump with NRHX High Temperature (Alternate Path)

Job Performance Measure No.: NRC Sim JPM 1

K/A Reference: 204000 A4.01 (3.1/3.0)

Examinee: Examiner:


Method of Testing:


Classroom Simulator X Plant ----- -----



Initial Conditions:

1 . The plant is at -99% power

2. Both RWCU Pumps are in service

3. An EO has been briefed, has a copy of the procedure, and is standing by in the Reactor Building to assist in shutting down a RWCU Pump

4. All applicable Prerequisites and Precautions and Limitations of Procedure 303 have been verified or are met

Task Standard: RWCU Pump B has been secured lAW 303.


General References:

1. 303, Reactor Cleanup Dem ineralizer System, Revision 139

2. RAP-D8b, NRHX OUTLET TEMP HI, Revision 001

Initiating Cue: Secure RWCU Pump B lAW 303, Reactor Cleanup Demineralizer System, starting at Step 22.4

NRC Sim JPM 1 Page 1 of 13




NRC Sim JPM 1

Form ES-C-1

Page 2 of 13



Form ES-C-1


Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT

Performance Step: 1




Performance Step: 2

Procedure Step: Review Precautions and Limitations.

Precautions and Limitations have been verified per the Initial Conditions.


Appendix C

Standard:



Performance Step: 3


Form ES-C-1

Open the Minimum Flow Valves for both pumps using the local toggle switches:

• V-16-36, Minimum Flow Valve Pump A

• V-16-37, Minimum Flow Valve Pump B

Directs the EO to open the Minimum Flow Valves for both pumps using the local toggle switches:


• V-16-37, Minimum Flow Valve Pump B

Booth/Cue: Initiate Trigger 1, then report minimum flow valves for both RWCU Pumps are open

Comment:

SAT/UNSAT




Form ES-C-1

Note: The Applicant will perform several cycles of manipulations using the RWCU Pump B discharge valve, V-16-50, and then the System Flow Control valve FCV-ND16. The cycle will repeat until the discharge valve V-16-50 is fully closed.

Standard:

Comment:

SAT/UNSAT

Performance Step: 4


Slowly close the discharge valve for the pump being removed from service by momentarily cycling the discharge valve control switch between CLOSE and mid position until a small decrease in pressure is seen (Panel 3F).

• V-16-49, RECIRC PUMP A DISCHARGE

OR

• V-16-50, RECIRC PUMP B DISCHARGE

Slowly closes RWCU Pump B discharge valve V-16-50 by momentarily cycling the discharge valve control switch between CLOSE and mid position until a small decrease in pressure is seen (Panel 3F) (red light on and green light on; RECIRC PUMP DISCHARGE PRESS lowers slightly)


Appendix C

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT



Performance Step: 5

Procedure Step: 22.4.3, 22.4.3.1, & 22.4.3.2

Form ES-C-1

Perform either or both of the following to increase pump discharge pressure to approximately the original value while adjusting PCVND11 as need to maintain system pressure at approximately 90 psig.

22.4.3.1 Slowly close FCV-ND16

22.4.3.2 Slowly close V-16-54, FCV Bypass

Rotates SYSTEM FLOW CONTROLLER FCV-ND16 CCW to increase pump discharge pressure to approximately the original value.

Performance Step: 6


Continue to close the discharge valve by momentarily cycling the discharge valve control switch between CLOSE and mid position while adjusting flow and pressure until the valve is fully closed.

Continues to close the discharge valve by momentarily cycling the discharge valve control switch between CLOSE and mid position while adjusting flow and pressure with FCV-ND16 knob CCW until the discharge valve is fully closed. (green light on; red light off)


Appendix C

Standard:

Booth:

Comment:

SAT/UNSAT

Standard:

Booth

Comment:

SAT/UNSAT



Performance Step: 7


Form ES-C-1

Stop the Cleanup Recirculation Pump being removed from service.

Stops the Cleanup Recirculation Pump 8 by placing RECIRC PUMP NC028 switch to STOP (green light on; red light off)

When the standby RWCU Pump is secured, place LOA-R8C009 to 0.39

Performance Step: 8


Close the Minimum Flow Valves for both pumps using the local toggle switches:


• V-16-37, Minimum Flow Valve Pump 8

Directs the EO to close the Minimum Flow Valves for both pumps using the local toggle switches:


• V-16-37, Minimum Flow Valve Pump 8

Insert LOA-RCU022 to 0 and LOA-RCU023 to 0; Then report minimum flow valves for both RWCU Pumps are closed


Appendix C

Standard:

Note:

Comment:

SAT/UNSAT



Performance Step: 9

Procedure Step: 22.4.7, 22.4.7.1, & 22.4.7.2

Form ES-C-1

Perform either or both of the following to adjust system flow to approximately 380-420 gpm

22.4.7.1 Throttle FCV-ND16 as necessary

22.4.7.2 Throttle V-16-54, FCV Bypass, as necessary

Throttle SYSTEM FLOW CONTROLLER FCV-ND16 knob if required to adjust CLEANUP DEMIN INLET FLOW to approximately 380-420 gpm

If RWCU flow is already in this required range, then no manipulations in this Step are required.




Form ES-C-1

NOTE: The following step will initiate the Alternate Path

Standard:

Evaluator/

Booth:

CUE:

Comment:

SAT/UNSAT

-----

Performance Step: 1 0


Adjust the PPC heat balance input for RWCU Flow to the value indicated on the 3F Recorder (IJ13).

Adjusts the PPC heat balance input for RWCU Flow to match the indicated flow(± 5 GPM).

During performance of this step, at the Evaluator's discretion, INSERT Trigger 3, ANN-D-88 to ON, to initiate the Alternate Path.

When the student opens the 'D' annunciator RAPs, hand them a yellow exam copy of RAP-D8b.

Performance Step: 11 Procedure Step: Respond to annunciator D8b. May Direct the EO to verify high system temperature. (RK05, TISIJ33)

Standard: Responds to annunciator D8b. May Direct the EO to verify high system temperature. (RK05, TISIJ33)

CUE: As the EO, report that TIS-IJ33 at RK05 indicates 155 °F and rising rapidly.

NOTE/CUE: If NRHX Temperature is requested again, report that it is now 165 oF and rising rapidly.

CUE: If the US is contacted, direct the applicant to confirm actions lAW the RAP.

Comment:

SAT/UNSAT




Form ES-C-1

NOTE: Steps 12, 13, and 14 may be performed in any order.

___ ../ ___ Performance Step: 12

Standard:

Comment:

SAT/UNSAT

Procedure Step: Trip RWCU Pumps Trips RWCU Pumps with their control switches (red light OFF; green light ON)

_____ Performance Step: 13

Standard:

Comment:

SAT/UNSAT

-----

Standard:

CUE:

Comment:

SAT/UNSAT

Procedure Step: Close V-16-1, CU Inlet Isolation Valve From Reactor Vessel Closes V-16-1, CU Inlet Isolation Valve From Reactor Vessel, with its control switch (red light OFF; green light ON)

Performance Step: 14 Procedure Step: Close V-16-14, Clean-Up Inlet Isolation Valve Closes Close V-16-14, Clean-Up Inlet Isolation Valve, with its control switch (red light OFF; green light ON) Once V-16-14 is closed, state that another Operator will continue with the actions in the RAP

Terminating Cue: The NRHX high temperature annunciator is received, the RWCU Pumps are secured and the system isolation valves are manually closed.



Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:



NRC SIM JPM 1

Number of Attempts: _________ _

Time to Complete:

Question:

Response:



NRC Sim JPM 1

Form ES-C-1

Page 11 of 13


Simulator Setup

Form ES-C-1

NOTE: Reset to IC-152 (password: 2014iltnrc) OR perform the following

1. Reset to full power IC and lower power to -95% with recirc flow

2. Start the standby RBCCW Pump and achieve a System Flow of 700 GPM

3. Raise RBCCW flow through the NRHX as follows:

a. Insert LOA-RBC009 to 0.80

b. When the standby RWCU Pump is secured, place LOA-RBC009 to 0.39

4. Place the second RWCU Pump in service lAW 303, section 22

a. Leave the heat balance screen up and available (with System Flow at or slightly above that flow attained above)

5. Place the following on Trigger 1:

a. LOA-RCU022 to 1 This opens RWCU Pump A minimum flow valve V-16-36

b. LOA-RCU023 to 1 This opens RWCU Pump B minimum flow valve V-16-37

c. These valves will be closed during JPM performance


a. ANN-D-88 to ON

7. Insert BKR-RCU001 to FAIL AUT TRIP 8. Insert BKR-RCU002 to FAIL AUT TRIP

a. This will prevent any automatic trips of the RWCU Pumps

9. Insert VLV-RCU001 to FAIL AUT CL

1 O.lnsert VLV-RCU004 to FAIL AUT CL


Appendix C

Initial Conditions:


STUDENT HANDOUT

1 . The plant is at -99% power 2. Both RWCU Pumps are in service

Form ES-C-1

3. An EO has been briefed, has a copy of the procedure, and is standing by in the Reactor Building to assist in shutting down a RWCU Pump

4. All applicable Prerequisites and Precautions and Limitations of Procedure 303 have been verified or are met

Task Cue:

Secure RWCU Pump B lAW 303, Reactor Cleanup Demineralizer System, starting at Step 22.4



Form ES-C-1


Task Title: Bypass an Inoperable Acoustic Monitor for EMRV NR108E


K/A Reference: 239002 A4.03 (3.8/3.9)

Examinee: Examiner:


Method of Testing:





Initial Conditions:

1. The plant was at rated power.

2. The Unit Supervisor has declared the acoustic monitor inoperable for EMRV NR108E.

3. Technical Specifications for this event have been reviewed by the Unit Supervisor.

4. It has been determined that the acoustic monitor failure is located inside the Drywell, and that a Job Order has been initiated to switch to the installed spare.

5. All Prerequisites and Precaustions and Limitations are met.

Task Standard: The acoustic monitor for EMRV NR108E is bypassed lAW Procedure 413


General References:

1. Procedure 413, Operation of the Safety Valve/EMRV Acoustic Monitoring System, Revision 19



Form ES-C-1

Initiating Cue: The Unit Supervisor directs you to bypass the acoustic monitor for EMRV NR108E lAW Procedure 413, Section 4.3.2.






Form ES-C-1


Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT

Performance Step: 1




Performance Step: 2

Procedure Step: Review Precautions and Limitations.

Precautions and Limitations have been verified per the Initial Conditions.


Appendix C

Standard:

Comment:

SAT/UNSAT



Performance Step: 3


Form ES-C-1

SWITCH the HI-ALARM switch down to DEFEAT (15R)

Places the HI-ALARM switch for NR108E (VMS-21) in DEFEAT position.


Appendix C

Standard:

Comment:

SAT/UNSAT



Performance Step: 4


Form ES-C-1

SWITCH the LO-BIAS switch down to DEFEAT (15R).

Places the LO-BIAS switch for NR1 OBE (VMS-21) in DEFEAT position.


Appendix C

Standard:

Comment:

SAT/UNSAT

-----

Standard:

CUE:

NOTE:

Comment:

SAT/UNSAT



Performance Step: 5


Form ES-C-1

PRESS the Associated Master Alarm Reset Push Button (15R).

Presses the associated MASTER ALARM RESET pushbutton.

Performance Step: 6


IF the acoustic monitoring failure is in the Drywell,

THEN INITIATE Job Order to switch to the installed spare acoustic monitor inaccordance with Attachment 413-4

Initiates a Job Order to switch to the installed spare.

Initiates a Job Order to switch to the installed spare.

Since this was part of the initiating cue, the Candidate may refer to the initiating cue and not mention this step.

NOTE: Step 4.3.2.5 is N/A


Appendix C

Standard:

CUE:

Comment:

SAT/UNSAT

Standard:

CUE:

NOTE:

Comment:

SAT/UNSAT



Performance Step: 7


IF the acoustic monitor cannot be repaired,

THEN REFER to Technical Specification 3.13.A.

Form ES-C-1

The Unit Supervisor has referred to Technical Specification 3.13.A.

Per the Initial Conditions, the Unit Supervisor has already reviewed Technical Specification 3.13.A. for applicability.

Performance Step: 8


MONITOR EMRV tail pipe temperatures once per shift on Recorder TR-IG02 ISOL CONDENSER/EMRV DISCH TEMPERATURES while the acoustic monitor is inoperable. (Panel 1 F/2F)

Monitors EMRV tail pipe temperature once per shift while the acoustic monitor is inoperable.

EMRV tail pipe temperature will be monitored once per shift while the acoustic monitor is inoperable.

It is not required that the Applicant monitor the tail pipe temperature now.

Terminating Cue: The acoustic monitor for EMRV NR108E is bypassed lAW Procedure 413.



Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response:

Result:



NRC SIM JPM 2

---------------------



NRC Sim JPM 2

Form ES-C-1

Page 8 of 10


Simulator Setup

1. Reset to full power IC (IC-115) 2. Insert MAL-NSS026A (VMS-17 Acoustic Monitor Fail) to 120

NRC Sim JPM 2

Form ES-C-1

Page 9 of 10

Appendix C

Initial Conditions:


STUDENT HANDOUT

1. The plant was at rated power.

Form ES-C-1

2. The Unit Supervisor has declared the acoustic monitor inoperable for EMRV NR108E.

3. Technical Specifications for this event have been reviewed by the Unit Supervisor.

4. It has been determined that the acoustic monitor failure is located inside the Drywell, and that a Job Order has been initiated to switch to the installed spare.

5. All Prerequisites and Precaustions and Limitations are met.

Task Cue:

The Unit Supervisor directs you to bypass the acoustic monitor for EMRV NR108E lAW Procedure 413, Section 4.3.2.




Task Title: Add Makeup to the Isolation Condenser System (Alternate Path)


K/A Reference: 207000 A3.05 (3.6/3.8)

Examinee: Examiner:


Method of Testing:




Form ES-C-1

X


Initial Conditions:

1 . Reactor is 1 00% power and stable 2. A Isolation condenser level is 6.9 feet due to inadvertent draining from the

shell 3. Drain valves has been shut and no more leakage is present

Task Standard: All 'A' Isolation Condenser AC, DC, and Vent valves have been manually closed.


General References:

1. 307, Isolation Condenser System, Revision 124

2. RAP-C3a, COND A FLOW HI POSSIBLE RUPTURE, Revision 004

Initiating Cue: As US, I am directing you to restore Isolation Condenser 'A' shell level to the normal band using Condensate Transfer lAW procedure 307, Section 7.



Appendix C

Validation Time:

NRC Sim JPM 3


6 Minutes

Form ES-C-1

Page 2 of 11



Form ES-C-1


-----

Standard:

Comment:

SAT/UNSAT

Standard:

Cue:

Comment:

SAT/UNSAT

Performance Step: 1




Performance Step: 2

Procedure Step: Review Prerequisites, Precautions and Limitations.

Prerequisites, Precautions and Limitations have been verified and/or are met.

All Prerequisites, Precautions and Limitations have been verified and/or are met.


Appendix C

Standard:

Cue:

Comment:

SAT/UNSAT



Performance Step: 3


Record initial shell level

Records initial shell level on attachment 307-15

Form ES-C-1

Indicated shell level on L TIG06A is 6.9 feet (per Initial Conditions)


Appendix C

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT



Performance Step: 4


Open V-11-257

Rotates keylock control switch to open on 5F/6F

Performance Step: 5


Open V-11-36

Places control switch to open on Panel 5F/6F

Performance Step: 6


Form ES-C-1

Verify annunciator ISOL COND MU VLV OPEN (RAP-K6d) alarms

Verifies annunciator ISOL COND MU VLV OPEN (RAP-K6d) alarms




Form ES-C-1

NOTE: The following step will initiate the Alternate Path

-----

Cue:

Evaluator/

Booth:

Evaluator:

Comment:

SAT/UNSAT

Performance Step: 7


Fill Isolation Condenser Shell 'A' so indicated level is between 7.3 and 7. 7 feet.

If the applicant requests level, report that level is 7.0 feet and rising

While filling, at the discretion of the Lead Evaluator, Insert Trigger 1, C-3-a, COND A FLOW HI POSSIBLE RUPTURE alarm

When the applicant opens RAP-C3a, hand them the yellow copy of the RAP.


Appendix C

Standard:

NOTE:

Comment:

SAT/UNSAT



Performance Step: 8

Procedure Step: RAP-C3a Automatic Actions

Closes Isolation Condenser System A Valves.

Form ES-C-1

• V-14-30, Steam Inlet Valve to 'A" Emergency Condenser • V-14-31, Steam Inlet Valve to 'A' Emergency Condenser • V-14-34, Emergency Condenser NE01A Condensate Return

Valve • i i V-14-36, Isolation Valve Emergency Condenser NE01A

Closes Isolation Condenser System A Valves. • V-14-30, Steam Inlet Valve to 'A" Emergency Condenser • V-14-31, Steam Inlet Valve to 'A' Emergency Condenser • V-14-34, Emergency Condenser NE01A Condensate Return

Valve • 11 V-14-36, Isolation Valve Emergency Condenser NE01A

The applicant may close these Isolation Valves prior to referring to the RAP (manually confirming actions that failed to automatically occur).




Form ES-C-1


Booth/Cue: As the Reactor Building EO, call the Control Room and report there is a pipe break tube leak in Isolation Condenser 'A'

Standard:

Cue:

Cue:

Comment:

SAT/UNSAT

Procedure Step: RAP-C3a, Manual Corrective Actions

IF pipe break tube leak is verified, THEN Perform the following:

• EVACUATE Reactor Building. • PLACE V-14-30, V-14-31, V-14-34, V-14-36 Also Cond

Isolation Valves Control Switches to CLOSE. • 11 PLACE V-14-5 and V-14-20, Emergency Condenser NE01A

High Point Vent Valves Control Switches to CLOSE. • Evacuates the Reactor Building [SEE CUE BELOW]. • Places V-14-30, V-14-31, V-14-34, V-14-36 Also Cond

Isolation Valves Control Switches to CLOSE [Performed in Step 8].

• 11 Places V-14-5 and V-14-20, Emergency Condenser NE01A High Point Vent Valves Control Switches to CLOSE.

Inform the applicant another operator will Evacuate the Reactor Building

When V-14-15 and V-14-20 are closed, inform the applicant another operator will continue with the procedure.

Terminating Cue: All 'A' Isolation Condenser AC, DC, and Vent valves have been manually closed.



Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response:

Result:



NRC Sim JPM 3



NRC Sim JPM 3

Form ES-C-1

Page 9 of 11


Simulator Setup

Form ES-C-1

1. Reset to full power (1 00%) [Or reset to any power IC if performing concurrent to another JPM]

2. Have a copy of 307 section 7 and Attachment 307-18 for the applicant

3. Have a yellow copy of RAP-C3a to hand to the applicant in Step 7

4. Insert ANN-N-7b to OFF- disables 2-demin pumps running alarm


i. ANN-C-3a to ON


Appendix C

Initial Conditions:


STUDENT HANDOUT

1 . Reactor is 1 00% power and stable

Form ES-C-1

2. A Isolation condenser level is 6.9 feet due to inadvertent draining from the shell

3. Drain valves has been shut and no more leakage is present

Task Cue:

As US, I am directing you to restore Isolation Condenser 'A' shell level to the normal band using Condensate Transfer lAW procedure 307, Section 7.



Form ES-C-1


Task Title: Purging the Primary Containment with Elevated Stack Radiation (Alternate Path)


K/A Reference: 223001 A4.07 (4.2/4.1)

Examinee: Examiner:


Method of Testing:




X


Initial Conditions:

1. The plant is at rated power preparing for a shutdown

2. Entry into the Primary Containment will be required

3. The Primary Containment is being prepared to be purged with air, lAW 312.9, Primary Containment Control

4. All Prerequisites of Section 9.0, Purging Primary Containment With Air, are complete

5. Stack RAGEMS is OOS; Chemistry is sampling daily

Initiating Cue: Purge the Primary Containment with air lAW 312.9, Primary Containment Control, starting at Step 9.3.6


General References:

1. 312.9, Primary Containment Control, Revision 58



Form ES-C-1

Task Standard: Drywell air purge has been initiated, then isolated when stack gas high radiation indicated> 1000 CPS






Form ES-C-1

Denote critical steps with a check mark ~

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT

Performance Step: 1




Performance Step: 2


Verifies Prerequisites and reviews Precautions and Limitations.


Appendix C

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT



Performance Step: 3

Procedure Step: 9.3.6. 1

Confirm closed Drywell Vent and Bypass valves: • V-23-21 • V-23-22 • V-27-1 • V-27-2

Confirm closed Drywell Vent and Bypass valves: • V-23-21 • V-23-22 • V-27-1 • V-27-2 (green lights on; red lights off)

Performance Step: 4


Form ES-C-1

If the REACTOR MODE SELECTOR switch is in the RUN position, THEN place DRYWELL VENT-PURGE INTERLOCK BYPASS switch in BYPASS position (Panei12XR)

Places DRYWELL VENT-PURGE INTERLOCK BYPASS switch in the BYPASS position


Appendix C

Standard:

Note/Cue:

Comment:

SAT/UNSAT



Performance Step: 5


Open Torus Vent valves (Panel 11 F): • V-28-17 • V-28-18

Opens Torus Vent valves (Panel 11 F):

• V-28-17 • V-28-18

Form ES-C-1

By taking their control switches CW (green lights off; red lights on)

As Drywell pressure lowers, annunciator C3f, OW PRESS HI/LO may alarm. State that another operator will respond.


Appendix C

Standard:

Comment:

SAT/UNSAT

Note/Cue:

Standard:

Comment:

SAT/UNSAT



Performance Step: 6


Monitor the following:

Form ES-C-1

• Reactor Building ventilation exhaust activity (Panel 1 OF)

• Stack gas activity (Panel 1 OF)

• Stack gas activity (Panel 1 R)

Monitors the following:

• Reactor Building ventilation exhaust activity (Panel 1 OF)

• Stack gas activity (Panel 1 OF)

• Stack gas activity (Panel 1 R)

Performance Step: 7


Mark the time the depressurization was started on the stack gas recorder (Panel 1 OF).

These are electronic recorders. If questioned or the applicant attempts to electronically mark the recorders, state that the recorders have been marked.

Note: Step 9.3.6.6 is a conditional statement which requires no actions and is not provided here.


Appendix C

Standard:

Cue:

Comment:

SAT/UNSAT



Performance Step: 8


Form ES-C-1

Verify Torus pressure is approximately zero as indicated on the pressure recorder (Panel 12XR)

Verifies Torus pressure is approximately zero as indicated on the pressure recorder

State that time compression is used here and that Torus pressure indicates approximately zero as indicated on the pressure recorder


Appendix C

Standard:

Comment:

SAT/UNSAT

-----

Standard:

Comment:

SAT/UNSAT



Performance Step: 9


Close Torus Vent valves (Panel 11 F):

• V-28-17 • V-28-18

Closes Torus Vent valves (Panel 11 F):

• V-28-17 • V-28-18

Form ES-C-1

By taking their control switches CCW (green lights on; red lights off) (Closing only 1 valve will meet the Critical Step)


Procedure Step: 9.3.7.1 Confirm closed Torus Vent and Bypass valves (Panel 11 F):

• V-28-17 • V-28-18 • V-28-47

Confirm closed Torus Vent and Bypass valves (Panel 11 F):

• V-28-17 • V-28-18 • V-28-47 (green lights on; red lights off)


Appendix C

Standard:

Comment:

SAT/UNSAT




Procedure Step:


Form ES-C-1

If the REACTOR MODE SELECTOR switch is in the RUN position, THEN place DRYWELL VENT-PURGE INTERLOCK BYPASS switch in BYPASS position (Panel 12XR)

Places DRYWELL VENT-PURGE INTERLOCK BYPASS switch in the BYPASS position (this step was already performed)


Appendix C

Standard:

Note/Cue:

Comment:

SAT/UNSAT





Open Orywell Vent valves (Panel 11 F):

• V-27-1 • V-27-2

Opens Orywell Vent valves (Panel 11 F):

• V-27-1 • V-27-2

Form ES-C-1

By taking their control switches CW (green lights off; red lights on)

Annunciator C6g, OW VENT VLV OPEN will alarm. State that another operator will respond. As Orywell pressure lowers, annunciator C3f, OW PRESS HI/LO may alarm. State that another operator will respond.

Note: Trigger 1 will initiate the Stack Effluent Hi annunciator (10 sec time delay) when V-27-2 goes open (red light on), and begins the Alternate Path.




Form ES-C-1

Note: Step 9.3.7.4 is a conditional statement which requires no actions and is not provided here.

-----

Standard:

NOTE:

Comment:

SAT/UNSAT



Monitor the following: a. Reactor Building ventilation exhaust activity (Panel 1 OF)

b. Stack gas activity (Panel1 R)

Monitors the following:

a. Reactor Building ventilation exhaust activity (Panel 1 OF)

b. Stack gas activity (Panel 1 R)

c. Recognizes/reports at some point that Stack Gas radiation is rising

Since Stack RAGEMS is OOS (chemistry sampling daily), Stack gas activity indication on the recorders will not change.

EVALUATOR CUE/NOTE: Annunciator STACK EFFLUENT HI (10F2d) will alarm (indicating Stack radiation level reached 1 000 CPS, and the applicant may immediately isolate the purge OR refer to the RAP prior to isolating the purge).

Due to noise when conducting multiple JPMs, the applicant may not hear the annunciator 1 OF2d. When annunciator 1 OF-2-d alarms, inform the applicant there is an alarm on Panel 1 OF. When they go to RAP-1 OF2d, hand them a yellow copy of the RAP.


Appendix C

Note/Cue:

Standard:

Comment:

SAT/UNSAT





Form ES-C-1

Mark the time the depressurization was started on the stack gas recorder (Panel 1 OF) These recorders have been changed to electronic recorders and do not allow marking. If questioned, state the recorder has been marked.


Appendix C

Standard:





Form ES-C-1

If stack gas activity exceeds 1000 cps, then immediately secure the purge:

a. Close Drywell Vent V-27-1

b. Close Drywell Vent V-27-2

c. Notify the US

If stack gas activity exceeds 1000 cps, then immediately secure the purge:

a. Closes Drywell Vent V-27-1

b. Closes Drywell Vent V-27-2

By taking their control switches CCW (green lights on; red lights off)

c. Notifies the US (not required for Critical Step)

Note: The Applicant may isolate the valves when annunciator 1 OF2d, Stack Effluent Hi alarms (an indication that Stack RAGEMS is

Comment:

SAT/UNSAT

> 1000 CPS) OR they may refer to the RAP first, then isolate the purge valves.

Terminating Cue: Drywell air purge has been initiated, then isolated when stack effluent hi alarm annunciates (indicating that stack gas high radiation indicated> 1000 CPS)



Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response:

Result:



NRC Sim JPM 4

---------------------



NRC Sim JPM 4

Form ES-C-1

Page 14 of 16


Simulator Setup

1. This JPM can be performed at any power level

2. Insert the following:

a. ANN-C4f to OFF

b. ANN-C5f to OFF

Form ES-C-1

c. This keeps the Torus-OW Vacuum Breakers Open annunciators off

3. Place the following on Conditional Trigger 1: hwx08o037r.eq.1

a. When Drywell vent valve V-27-2 red light comes on, Trigger 1 will initiate


a. ANN-1 OF-2d to ON on a 10 sec time delay

5. Have a copy of 312.9 section 9.0 marked up to and including step 9.3.5.

6. Have a yellow copy of RAP-1 OF2d to hand to the applicant when they locate the RAP.


Appendix C

Initial Conditions:


STUDENT HANDOUT

1. The plant is at rated power preparing for a shutdown

2. Entry into the Primary Containment will be required

Form ES-C-1

3. The Primary Containment is being prepared to be purged with air, lAW 312.9, Primary Containment Control

4. All Prerequisites of Section 9.0, Purging Primary Containment With Air, are complete

5. Stack RAG EMS is OOS; Chemistry is sampling daily

Task Cue:

Purge the Primary Containment with air lAW 312.9, Primary Containment Control, starting at Step 9.3.6


Appendix C



Task No.: 2620104001

Form ES-C-1

Task Title: De-energize 1 A 1 Substation Transformer by Cross-tieing USS 1A1 to USS 181


K/A Reference: 262001 A 1.05 (3.2/3.5)

Examinee: Examiner:


Method of Testing:





Initial Conditions:

1. The plant is in a COLD SHUTDOWN CONDITION

2. Transformer USS 1 A 1 is over-heated and needs to be removed from service while still supplying power to USS 1A1

3. Section 8.0, De-Energizing Unit Substation Transformers, of procedure 337,4160 Volt Electrical System, is complete up to Section 8.1.3

4. An EO has been briefed, has a copy of the procedure, and is standing by for support

5. Electrical Maintenance has been briefed and is standing by for support

Task Standard: USS 1 A 1 transformer has been removed from service lAW procedure 337, Section 8.0



Appendix C

General References:


1. 337,4160 Electrical System, Revision 97

Form ES-C-1

Initiating Cue: Continue in procedure 337, 4160 Electrical System, starting at Step 8.1.3, to de-energize Transformer 1 A 1






Form ES-C-1


Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT

Performance Step: 1




Performance Step: 2



Note: The Evaluator should be in communication with the Booth during this JPM. Where annotated, the Booth will perform the listed actions and notify the Evaluator. The Evaluator will provide feedback of the actions to the Applicant.




Performance Step: 3


Rack in Tie Breaker EC

Form ES-C-1

Standard: Directs the EO to rack-in breaker EC

Booth/Cue: Activate Trigger 1. Report that Breaker EC is racked-in.

Comment:

SAT/UNSAT

Standard:

Note:

Comment:

SAT/UNSAT

Performance Step: 4


Close Tie Breaker EC (Panel 8F/9F)

Closes Tie Breaker EC with the control switch to CLOSE (green light off; red light on)

Annunciator T8a will alarm and the Applicant may respond to the associated RAP (no actions required)




Performance Step: 5


Rack in Tie Breaker ED

Form ES-C-1

Standard: Directs the EO to rack-in breaker ED

Booth/Cue: Activate Trigger 2. Report that Breaker ED is racked-in.

Comment:

SAT/UNSAT

Standard:

Note:

Comment:

SAT/UNSAT

Performance Step: 6


1. Place Synchroscope Switch for Tie Breaker ED to ON

2. Place TIE BREAKER ED control switch to CLOSE

3. Verify TIE BREAKER ED red closed light is illuminated

4. Place the Synchroscope Switch for Tie Breaker ED to OFF

1. Places Synchroscope Switch for Tie Breaker ED to ON

2. Checks voltages matched on Running and Incoming

3. Places TIE BREAKER ED control switch to CLOSE (green light off; red light on)

4. Verifies TIE BREAKER ED red closed light is illuminated

5. Places the Synchroscope Switch for Tie Breaker ED to OFF (Note: Only steps 1 & 3 required for Critical Step)

Annunciator T8e will alarm and the Applicant may respond to the associated RAP (no actions required)


Appendix C

Cue:

Standard:

Comment:

SAT/UNSAT



Performance Step: 7


Install jumper from TB6-22 to TB6-24 in Panel 8F/9F

Form ES-C-1

Report that the jumper from TB6-22 to TB6-24 in Panel 8F/9F is installed, and has been concurrently verified. Also report that both performers have signed for the step.

Jumper installed.

Performance Step: 8


Rack in Tie Breaker US1 T

Standard: Directs the EO to rack-in Breaker US1T

Booth/Cue: Activate Trigger 3. Report that Breaker US1T is racked-in.

Comment:

SAT/UNSAT


Appendix C

Standard:

Note:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT



Performance Step: 9


Close TIE BREAKER US1T (Panel 8F/9F)

Form ES-C-1

Closes TIE BREAKER US1T with the control switch to CLOSE (green light off; red light on)

Annunciator U7b will alarm and the Applicant may respond to the associated RAP (no actions required)



Open MAIN BREAKER 1 A 1M (Panel 8F/9F)

Opens MAIN BREAKER 1A1M with the control switch to TRIP (green light on; red light off)


Appendix C

Standard:

Cue:

Comment:

SAT/UNSAT





Open FEEDER BREAKER 1 A 1 P (Panel 8F/9F)

Form ES-C-1

Opens FEEDER BREAKER 1A1 P with the control switch to TRIP (green light on; red light off)

At the conclusion of this step, report that another Operator will complete the procedure.

Terminating Cue: USS 1 A 1 transformer has been removed from service lAW procedure 337, Section 8.0



Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:



NRC Sim JPM 5


Time to Complete:

Question:

Response:



NRC Sim JPM 5

Form ES-C-1

Page 9 of 11


Simulator Setup

Form ES-C-1

1 . The plant is in a scrammed condition with the reactor Mode switch in Shutdown

2. Insert LOA-EDS022 to CLOSE

a. This places the Tie Breaker EC 69 Permissive switch in Close

3. Place the following on Trigger 1

a. LOA-EDS021 to RACKED IN

i. This will rack-in Tie Breaker EC

4. Insert LOA-EDS031 to CLOSE

a. This places the Tie Breaker ED 69 Permissive switch in Close



i. This will rack-in Tie Breaker ED

6. Insert the following:

a. LOA-EDS068 to JUMPERED

i. This inserts jumpers on breaker US1 T



i. This will rack-in Breaker US1 T


Appendix C

Initial Conditions:


STUDENT HANDOUT

1. The plant is in a COLD SHUTDOWN CONDITION

Form ES-C-1

2. Transformer USS 1 A 1 is over-heated and needs to be removed from service while still supplying power to USS 1A1

3. Section 8.0, De-Energizing Unit Substation Transformers, of procedure 337, 4160 Volt Electrical System, is complete up to Section 8.1.3

4. An EO has been briefed, has a copy of the procedure, and is standing by for support

5. Electrical Maintenance has been briefed and is standing by for support

Task Cue:

Continue in procedure 337, 4160 Electrical System, starting at Step 8.1.3, to de-energize Transformer 1 A 1


Appendix C



Task No.: 2450201302

Form ES-C-1

Task Title: Perform Anticipatory Scram Turbine Stop Valve Closure Test with RPS Actuation (Alternate Path)


K/A Reference: 212000 A2.19 (3.8/3.9)

Examinee: Examiner:


Method of Testing:

Simulated Performance Actual Performance X ----




Initial Conditions:

1 . The plant is steady at 90% power with no other testing in-progress.

2. All prerequisites have been verified.

3. The procedure is complete up through step 6.2.

4. All relays have been flagged

Task Standard: The Candidate recognizes a% scram when Turbine Stop Valve #2 is tested and places the MAIN STOP VALVE TEST SELECT switch in OFF, resets the% scram, notifies the Shift Manager, and exits the test.


General References:

1. Procedure 619.4.002, Anticipatory Scram Turbine Stop Valve Closure Test (>45% Load), revision 23



Form ES-C-1

Initiating Cue: Perform Procedure 619.4.002, Anticipatory Scram Turbine Stop Valve Closure Test (>45% Load), starting at Step 6.3. You will perform all verifications lAW the surveillance.






Form ES-C-1


-----

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT

Performance Step: 1




Performance Step: 2

Procedure Step: Reviews Precautions and Limitations.





Form ES-C-1

NOTE: Procedure step 6.3 requires no actions or verifications by the candidate and is not listed as a Performance Step here .


Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT

Procedure Step: 6.4

Place the Main Stop Valve Test Select switch in No.3 position

Places the MAIN STOP VALVE TEST SELECT switch in No.3 position

Performance Step: 4

Procedure Step: 6.5

Momentarily press pushbutton Main Stop Valve Test

Momentarily presses the MAIN STOP VALVE TEST pushbutton


Appendix C

Standard:

Cue:

Comment:

SAT/UNSAT

Standard:

Cue:

Comment:

SAT/UNSAT



Performance Step: 5


Verify No. 3 Stop Valve closed

Form ES-C-1

Verifies No.3 Stop Valve closed (MAIN STOP VALVE POSITION No. 3 pointer points to C. The Candidate may also verify position indication lights on Panel 7F, red light OFF and green light ON.)

If the Candidate starts to go around front to Panel 7F, state that No.3 Stop Valve indicates closed.

Performance Step: 6


Verify the following:

• Relay 1 K 12 energized

• Relay 2K11 energized

• Relay 1 K52 energized

• Relay 2K51 energized

Verifies the following relays energized: 1 K12, 2K11, 1 K52, and 2K51.

RPS relays are not modeled. State that Relays 1 K12, 2K11, 1 K52, and 2K51 are energized.

NOTE: Procedure step 6.6 requires no actions or verifications by the candidate and is not listed as a Performance Step here.


Appendix C

Standard:

Comment:

SAT/UNSAT

-----

Standard:

Cue:

Comment:

SAT/UNSAT



Performance Step: 7

Procedure Step: 6. 7

Form ES-C-1

Place the Main Stop Valve Test Select switch in No.2 position

Places the MAIN STOP VALVE TEST SELECT switch in No. 2 position

Performance Step: 8


Verify No. 3 Stop Valve opens

Verifies No.3 Stop Valve opens (MAIN STOP VALVE POSITION No. 3 pointer points to 0. The Candidate may also verify position indication lights on Panel 7F as red light ON and green light OFF)

If the Candidate starts to go around front to Panel 7F, state that No. 3 Stop Valve indicates open.


Appendix C

Standard:

Cue

Comment:

SAT/UNSAT



Performance Step: 9


Verify all Stop valves open

Form ES-C-1

Verifies all Stop valves open (all MAIN STOP VALVE POSITION No. 1, 2, 3, 4 pointers point to 0. The Candidate may also verify position indication lights on Panel 7F as red lights ON and green lights OFF)

If the Candidate starts to go around front to Panel 7F, state that all Stop Valves indicates open.

NOTE: The following step will result in an unexpected Y2 scram. This initiates the Alternate Path.

Standard:

Note:

Cue:

Comment:

SAT/UNSAT


Procedure Step: 6.8

Momentarily press pushbutton Main Stop Valve Test

Momentarily presses pushbutton Main Stop Valve Test

This will result in a Y2 scram condition. When recognized by the candidate, provide the cue below.

Relay 1 K 11 is de-energized

Note: The Candidate will now apply prior Step 6.6.






Form ES-C-1

Immediately open No. 2 Stop Valve by placing the Main Stop Valve Test Select switch in OFF.

Standard: Immediately opens No. 2 Stop Valve by placing the MAIN STOP VALVE TEST SELECT switch in OFF

Notify the When TSV 2 indicates full open, DELETE MAL-RL Y-RPS021A Booth:

Comment:

SAT/UNSAT

Note/Cue:

Standard:

Comment:

SAT/UNSAT



Reset the half-scram

The candidate may ask for concurrent verification for resetting the Yz scram. State that you will perform the concurrent verification and agree with what ever action the candidate proposes.

Resets the half-scram by pressing the SCRAM SYSTEM RESET pushbutton (RPS 1 SCRAM SOLENOIDS ON)


Appendix C

-----

Standard:

Cue:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT





Notify the Shift Manager

Notifies the Shift Manager

As the Shift Manager, acknowledge the report



Exit this procedure

Exits this procedure

Form ES-C-1

Terminating Cue: The Candidate recognizes a% scram when Turbine Stop Valve #2 is tested and places the MAIN STOP VALVE TEST SELECT switch in OFF, resets the% scram, notifies the Shift Manager, and exits the test.



Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response:

Result:



NRC Sim JPM 6



NRC Sim JPM 6

Form ES-C-1

Page 10 of 12


Simulator Setup

Form ES-C-1

1. Reset to full power IC-115 and reduce recirculation flow to <90% power. (about 40 hz)

2. Insert Trigger: on Trigger 1, insert the following:

• hwx31 d047r.lt.0.50

3. Insert malfunction RL Y-RPS021A on Trigger 1. When Stop Valve #2 goes closed, this will de-energize relay 1 K11.

4. Verify all Turbine Stop Valve selsyns indicate OPEN on Panel 14R.

5. Have a copy of the procedure completed up to and including step 6.2. (619.4.002).

6. When Stop Valve #2 is re-opened, delete RL Y-RPS021A.

7. Place flags on RPS relays: 1 K11, 1 K12, 2K11, 2K12


Appendix C

Initial Conditions:


STUDENT HANDOUT

Form ES-C-1

1 . The plant is steady at 90% power with no other testing in-progress.

2. All prerequisites have been verified.

3. The procedure is complete up through step 6.2.

4. All relays have been flagged

Task Cue:

Perform Procedure 619.4.002, Anticipatory Scram Turbine Stop Valve Closure Test (>45% Load), starting at Step 6.3. You will perform all verifications lAW the surveillance.


Appendix C



Task No.:

Task Title: Swap Instrument Air Compressors


K/A Reference: 300000 K4.04 (2.8 I 2.9)

Examinee: Examiner:


Method of Testing:

2790101001




Form ES-C-1

X


Initial Conditions:

1. The plant is at rated power.

Task Standard: Air compressor #2 has been placed in LEAD and air compressor #1 has been placed in LAG.


General References:

1. 334, Instrument and Service Air System, revision 126

NRC Sim JPM7 Page 1 of 9

Appendix C

Initiating Cue:


Form ES-C-1

1. Place #2 Compressor in LEAD and #1 Compressor in LAG lAW 334, Instrument and Service Air System, Section 7.4. This includes air compressor starts from the Control Room.

o All prerequisites and precautions and limitations are met

o Steps 7.4.1.1 and 7.4.1.2 have been completed by the EO who is at the air compressors with the a copy of the procedure

o The announcement for starting air compressors has been made

o Local Air Compressor #2 indication indicates "stopped in Auto Restart"

o All starting and stopping of air compressors will be done from the Control Room






Form ES-C-1


-----

Standard:

Comment:

SAT/UNSAT

Standard:

CUE:

Comment:

SAT/UNSAT

Performance Step: 1




Performance Step: 2


STARTS the #2 Compressor: PLACE the Panel 7F Control Switch to STOP, and allow the switch to spring return to normal after stop. PLACE the Panel 7F Control Switch to START, and hold for 3-5 seconds, or press the local start (green) button.

Starts the #2 Compressor by placing the Panel 7F Control Switch to STOP, and allow the switch to spring return to normal after stop. Then places the Panel 7F Control Switch to START, and hold for 3-5 seconds.

May call the EO to verify air compressor #2 local indication (provided in Initial Conditions). If called report that air compressor #2 local display indicates "stopped in Auto Restart".




Form ES-C-1

Note: Step 7.4.1.7 is N/A

CUE:

Standard:

Comment:

SAT/UNSAT

Performance Step: 3


DIRECTS the EO to verify:

• Bearing oil pressure is 40-50 psig, for #1 and #2 Air Compressors, 45 to 55 psig for #3 Air Compressor.

• TBCCW is observed flowing in the sight glass, and TBCCW leaving the compressor is less than 125°F.

As the EO directed to verify air compressor #2 indications following the start, report a good start on air compressor #2 and all indications are in the normal range.

DIRECTS the EO to verify:

• Bearing oil pressure is 40-50 psig, for #1 and #2 Air Compressors, 45 to 55 psig for #3 Air Compressor.

• TBCCW is observed flowing in the sight glass, and TBCCW leaving the compressor is less than 125°F.


Appendix C

Standard:

Comment:

SAT/UNSAT



Performance Step: 4


Form ES-C-1

STOP the compressor to be removed from service by placing the control switch to the STOP. (Panel ?F)

Stops the compressor to be removed from service by placing the control switch to the STOP. (Panel ?F). Verifies indications the compressor is stopped.

NRC Sim JPM? Page 5 of 9

Appendix C

CUE:

Standard:

Comment:

SAT/UNSAT



Performance Step: 5

Procedure Step: 7.4.1.1 0

Form ES-C-1

Directs the EO to confirm the air compressor #1 for LAG operation settings are as specified in Attachment 334-9.

Report that air compressor #1 setting have been adjusted lAW Attachment 334-9 and air compressor #1 is in LAG. Inform the applicant another operator will continue with the procedure and the JPM is complete.

Air Compressor #1 is in LAG and settings have been adjusted lAW Attachment 334-9.

Terminating Cue: Air Compressor #1 is in LAG and #2 Compressor is in LEAD.



Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:



NRC Sim JPM 7


Time to Complete:

Question:

Response:



NRC Sim JPM7

Form ES-C-1

Page 7 of 9


JPM Setup

Form ES-C-1

CAUTION: Line item #2 below MUST be completed prior to EVERY JPM, even if the IC was snapped to 0. Air Compressor #2 will revert back to LAG after every simulator initialization.

1. Reset to full power IC or equivalent.

NOTE: The initial conditions of the JPM may not match with the simulator I C.

NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. Insert LOA-CAS038 to LEAD (This places air compressor #2 in the LEAD setting)

3. Ensure air compressor #2 is labeled "stopped in Auto Restart"

4. Have a copy of procedure 334, section 7.4, for swapping the air compressors for the applicant marked up with steps 7.4.1.1 and 7.4.1.2 complete and a copy of Attachment 334-9


Appendix C

Initial Conditions:


STUDENT HANDOUT

1. The plant is at rated power.

Initiating Cue:

Form ES-C-1

2. Place #2 Compressor in LEAD and #1 Compressor in LAG lAW 334, Instrument and Service Air System, Section 7.4. This includes air compressor starts from the Control Room.

o All prerequisites and precautions and limitations are met

o Steps 7.4.1.1 and 7.4.1.2 have been completed by the EO who is at the air compressors with the a copy of the procedure

o The announcement for starting air compressors has been made

o Local Air Compressor #2 indication indicates "stopped in Auto Restart"

o All starting and stopping of air compressors will be done from the Control Room



Form ES-C-1


Task Title: Swap Control Room Ventilation Fans (Alternate Path)

Job Performance Measure No.: NRC JPM Sim 8

K/A Reference: 290003 A4.02 (2.8/2.8)

Examinee: Examiner:


Method of Testing:





Initial Conditions:

1. The B Control Room Ventilation System is currently in service and needs to be removed from service for maintenance.

2. All prerequisites have been verified to perform the procedure, including TBCCW and Instrument, Service and Breathing Air Systems.

3. An EO has been briefed on the evolution, has a copy of the procedure and a radio and is ready to support the evolution.

4. The procedure has been completed up to and including step 1 0.4.6.

Task Standard: The Control Room Ventilation Systems have been swapped from B to A, and the A Ventilation System has been placed in the PART RECIRC emergency mode.


General References:

1. Procedure 331.1, Control Room and Old Cable Spreading Room Heating, Ventilation and Air Conditioning System, revision 39.

2. RAP-10F1k, AREA MON HI, Rev 004.

NRC JPM Sim 8 Page 1 of 15


Form ES-C-1

Initiating Cue: Swap Control Room Ventilation Systems lAW Procedure 331.1, Control Room and Old Cable Spreading Room Heating, Ventilation and Air Conditioning System, starting at step 10.4.7.






Form ES-C-1


Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT

Performance Step: 1




Performance Step: 2

Procedure Step: Reviews Precautions and Limitations.

Reviews Precautions and Limitations.


Appendix C

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT



Performance Step: 3

Procedure Step: 1 0.4.7

Form ES-C-1

Stop 8 Control Room HV AC by placing FN-826-0088 System Initiation switch to OFF (Panel 9XR).

Places the CONTROL ROOM HVAC 8 SYSTEM INITIATION control switch to OFF (red light OFF, green light ON).

Performance Step: 4


Verify FN-826-0088, Supply Fan stopped.

Verifies CONTROL ROOM HVAC 8 Supply Fan OFF (red light OFF, green light ON).


Appendix C

-----

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT



Performance Step: 5


Verify Isolation Dampers are closed.

• DM-826-039 (Panel 9XR)

• DM-826-040 (Panel 9XR)

Verifies Isolation Dampers are closed.

Form ES-C-1

• DM-826-039 (Panel 9XR) (red light OFF, green light ON)

• DM-826-040 (Panel 9XR) (red light OFF, green light ON)

Performance Step: 6

Procedure Step: 1 0.4.1 0

Momentarily place the A Control Room HVAC System Bypass switch in RESET (Panel 11 R).

Momentarily places the CONTROL ROOM HVAC A SYSTEM BYPASS switch in RESET.


Appendix C

Cue:

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT



Performance Step: 7


Form ES-C-1

Place mode selector for System A to the desired position (Panel 11 R).

If the Applicant asks which mode to be in, state "normal mode".

Confirms the CONTROL ROOM HVAC A SYSTEM MODE switch is in NORM.

Performance Step: 8


Start "A" Control Room HV AC by placing FN-826-008A System Initiation switch to ON (Panel 11 R).

Places the CONTROL ROOM HVAC A SYSTEM INITIATION switch to ON (red light ON, green light OFF).


Appendix C

-----

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT



Performance Step: 9


Verify Isolation Dampers are open.

• DM-826-042 (Panel 11 R)

• DM-826-043 (Panel 11 R)

Verifies Isolation Dampers are open.

Form ES-C-1

• DM-826-042 (Panel 11 R) (red light ON, green light OFF)

• DM-826-043 (Panel11 R) (red light ON, green light OFF)



Verify FN 826-008A, Supply Fan is running.

Verifies CONTROL ROOM HVAC A Supply Fan ON (red light ON, green light OFF).


Appendix C

Note/Cue:

Standard:

Comment:

SAT/UNSAT





Form ES-C-1

CONFIRM CLOSED refrigeration compressor circuit breakers on side of air conditioning unit 1-826-001 A based on heat load. (New Cable Spreading Room)

The Applicant may ask how many breakers to close: close those breakers which were opened earlier.

Directs the EO to confirm CLOSED refrigeration compressor circuit breakers on side of air conditioning unit 1-826-001 A based on heat load. (New Cable Spreading Room)

NOTE: Step 10.4.16 is N/A


Appendix C

-----

Standard:





Form ES-C-1

Start FN-826-009, Kitchen and Toilet Fan as needed by placing its five-minute timer control switch in START.

Note/Cue 1: This is not modeled in the simulator. The kitchen fan timer is in start.

Comment:

SAT/UNSAT

NOTE: The following steps presents an Alternate Path for the Applicant.

Performance Step: 13 -----Note: If the Applicant does not respond to the front panel alarm while at

the back panel, provide the cue below.

Cue: Respond to the control room alarm.

Standard:

NOTE:

Comment:

SAT/UNSAT


Provides repeat back of initiating cue. Evaluator acknowledges the repeat back. When the Applicant locates the alarm response procedure RAP-1 OF1 k, then provide a copy of the alarm response to the Applicant.

Depending on what JPM is performed in parallel with this JPM, the applicant may not recognize to respond to annunciator 1 OF-1-k. When this annunciator comes in tell the applicant to respond to all annunciators on Panel 1 OF, or cue them that 1 OF1 k came into alarm.


Appendix C

Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT




Procedure Step: RAP-1 OF1 k

Form ES-C-1

Check area radiation monitors to determine area of high radiation (Panei2R).

Checks area radiation monitors to determine area of high radiation (Panel 2R). Determines that area radiation monitor R01 0-A 1 is above the high alarm setpoint.



Confirm high radiation condition at radiation monitors:

• R14C-1, R014C-3 through R014C-7

• R014B-7, R014B-9

• R014C-9, R015C-10

Confirm high radiation condition at radiation monitors:

• R14C-1, R014C-3through R014C-7

• R014B-7, R014B-9

• R014C-9, R015C-10

Confirms that no high radiation at these monitors exists




Form ES-C-1

NOTE: Since no high radiation is confirmed, then entry into the Secondary Containment Control EOP is not required and the next RAP step (not included here) is NA.

Standard:

Cue:

Comment:

SAT/UNSAT

Standard:

Cue:

Comment:

SAT/UNSAT



Refer to EP-AA-1 010, Radiological Emergency Plan for Oyster Creek Generating Station to determine EAL.

Refers the SRO to EP-AA-1010, Radiological Emergency Plan for Oyster Creek Generating Station to determine EAL.

As the SRO, acknowledge the report.


Procedure Step: RAP-10F1k

Notify the Shift Manager.

Notifies the Shift Manager.

As the Shift Manager, acknowledge the report.


Appendix C

Standard:

Cue:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT





Form ES-C-1

As directed, announce over the page system the evacuation requirements of the specific area.

As directed, announces over the page system the evacuation requirements of the specific area.

Another Operator will make the announcement.



For RO 1 OA-1, RO 1 OA-2 or RO 1 OA-3, place the Control Room HVAC in PART RECIRC in accordance with Procedure 331.1, Control Room and Old Cable Spreading Room Heating Ventilation and Air Conditioning.

Places the CONTROL ROOM HVAC A SYSTEM MODE switch in PART RECIRC (amber PART RECIRC light ON, NORM light OFF).

Task Standard: The Control Room Ventilation Fans have been swapped from B to A, and the A Ventilation System has been placed in the PART RECIRC emergency mode.



Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:



NRC JPM Sim 8


Time to Complete:

Question:

Response:



NRC JPM Sim 8

Form ES-C-1

Page 13 of 15


Simulator Setup

1. Reset to full power IC-115

2. Verify CR HV AC System B is in operation

Form ES-C-1

3. Have procedure 331.1, section 10 complete up to and including step 1 0.4.5.

4. Have a clean copy of RAP-10F1k, AREA MON HI.

5. Have a copy of 331.1, step 5.4, ready to hand to the applicant for Step 19.

6. Insert the following conditional trigger on Trigger 1: hwx22o303b.gt.O

a. This will activate Trigger 1 when the CR Vent System A damper DM 826-042 red light comes on


a. ICH-RMS005A to 0.8 on a 2 minute time delay

i. This places radiation monitor R01 0-A 1 above its high alarm setpoint of 5 mr/hr (to 6.3 mr/hr) (Admin Bldg Entr to Turb Bldg ARM) after 2 minutes. When this radiation monitor goes above it upscale limit, annunciator 1 OF1 k, AREA MON HI.

Note: The 2 minute time delay may be made longer or shorter if required. It is intended that the actions above occur when the Applicant has completed the procedure to swap CR HVAC fans; or, the above actions may be manually inserted at the required time without the trigger.


Appendix C

Initial Conditions:


STUDENT HANDOUT

Form ES-C-1

1. The B Control Room Ventilation Fan is currently in service and needs to be removed from service for maintenance.

2. All prerequisites have been verified to perform the procedure, including TBCCW and Instrument, Service and Breathing Air Systems.

3. An EO has been briefed on the evolution, has a copy of the procedure and a radio and is ready to support the evolution.

4. The procedure has been completed up to and including step 1 0.4.6.

Task Cue:

Swap Control Room Ventilation Systems lAW Procedure 331.1, Control Room and Old Cable Spreading Room Heating, Ventilation and Air Conditioning System, starting at step 1 0.4.7.


Appendix C



Task No.: 3420302008

Form ES-C-1

Task Title: Control CRD Flow Post-Scram lAW Support Procedure 3

Job Performance Measure No.: NRC Plant JPM 1

K/A Reference: 201001 A 1.03 (2.9/2.8)

Examinee: Examiner:


Method of Testing:

Simulated Performance X Actual Performance -----

Classroom Simulator Plant X ----- -----



Initial Conditions:

1. The plant was at rated power when an event occurred. Present plant conditions include the following:

a. All control rods indicate full-in

b. RPV water level is 11 0" and rising slowly

c. Drywall pressure is 3.8 psig and steady

d. Both CRD Pumps are running

e. You have a set of Building Keys

f. RP has been contacted; permission has been granted to go above 7ft.

Initiating Cue:

1. Control CRD injection into the RPV lAW Support Procedure 3, CRD System Operation, Step 3.5, to establish 150 gpm CRD flow.


NRC Plant JPM 1 Page 1 of 8

Appendix C

General References:


1. EMG-SP3, CRD System Operation, Rev 000.

Form ES-C-1

Task Standard: V-15-30 is being throttled and CRD flow is approximately 150 gpm as indicated on Flow Gage Fl-225-2 (RB 23 SE).






Form ES-C-1


Standard:

Comment:

SAT/UNSAT

Standard:

CUE:

Comment:

SAT/UNSAT

Performance Step: 1




Performance Step: 2


CLOSE CAD Charging Header Supply Valve V-15-52 (RB 23 SE).

Closes CAD Charging Header Supply Valve V-15-52 by rotating the valve handwheel CW until it stops.

CAD Charging Header Supply Valve V-15-52 is closed.


Appendix C

Standard:

CUE:

NOTE:

Comment:

SAT/UNSAT

-----

Standard:

Comment:

SAT/UNSAT



Performance Step: 3


Form ES-C-1

OPEN CRD Bypass Isolation Valve, V-15-237 (RB 23 SE).

Opens CRD Bypass Isolation Valve V-15-237 by rotating the valve handwheel CCW until it stops.

CRD Bypass Isolation Valve V-15-237 is open.

No CRD flow will be indicated in the Performance Step 4 below UNTIL V-15-30 is opened in Performance Step 5. Flow will then be monitored as V-15-30 is throttled open.

Performance Step: 4


MONITOR flow on Flow Gage Fl-225-2 (RB 23 SE).

Monitors flow on Flow Gage Fl-225-2.


Appendix C

Standard:

CUE:

Comment:

SAT/UNSAT



Performance Step: 5


Form ES-C-1

THROTTLE Open CRD Bypass Valve, V-15-30 (RB 23 SE), so as not to exceed 150 gpm flow for one or two pump operation.

Throttle Open CRD Bypass Valve, V-15-30, so as nQ! to exceed 150 gpm flow for one or two pump operation, by rotating the valve handwheel CCW.

When V-15-30 is initially opened, report flow indicates 100 GPM. When V-15-30 is throttled open a second time, report that flow indicates 150 GPM.

Terminating Cue: V-15-30 is being throttled and CRD flow is approximately 150 gpm as indicated on Flow Gage Fl-225-2 (RB 23 SE).



Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:



NRC Plant JPM 1


Time to Complete:

Question:

Response:



NRC Plant JPM 1

Form ES-C-1

Page 6 of 8

Appendix C

1. None

NRC Plant JPM 1


JPM Setup

Form ES-C-1

Page 7 of 8

Appendix C

Initial Conditions:


Form ES-C-1

1. The plant was at rated power when an event occurred. Present plant conditions include the following:

a. All control rods indicate full-in

b. RPV water level is 11 0" and rising slowly

c. Drywall pressure is 3.8 psig and steady

d. Both CRD Pumps are running

e. You have a set of Building Keys

f. RP has been contacted; permission has been granted to go above 7ft.

Task Cue:

Control CRD injection into the RPV lAW Support Procedure 3, CRD System Operation, Step 3.5, to establish 150 gpm CRD flow.

There will be no manipulations of plant components. All•inu~ations are to be simulated.



Form ES-C-1

Facility: Oyster Creek Task No.: 2090501403/2090504401

Task Title: Align the Core Spray System to the Condensate Storage Tank for Emergency Operations

Job Performance Measure No.: NRC Plant JPM 2

K/A Reference: 295030 EA 1.06 (3.4/3._4),___ __ _

Examinee: Examiner:


Method of Testing:


Classroom Simulator Plant X ----- -----



Initial Conditions:

1. The Reactor is shutdown.

2. Reactor water level is being maintained at 160 inches with feedwater.

3. Drywell pressure is 1.1 psig and stable.

4. Tor us water level is 140 inches and lowering due to a leak.

5. The Reactor Building is accessible.

6. You have a full set of Building Keys.

Initiating Cue:

1. Line up and makeup to the torus from the CST via Core Spray System 1 in accordance with EMG-SP37. Steps 3.2.1, 3.2.2, 3.2.3 and 3.2.4 have already been performed.


General References:

1. EMG-SP37, Makeup to the Torus via Core Spray System, Rev 001.



Form ES-C-1

Task Standard: Makeup to the torus from the CST via Core Spray System 1 in accordance with Support Procedure 37 has been lined-up.






Form ES-C-1


Standard:

Comment:

SAT/UNSAT

Standard:

Performance Step: 1




Performance Step: 2


Place the Core Spray pump suction valve breakers in OFF:

• V-20-3 (MCC 1 A21 A RB 23' SW)

• V-20-32 (MCC 1 B21 ARB 23' NE)

Places the Core Spray pump suction valve breakers in OFF:

• V-20-3 (MCC 1 A21 A RB 23' SW)

• V-20-32 (MCC 1 B21A RB 23' NE)

CUE: The breakers for valve V-20-3 and V-20-32 are in the OFF position. (Split CUES for each valve if required)

Comment:

SAT/UNSAT


Appendix C

Standard:



Performance Step: 3


Unlock and open the following CST valves:

• V-20-1 (NW corner Room)



Unlocks and opens the following CST valves:




Form ES-C-1

CUE: Valves V-20-1, V-20-5, and V-20-34 are unlocked and open. (Split CUES for each valve if required)

Comment:

SAT/UNSAT

Standard:

Cue:

Comment:

Performance Step: 4


Start ONE of the following Core Spray System 1 main pumps NZ01 A or NZ01 C.

Calls the Control Room to start Core Spray System 1 main pump NZ01A or NZ01C.

Core Spray Pump NZ01 A is running.


Appendix C

SAT/UNSAT



Form ES-C-1

NOTE: Step 3.2.6 is N/A

Standard:

CUE:

Comment:

SAT/UNSAT

-----

Standard:

CUE:

Comment:

SAT/UNSAT

Performance Step: 5


Unlock and place the breaker for V-20-27 in the ON position (MCC 1 A21 B RB 23' E).

Unlocks and places the breaker for V-20-27 in the ON position (MCC 1A21B RB 23' E).

V-20-27 breaker is ON.

Performance Step: 6


Open Torus Test Flow Return valve V-20-27 (Keylock RB 51' NW)

On RB 51' NW, opens Torus Test Flow Return valve V-20-27 by placing upper keylock switch to the OPEN position (red light ON).

Valve V-20-27 indicates full open and Torus water level is rising. This JPM is complete.

Terminating Cue: Makeup to the torus from the CST via Core Spray System 1 in accordance with Support Procedure 37 has been lined-up.


Appendix C

NRC Plant JPM 2



Form ES-C-1


Page 6 of 9

Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:



NRC Plant JPM 2


Time to Complete:

Question:

Response:



NRC Plant JPM 2

Form ES-C-1

Page 7 of 9


JPM Setup

1. Have a copy of SP-37 marked up to and including step 3.2.4

NRC Plant JPM 2

Form ES-C-1

Page 8 of 9

Appendix C

Initial Conditions:


1. The Reactor is shutdown.

Form ES-C-1

2. Reactor water level is being maintained at 160 inches with feedwater.

3. Drywell pressure is 1.1 psig and stable.

4. Tor us water level is 140 inches and lowering due to a leak.

5. The Reactor Building is accessible.

6. You have a full set of Building Keys.

Task Cue:

Line up and makeup to the torus from the CST via Core Spray System 1 in accordance with EMG-SP37. Steps 3.2.1, 3.2.2, 3.2.3 and 3.2.4 have already been performed.

There will be no •ipulations of plant components. All•inuplations are to be sindated.




Task Title: Swap Static Chargers from C1 to C2

Job Performance Measure No.: NRC PLANT JPM3

K/A Reference: 263000 K1.02 (3.2/3.3)

Examinee: Examiner:


Method of Testing:


Classroom Simulator Plant ----- -----


Form ES-C-1

X


Initial Conditions:

1 . The plant is at rated power

2. Static Charger C1 is currently supplying 125 VDC Bus C

3. Static Charger C2 is in standby and is ready to be placed in service

4. This task is being performed for equipment rotation

5. The SRO has addressed all applicable Tech Specs

6. Procedure 340.3, 125 Volt DC Distribution System C, has been completed up to and including Step 8.3.2

Task Standard: Static Charger C2 is supplying Bus C lAW 340.3


General References:

1. 340.3, 125 VDC Distribution Systems C, Revision 36



Form ES-C-1

Initiating Cue: Transfer operation from Charger C1 to the Alternate Static Charger C2 lAW procedure 340.3, 125 Volt DC Distribution System C, starting at Step 8.3.3.






Form ES-C-1


Standard:

Comment:

SAT/UNSAT

Standard:

Comment:

SAT/UNSAT

Performance Step: 1




Performance Step: 2




Appendix C

Standard:

Cue:

Comment:

SAT/UNSAT

Standard:

Cue:

Comment:

SAT/UNSAT



Performance Step: 3


Form ES-C-1

Open the DC OUTPUT breaker at the charger cabinet:

BTCHG C1\DC OUTPUT, Battery Charger C-1 DC Output breaker

or


Opens the DC OUTPUT breaker at the charger cabinet:

BTCHG C 1 \DC OUTPUT, Battery Charger C-1 DC Output breaker (Breaker to the OFF position)

The Battery Charger C-1 DC Output breaker is open

Performance Step: 4


Verify annunciator window 9XF-2-d, BUS C UV alarms

Calls the Control Room to verify annunciator window 9XF2d, BUS C UV is in alarm

Annunciator window 9XF2d, BUS C UV is in alarm


Appendix C

Standard:

Cue:

Comment:

SAT/UNSAT

Standard:

Cue:

Comment:

SAT/UNSAT



Performance Step: 5


Form ES-C-1

Open the breaker at Distribution Center C for the charger:

DC-C 125V\2, DC-C 125V Breaker 2 for Battery Charger C1 Output

or

DC-C 125V\ 1, DC-C 125V Breaker 1 for Battery Charger C2 Output.

Opens the breaker at Distribution Center C for the charger:

DC-C 125V\2, DC-C 125V Breaker 2 for Battery Charger C1 Output (Breaker to the OFF position)

DC-C 125V Breaker 2 for Battery Charger C 1 Output is open

Performance Step: 6


Verify annunciator window 9XF-5-d, BUS C INPUT BRKRS OPEN alarms

Calls the Control Room to verify annunciator window 9XF-5-d, BUS C INPUT BRKRS OPEN is in alarm

Annunciator window 9XF-5-d, BUS C INPUT BRKRS OPEN is in alarm


Appendix C

Standard:

Cue:

Comment:

SAT/UNSAT

-----

Standard:

Cue:

Comment:

SAT/UNSAT



Performance Step: 7


Form ES-C-1

Close the breaker at Distribution Center C for the charger:

DC-C 125V\2, DC-C 125V Breaker 2 for Battery Charger C1 Output

or

DC-C 125V\ 1 , DC-C 125V Breaker 1 for Battery Charger C2 Output

Close the breaker at Distribution Center C for the charger:

DC-C 125V\ 1 , DC-C 125V Breaker 1 for Battery Charger C2 Output (Breaker to the ON position)

DC-C 125V Breaker 1 for Battery Charger C2 Output is closed

Performance Step: 8


Verify annunciator window 9XF-5-d, BUS C INPUT BRKRS OPEN clears

Calls the Control Room to verify annunciator window 9XF-5-d, BUS C INPUT BRKRS OPEN clears

Annunciator window 9XF-5-d, BUS C INPUT BRKRS OPEN is clear


Appendix C

Cue:

Standard:

Cue:

Comment:

SAT/UNSAT

Standard:

Cue:

Comment:

SAT/UNSAT



Performance Step: 9


Form ES-C-1

Adjust static charger C 1 or C2 float voltage rheostat to set voltage at or slightly above battery bus voltage

Inform the applicant they have a screwdriver with them (for the voltage adjustments)

Static Charger C2 float voltage is 131 volts.

Bus DC-C voltage is 132 volts

Adjusts static charger C2 float voltage rheostat to set voltage at or slightly above battery bus voltage by rotating the screw-adjust rheostat until float voltage is equal to or slightly above 132 volts

After adjustment, report that Static charger C2 float voltage indicates 132.5 volts.



Close the DC OUTPUT breaker at the charger cabinet:


or BTCHG C2\DC OUTPUT, Battery Charger C-2 DC Output breaker

Closes the DC OUTPUT breaker at the charger cabinet:

BTCHG C2\DC OUTPUT, Battery Charger C-2 DC Output breaker (Breaker to the ON position)

Battery Charger C-2 DC Output breaker is closed


Appendix C

Cue:

Standard:

Comment:

SAT/UNSAT





Form ES-C-1

Maintain voltage on Distribution Center C in accordance with Section 11.0


If the battery is not on an equalizing charge, then maintain voltage between 130.6 and 135

C Bus voltage indicates 132 VDC

Adjust the appropriate Static Charger rheostat as necessary to maintain DC System voltage as follows: lf_the battery is not on an equalizing charge, then MAINTAIN voltage between 130.6 and 135 (no adjustments are required)


Appendix C

-----

Standard:

Cue:

Comment:

SAT/UNSAT





Form ES-C-1

When C Bus voltage is adjusted above 130.5 VDC, then verify annunciator window 9XF-2-d, BUS C UV clears

Calls the Control Room to verify annunciator window 9XF-2-d, BUS C UV is clear

Annunciator window 9XF-2-d, BUS C UV is clear

Note: There are other steps to exit the Tech Specs and to shutdown the C1 Charger but this concludes the JPM.

Terminating Cue: Static Charger C2 is supplying Bus C lAW 340.3



Appendix C

JPM Number:

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question:

Response:

Result:



NRC Plant JPM3



NRC Plant JPM 3

Form ES-C-1

Page 10 of 12


JPM Setup

Form ES-C-1

1. When creating the procedure for the candidates' use, include section 11.0


Appendix C

Initial Conditions:


STUDENT HANDOUT


2. Static Charger C1 is currently supplying 125 VDC Bus C

Form ES-C-1

3. Static Charger C2 is in standby and is ready to be placed in service

4. This task is being performed for equipment rotation

5. The SRO has addressed all applicable Tech Specs

6. Procedure 340.3, 125 Volt DC Distribution System C, has been completed up to and including Step 8.3.2

Task Cue:

Transfer operation from Charger C1 to the Alternate Static Charger C2 lAW procedure 340.3, 125 Volt DC Distribution System C, starting at Step 8.3.3.

There will be no ~~anipulations of plld components. Allmainuplations are to be simulated.


I L T 13-1 NRC Scenario 1 (New)

Scenario Outline

Facility: Oyster Creek Scenario No.: 1 Op Test No.: 13-1 NRC

Examiners: Operators:

Initial Conditions: • 2% power with mode switch in STARTUP • Control rod withdrawal is in progress • Air Compressor #3 is tagged OOS • RWM is tagged OOS • lnerting the Primary Containment is on hold for a nitrogen delivery • Steam chest warming is in progress

Turnover: • Continue with rod withdrawal. Complete step 10 Group 3-1 starting at rod 26-23. When rod pulls

are complete wait for further direction from Reactor Engineering. Timing of rod position 00-02 is not required and Continuous Rod Withdrawal is authorized per Reactor Engineering.

Event No. Malt. No. Event Type* Event Description

1 N/A R ATC Raise reactor power with control rods lAW the ReMA

MAL-2 CRD007 - c ATC Stuck control rod {26-23)

2623

3 ICH- c BOP

ICS003A TS SRO Leak in Isolation Condenser Shell B

4 MAL- c BOP Loss of VMCC 1 B2 EDS004B TS SRO

5 MAL- c BOP The in-service RBCCW pump trips RBC001A

MAL-The standby RBCCW pump also trips resulting in a loss

6 RBC001B c ATC of all RBCCW flow which requires the ATC to scram the reactor; eight rods fail to insert

7 MAL- M Crew Steam leak in Drywell NSS017A

8 MAL- c Crew CRD Flow Control Valve fails closed CRD001A

(N)ormal, (R)eactivity, (J)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs

ILT 13-1 NRC Scenario 1 Page 1 of 27

ILT 13-1 NRC Scenario 1 (New)

Simulator Summary

Event Event Summary

1 The ATC will withdraw control rods to raise reactor power lAW the pull sheet and 302.2. (ATC: Reactivity Manipulation)

2 The ATC will respond to indications of a stuck control rod (26-23). The ATC will apply and insert signal to the stuck rod lAW ABN-6. The control rod will then move. The ATC will then continue withdrawing control rods. (ATC: Component Failure)

3 The BOP will respond to lowering level in Isolation Condenser B shell lAW RAP-C6b. The BOP will attempt fill the IC shell from Panel 5F/6F. The RB EO will report IC-A shell level is 6.6 ft. and slowly lowering (non-recoverable). The BOP will isolate IC-B and the SAO will declare IC B inoperable and apply Tech Spec 3.8.C. (BOP: Component Malfunction; SRO: Tech Spec)

4 The crew will respond to the trip of VMCC 1 B2 and enter ABN-51, Loss of VMCC 1 B2. The BOP will restore power to PSP-2 and the ATC will reset the Y2 scram. The SAO will review TS 3.7 and enter a 30 hr cold shutdown LCO. (BOP: Component Malfunction; SRO: Tech Specs)

5 The in-service RBCCW pump will trip and the crew will enter ABN-19. The BOP will diagnose a tripped pump and will start the standby RBCCW pump. (BOP: Component Malfunction)

6 The standby RBCCW pump will trip resulting in a loss of all RBCCW flow. The ATC will manually scram the reactor and may secure all running Recirculation Pumps (subsequent ABN action). Eight rods will fail to insert and the crew will enter RPV Control- with ATWS. (ATC: Component Malfunction) (PRA)

7 Three minutes after the mode switch is taken to Shutdown, a small but increasing RPV steam leak (LOCA) into the Primary Containment occurs. The steam leak will significantly increase requiring the crew to spray the OW to reduce Containment pressure. (Crew: Major)

8 The in-service CAD Flow Control Valve fails closed and manually driving control rods that failed to insert will no longer work. The ATC will swap Flow Control Valves lAW procedure 302.1, Control Rod Drive System, and continue manually driving all control rods that failed to insert OR will scram the affected rods individually from their individual scram test switches on Panel 6XR. (ATC: Component Malfunction)



Critical The crew will be required to manually insert rods that failed to scram Task 1 to achieve a shutdown reactor

Critical When Drywell or Torus pressure exceeds 12 psig, OR before Drywell Task 2 bulk temperature is determined it cannot be maintained below 281 °F,

spray the dryweiiiAW SP-29, Initiation of the Containment Spray System for Drywell Sprays.

ES-301·4 Target Quantitative Actual Event Attributes Attributes Number{s}

1. Total malfunctions (5·8) 7 2-8

2. Malfunctions after EOP entry (1·2) 2 7-8

3. Abnormal events (2·4) 2 4-5

4. Major transients (1·2) 1 7

5. EOPs entered/requiring substantive 2 6-7 actions (1-2)

6. EOP contingencies requiring substantive 1 6 actions (0-2)

7. Critical tasks (2·3) 2 7,8

ILT13-1 NRCScenario1 Page 3 of 27


Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 1 Event No.: 1 Event Description: Withdraw Control Rods to raise reactor Qower

Initiation: Following shift turnover

Cues: As directed by the SRO following shift turnover

Time Position Applicant's Actions or Behavior

SAO • Directs ATC to withdraw control rods lAW the pull sheet and 302.2

• Acts as the Reactivity Manager during the reactivity manipulation

ATC • Withdraws control rods lAW the pull sheet and 302.2

0 VERIFY the PERMIT light is illuminated

0 CONFIRM the ROD POWER Switch ON

0 SELECT the control rod to be withdrawn by momentarily depressing the pushbutton on the CONTROL ROD SELECT pushbutton matrix

• Verifies the control rod light is lit

• Verifies no other control rods are selected

0 TURN the ROD CONTROL Switch to ROD OUT NOTCH position and simultaneously TURN the NOTCH OVERRIDE

0 VERIFY the WITHDRAW light remains illuminated for the duration of rod withdrawal and an increasing rod position display is presented

0 ALLOW the rod to settle one notch before the desired position by simultaneously releasing the Rod Control Switch and the Notch Override Switch one digit before the desired notch position (one notch above the target notch) is reached, unless the control rod is being withdrawn to the full-out position

0 VERIFY that the rod latches in an even-numbered position before the SETTLE light extinguishes

NOTE: The third rod the candidate will move, Rod 26-23, will not move and Event 2 will occur. Rod withdrawal may continue after Rod 26-23 is un-stuck at the discretion of the Lead Evaluator.



BOP • Provides peer check for control rod movements

• Verifies the following during switch movement

0 Amber OVERRIDE light is illuminated

0 Green INSERT light is illuminated following switch movement and remains on for approximately 1 second

0 Rod position readout momentarily displays the next lower odd-numbered digit as the drive unlatches

Terminus: Control rods are withdrawn to the discretion of the Lead Evaluator.

Notes/Comments



Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 1 Event No.: g Event Description: A control rod will be stuck at Qosition 12 (26-23)

Initiation: When the ATC attempts to withdraw Control Rod 26-23.

Cues: Control Rod 26-23 will not move when withdrawal signal is applied.


ATC • Recognizes/reports a stuck control rod 26-23

• Enters and executes ABN-6 OR 302.2 P&L 6.2.7

0 Verifies that no Control Rod Blocks are in effect.

0 If CRD DR WTR PRESS indicates< 250 psid, adjusts to 250 psid.

0 If using ABN-6 and the US requests, consult with the System Manager and Reactor Engineering to determine if Procedure 235 should be performed concurrently with ABN-6. [ROLE PLAY 1]

ROLE PLAY 1: If requested, report as the System Manager and Reactor Engineering to complete actions of ABN-6, then perform actions of Procedure 235 if still necessary.

0 If the Control Rod will not move, apply RAISE drive water pressure to 300 psid and then attempt to withdraw the rod. [ROLE PLAY 2]

ROLE PLAY 2: When the ATC raises drive water pressure the first time, DELETE MAL-CRD007 _2623.

SRO • May directs entry into ABN-6 or use 302.2 P&L 6.2. 7 to free stuck rod

• May notify SM/WWM/Reactor Engineering

BOP • May announce entry into ABN-6 (may be performed by ATC)

Terminus: Control rod 26-23 has been un-stuck and is withdrawn to position 48.



Notes/Comments

IL T 13-1 NRC Scenario 1 Page 7 of 27


Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 1 Event No.:~ Event Description: Leak in Isolation Condenser Shell B [Trigger 1J Initiation: Control rod 26-23 has been un-stuck and is withdrawn to position 48., or as directed by the Lead Examiner. Cues: Annunciator C6b, SHELL B LVL HI/LO; ISOL CONDENSER B LEVEL indicates lower than normal Time Position Applicant's Actions or Behavior

BOP • Responds to annunciator C6b, SHELL B LVL HI/LO . 0 Reports Isolation Condenser shell level and trend. 0 May restore shell water level lAW procedure 307,

Isolation Condenser System, section 7.4.1, using Demineralized Water.

• Records initial shell water level on Attachment 307-15

• Opens V-11-34 on Panei5F/6F . • Verifies annunciator K6d is received . • Commences filling isolation condenser until

shell level indicates between 7.3 and 7.7 feet.

0 After shell level makeup has been initiated, reports Isolation Condenser Shell level is not rising.

0 May direct the EO to investigate Isolation Condenser B. [ROLE PLAY]

ROLE PLAY: When asked as the EO to investigate, report IC-B shell level is 6.6 ft. and slowly lowering. There is water on the floor under the ICs. The water is contained, directed to the floor drain, and no equipment is affected. If asked to verify 1-7 sump is not overflowing, report it is not overflowing and is not isolated.

0 If directed to isolate Isolation Condenser B, places the following switches in CLOSE:

• AC V-14-32 (steam) • DC V-14-33 (steam) • DC V-14-35 (condensate return) • AC V-14-37 (condensate return)

SRO • Declares Isolation Condenser B inoperable and applies Tech Spec 3.8.B, C.

0 The shell side of each condenser shall contain a minimum water volume of 22,730 gallons. If the minimum volume cannot be maintained or if a source of makeup water is not available to the condenser, the condenser shall be considered inoperable.

0 If one isolation condenser becomes inoperable during the run mode the reactor may remain in



operation for a period not to exceed 7 days provided the motor operated isolation and condensate makeup valves in the operable isolation condenser are verified daily to be operable.

• May direct arming IC-B thermal overloads lAW 307 step 11.7.1

• Notifies SM/WWM about Isolation Condenser B .

• May direct the BOP to isolate Isolation Condenser B .

Terminus: Isolation Condenser B is declared inoperable and the SRO has applied Tech Specs.

Notes/Comments


ILT13-1 NRCScenario1 (New)

Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 1 Event No.: 1 Event Description: Resoond to trio of VMCC 1 82 rTriaaer 31 Initiation: Isolation Condenser B is declared inoperable and the SRO has applied Tech Specs.or as directed by the Lead Examiner Cues: Annunciators G3c, RPS MG SET 2 TRIP; G1c, SCRAM CONTACTOR OPEN; 9XF4a, PROT SYS PNL 2 PWR LOST; 9XF5c, CIP-3 INV AC INP LOST Time Position Applicant's Actions or Behavior

BOP • Responds to annunciators • Recognizes and reports loss of VMCC 1 B2 • Performs ABN-51

ILT 13-1 NRC Scenario 1

o Confirms CIP-3 INV AC INP LOST (9XF-5-c) alarm received

o Verifies the Trans Output green Off light is lit on Panel 7R

o Restores power to PSP-2 by placing the Power Select switch in the TRANS position

o Resets the following: o Half Scram signal (4F) o Main Steam Isolation signal (4F) o APRM lights (5R) o APRM flow converters (3R, 5R) o Main Steam Line Rad Monitor drawers o Annunciators o NOTE: The following are simulated photographs. The

candidate can simulate and assume indications are as expected.

• Resets the INOP status LED on APRM FCTR cards

• Verifies status LED on FCTR card is GREEN • Verifies Curve Select Display is "0"

o Resets/verifies reset annunciator 9XF-4-a, PROT SYS PNL PWR LOST

o Informs the US the following valves inoperable (1 F/2F) lAW Tech Spec 3.7 and 3.5.A.3 (only if 'B' Battery is unavailable- it will begin discharging but will be available for several hours)

• V-14-31, DC Steam Inlet Valve to 'A' Condenser • V-14-34, DC Condensate Return Valve from 'A'

Condenser • V-16-2, Inlet Isolation Valve to Cleanup Auxiliary

Pump • V-16-14, Clean-Up Inlet Isolation Valve

o Informs the US the B Battery is INOPERABLE as soon as it beg_ins discharging

Page 10 of 27


0 Monitors 125 VDC B Bus Voltage 0 Reduces loads as directed by the US utilizing the B

Battery Load List 0 Monitors 125 VDC A Bus Voltage 0 Verifies the following alarms are received: 0 MCC-1AB2 PWR XFER (9XF-2-c) 0 VACP-1 PWR XFER (9XF-3-c) 0 IP-4 PWR XFER (9XF-7-c) 0 Confirms one Fire Diesel Pump is operating in

MANUAL mode and the other Fire Diesel Pump in AUTO mode

0 Directs the EO to investigate the loss of VMCC 1 B2 [ROLE PLAY]

ROLE PLAY: As the EO sent to investigate the trip of VMCC 1 B2, report the feeder breaker to VMCC 1 B2 tripped on overload

0 Informs US of Tech Specs section 3.7, Auxiliary Power 0 Notifies the Director of Operations and the WWM 0 Informs US to refer to EP-AA-1010 0 Reports ABN-51 is complete

SRO • Directs entry into ABN-51

• Notifies SM/WWM about the loss of VMCC 1 B2

• Declares VMCC 1 B2 inoperable

• Declares B Battery inoperable as soon as it begins to discharge

• Reviews/applies Tech Spec 3.7.B 0 The reactor shall be PLACED IN the COLD

SHUTDOWN CONDITION if the availability of power falls below that required by Specification A above

• Declares the following valves inoperable (1 F/2F) lAW Tech Spec 3.5.A.3 (only if 'B' Battery is fully discharged)

0 V-14-31, DC Steam Inlet Valve to 'A' Condenser 0 V-14-34, DC Condensate Return Valve from 'A'

Condenser 0 V-16-2, Inlet Isolation Valve to Cleanup Auxiliary Pump 0 V-16-14, Clean-Up Inlet Isolation Valve

ATC • Makes plant announcement of entry into ABN-51

• Reports Y2 scram on RPS 2

• Following restoration of RPS-2, resets the following: 0 Half Scram signal 0 Main Steam Isolation signal



Terminus: ABN-51 actions are complete and the SRO has reviewed/applied Tech Specs 3.7.8 and 3.5.A.3

Notes/Comments



Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 1 Event No.:§

Event Description: The in-service RBCCW QUmQ triQS [Trigger 5]

Initiation: ABN-51 actions are complete and the SRO has reviewed/applied Tech Specs 3.7.B and 3.5.A.3, or as directed by the Lead Examiner

Cues: Annunciators C3c, RBCCW PUMP 1-1 TRIP; E7d, E7f, F7b, CCW FLOW LO for all Recirculation Pumps; RBCCW PUMP 1-1 indicates tripped


BOP • Responds to annunciators C3c, RBCCW PUMP 1-1 TRIP; E7d, E7f, F7b, CCW FLOW LO for all Recirculation Pumps

• Checks RBCCW HX OUTLET PRESS and RBCCW PUMP 1-1 indications and recognizes RBCCW Pump 1-1 has tripped

• Enters and performs immediate actions of ABN-19 .

• Starts RBCCW Pump 1-2 by placing its control switch to START (must be started within 1 minute)

• Reports RBCCW Pump 1-1 tripped and RBCCW Pump 1-2 was started and indications are normal

• Directs EO to determine if RBCCW Pump 1-1 tripped on overload and to perform running checks on RBCCW Pump 1-2 [ROLE PLAY]

ROLE PLAY: When directed as the EO to check RBCCW Pump 1-1 for overload and to perform running checks on RBCCW Pump 1-2, report that RBCCW Pump 1-1 tripped on overload and report that running checks on RBCCW Pump 1-2 are SAT.


• May enter Primary Containment Control EOP on high DW Temp (if required)

• Notifies SM/WWM about the failed RBCCW Pump 1-1

ATC • Makes plant announcement about ABN-19 entry (may be performed by BOP)

Terminus: RBCCW Pump 1-2 has been manually started



Notes/Comments




Event Description: The standby (second) RBCCW Pump trips resulting in a loss of all RBCCW flow [Trigger 71

Initiation: RBCCW Pump 1-2 has been manually started, or as directed by the Lead Examiner

Cues: Annunciators C4c, RBCCW PUMP 1-2 TRIP; E7d, E7f, F7b, F7d, F7f, CCW FLOW LO for all Recirculation Pumps;


SRO • Recognizes a loss of all RBCCW flow has occurred and enters ABN-19

• Directs a manual scram lAW ABN-1

• Directs tripping all Recirculation Pumps

• Directs entry into RPV Control- No ATWS

o Directs the Crew to maintain RPV water level 138"- 175" (or 138"- 160") using SP2 (Cond/FW) and/or SP3 (CRD)

o If an RPV isolation did not occur, directs the Crew to maintain RPV pressure (approximately) 800- 1000 psig using the Turbine Bypass Valves

o If an RPV isolation occurred (due to reaching RPV Lo-Lo Level post scram), directs the Crew to maintain RPV pressure (approximately) 800- 1 000 psig using the Isolation Condensers (SP-11) and/or EMRVs (SP-12)

• Directs SP-1 (Confirmation of Automatic Initiations and Isolations)

ATC • Scrams the reactor lAW ABN-1 o Depresses both Manual Scram Pushbuttons

o Places the Reactor Mode Selector switch in SHUTDOWN

o Verifies all control rods fully inserted

o Reports immediate scram actions complete

• Trips all operating Recirculation Pumps lAW ABN-19

• Performs SP-11 (ICs) and/or SP-12 (EMRVs) to maintain RPV pressure as directed

o SP-11 (ICs)

o Trips Recirculation Pump A for use with IC-A (or



Recirculation Pump E for use with IC-B)

o Verifies RPV water level < 160" o Cycles Condensate Return Valve V-14-34 as

necessary to maintain RPV Pressure with IC-A (or V-14-35 for IC-B)

o SP-12 (EMRVs)

o Verifies Torus water level is> 90"

• Places one or more EMRV control switch in the MAN position, then back to AUTO

BOP • Controls RPV water level as directed following the scram

o Reports entry into RPV Control- No ATWS on low RPV water level

o When RPV level begins to rise following the scram, then performs the following:

o Places all MFRVs in MANUAL, if in AUTO

o Closes all MFRVs, if OPEN

o Directs the EO to close CRD Supply Water Valve to Charging Water Header valve V-15-52 [ROLE PLAY]

ROLE PLAY: As the EO directed to close CRD Supply Water Valve to Charging Water Header valve V-15-52, insert Trigger 9. Report when complete.

o Enters SP-2 (Cond/FW) when directed

o Controls RPV water level using the following as necessary:

o Feedwater Regulating valves

o Main Feed Regulating Valve (MFRV) Block valves

o Feedwater Low Flow valves o Heater Bank Outlet Isolation valves o Feedwater and Condensate pumps

• Performs SP-1 as directed

• Makes plant announcement for reactor scram due to loss of all RBCCW flow

Terminus: The reactor is scrammed, all Recirculation Pumps are tripped, and RPV water level and pressure are under control



Notes/Comments



Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 1 Event No.: Z Event Description: Large steam leak in the Drywell [Trigger 111 with eight control rods failing to insert

Initiation: The reactor is scrammed, all Recirculation Pumps are tripped, and RPV water level and pressure are under control, or as directed by the Lead Examiner

Cues: Drywell pressure and temperature rising; Annunciators C3f, OW PRESS HIILO; C1f, C2f, OW PRESS HI-HI

Time Position

Crew

(BOP

&

ATC)

CRITICAL TASK 2

Applicant's Actions or Behavior

• Reports OW pressure rising

• Responds to Annunciators C3f, OW PRESS HI/LO; C1f, C2f, OW PRESS HI-HI

• Reports EOP entry on high Drywell pressure and temperature

• Performs SP-1 (Verifications)

• Lines up Drywell Sprays lAW SP-29

o Confirms all Recirculation Pumps are tripped

o Trips all Drywell Recirculation Fans by placing their control switches to OFF

• Initiates Drywell Sprays lAW SP-29

o For OW Spray System 1 (2)

• Places the SYSTEM MODE SELECT switch to the OW SPRAY position

• Verifies TORUS CLG DISCHARGE valve closes

• Verifies OW SPRAY DISCHARGE valve opens

• Confirms the SYSTEM MODE SELECT switch is in the OW SPRAY position

• Verifies TORUS CLG DISCHARGE valve is closed

• Verifies OW SPRAY DISCHARGE valve is open

• Starts and ESW PUMP by placing its control switch in START

• Places and holds the SYSTEM 1 (2) PUMPS START PERMISSIVE keylock to the pump to be started

• Starts the CONTAINMENT SPRAY PUMP by placing its control switch to START

• Maintains OW Pressure between 4-12 psig


ILT13-1 NRCScenario1 (New)

• Maintains RPV water level in the desired band 138" - 175" lAW SP-2 (FW/Cond) and/or SP-3 (CRD)

• Maintains RPV Pressure in the band directed by the SRO

SRO • May reduce the RPV pressure band to approximately 500-700 psig due to the leak

• If RPV pressure falls< 500 psig, informs the crew the Yarways are no longer available for RPV level indication

• May secure Core Spray lAW SP-10

• Directs entry into Primary Containment Control EOP and re-entry into RPV Control- no ATWS (high OW Pressure)

• Directs entry into ABN-36 when the LOOP occurs

• Before bulk Drywell temperature reaches 281°F:

0 Verifies Drywell temperature/pressure within the CSIL Curve

0 Verifies Torus water level< 348"

0 Directs lineup of Drywell Sprays lAW SP-29

• When it is determined Drywell temperature cannot be

CRITICAL TASK 2 maintained below 281 °F, directs initiation of Drywell Sprays

OR

• When Dryweii/Torus pressure reaches 12 psig, directs initiation of Drywell Sprays lAW SP-29

• May Anticipate ED (using Turbine Bypass Valves and/or Isolation Condensers)

FLOOR: Raise the steam leak at the Lead Examiners Discresion

Terminus: Drywell Sprays have been initiated and Drywell pressure is lowering

Notes/Comments



Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 1 Event No.:~

Event Description: CAD Flow Control Valve fails closed [Trigger 13)

Initiation: When several control rods have been manually inserted post scram, or as directed by the Lead Examiner, insert Trigger 13

Cues: Annunciator H5c, CAD HIGH TEMP; DRIVE WATER FLOW, COOLING WATER FLOW, CLG WTR/REACTOR 1:\P, & DRIVE WTRIREACTOR 1:\P go downscale


Crew • Responds to annunciator H5c, CAD HIGH TEMP, and abnormal CAD indications.

• Reports abnormal CAD indications.

• Reports the CAD FCV (NC30A) indicates closed.

• May direct the EO to investigate the failed CAD FCV [ROLE PLAY 1].

• Enters ABN-6, Control Rod Malfunctions, section 13, Flow Control Valve NC-30A/B Fails Closed.

• Places CAD FCV NC30B in service lAW procedure 302.1, section 6.3.3.

o Places the CAD FLOW CONTROLLER in MAN.

o Directs the EO to open the standby FCV inlet/outlet valves [ROLE PLAY 2].

o Directs the EO to place the 4-Way Valve in position to supply both controllers [ROLE PLAY 3].

o Places the CAD FLOW CONTROL VALVES switch to the B position.

o Directs the EO to place the 4-Way Valve in position to supply the in-service controller [ROLE PLAY 4].

o Verifies normal CAD indications. o Places the CAD FLOW CONTROLLER in AUTO.

o Directs the EO to close the failed FCV inlet/outlet valves [ROLE PLAY 5].

• Reports the standby CAD FCV is in service and indications are normal.

• May continue in EMG-SP21 and attempt to reset the scram and re-scram. This is unsuccessful.

• May continue in EMG-SP21 and attempt to scram each rod by ,__C_R_I_T-IC_A_L~.....-T_A_S_K_1__, their individual scram test switches. This is a success path.

• Manually drives all rods that failed to scram to less than



position 04

Crew • Announces entry into ABN-6, Control Rod Malfunctions, due to CRD FCV NC30A failing closed.

• May check CRD Temperatures on Panel 8R and report there are several control rods with high temperatures.

SRO • Directs entry into ABN-6, Control Rod Malfunctions, due to CRD FCV NC30A failing closed.

• May directs swapping CRD FCVs lAW procedure 302.1, section 6.3.3.

• Notifies the SMIWWM about the failed CRD FCV .

CRITICAL TASK 1 • Directs inserting all rods that failed to scram to less than position 04

ROLE 1. When/if asked as the EO to investigate the in-service CRD FCV (NC30A),

PLAY report that it is closed, was leaking air badly, and that you have isolated the air supply to the valve.

2. (Step 6.3.3.1.1.2.b) When/if asked as the EO to open the standby CRD FCV inlet/outlet valves, insert Trigger 15 and report the valves OPEN (V-15-18, V-15-19).

3. (Step 6.3.3.1.1.3) When/if asked as the EO to place the 4-Way Valve in position to supply both controllers, state it is in the position to supply both controller (NO booth actions are required).

4. (Step 6.3.3.1.1.5) When/if asked as the EO to place the 4-Way Valve in position to supply the in-service controller state it is in the position to supply NC30B (NO booth actions are required).

5. (Step 6.3.3.1.1.8.a) When/if asked as the EO to close the failed FCV inlet/outlet valves, state the valves are closed insert Trigger 17 (closes V-15-16, V-15-17).

ROLE The ONLY success paths lAW SP-21 {Hydraulic ATWS) are to manually PLAY drive all rods in after the Crew swaps CRD Flow Control Valves or

scram each rod with their individual scram test switches on Panel 6R.

NOTE If the Crew requests an EO to Vent the CRD Over-Piston volume inform them V-15-24 and V-15-25 are mechanically seized and cannot be operated.

Terminus: CRD FCV NC30B is in service and CRD parameters indicate normal and the Crew insert all control rods to less than position 04.



Procedures Used

Event Procedure

1 • 302.2

• Control Rod pull sheets

2 • ABN-6

3 • RAP-6C8

• 307, section 7 and Attachment 307-15

• TS3.8

4 • ABN-51

• RAP-G3c

• RAP-G3c

• RAP-G1c

• RAP-C9XF4a

• RAP-9XF5c

• TS 3.7

5 • ABN-19

• RAP-C3c

6 • ABN-19

• ABN-1

• RPV Control-no ATWS

• SP-1

• SP-2

• SP-3

• SP-11

• SP-12

7 • RPV Control-no ATWS

• Primary Containment Control



• SP-29

• ABN-36

8 • RAP-H5c

• ABN-6

• 302.1



Simulator Setup

1. Reset to IC-151. Password: 2014iltnrc 2. Verify B & C MFRVs are in MAN and closed 3. Have a copy of 302.2, 201, & 402.2 for the applicants 4. Place Air Compressor #3 in PTL and hang tag 5. Have a copy of Scenario 1 pull-sheets (Sequence Step Numbers 9-11

completed through step 10 and rod 34-15 of step 1 0) in yellow. Place in binder in simulator in front of Step 8 (or hand to students as part of their prescenario brief).

6. Verify the RWM is in BYPASS and tagged OOS 7. Verify Nls are on IRMs

Event Trigger Malfunction

1 NA NA

2 Preset~ MAL-CRD007 _26-23

• This will stick Control Rod 26-23 .

• NOTE: DELETE this malfunction when the Applicant raises CRD drive pressure the 1st time to rod 26-23 lAW ABN-6. (See Booth actions for Event 2).

3 T1 ~ • IMF-ANN-C-68

• ICH-ICS003A from 7.2' to 4.8' over a 4-minute ramp

This will cause IC B shell water level indication to lower to 4.8' over a 2-minute period. Note that this malfunction set to lower to 4.8' will give an indication on Panel 1 F/2F of 4.8'.

4 T3~ MAL-EDS004B

• Loss of VMCC 1 82

5 T5~ MAL-RBC001A



• Trips RBCCW Pump 1-1

6 T7 ---+ MAL-RBC001 8

• Trips RBCCW Pump 1-2

T9 ---+ LOA-CRD024 to 0

• This closes CAD Supply Water Valve to Charging Water Header valve V -15-52

7 Preset---+ MAL-CRD022_0223, 0231, 2251, 3051, 5031,5023,3003,2203

• This will result in eight control rods failing to scram

Preset---+ hwx03i271 s.eq.1

• This will activate Trigger 11 when the Mode Switch is taken to SHUTDOWN

Conditional MAL-NSS0178 to 10% over 20 minutes with a 2-minute time delay

T11 ---+

• This will cause a steam leak in the Drywell

8 T13 ---+ MAL-CRD001A to 0

• This closes CRD FCV NC30A

T13 ---+ MAL-ANN-H-5C to ON on a 30 sec time delay

T15- LOA-CRD012 to 1

LOA-CRD011 to 1

• This opens the alternate FCV NC308



inlet/outlet valves.

T17~ LOA-CRD009 to 0

LOA-CRD01 0 to 0

• This closes the failed FCV NC30A inlet/outlet valves



Shift Turnover

Current plant conditions:

• 2% power with mode switch in STARTUP • Control rod withdrawal is in progress • Air Compressor #3 is tagged OOS • RWM is tagged OOS

• lnerting the Primary Containment is on hold for a nitrogen delivery. The reactor Mode switch is in STARTUP.

• Steam chest warming is in progress

Shift Activities

• Continue with rod withdrawal. Complete step 10 Group 3-1 starting at rod 26-23. When rod pulls are complete wait for further direction from Reactor Engineering. Timing of rod position 00-02 is not required and Continuous Rod Withdrawal is allowed per Reactor Engineering.

• Procedure 201, Plant Startup is currently at Step 6.57 to withdraw control rods to achieve 1-2 Turbine Bypass valves open



Scenario Outline

Facility: Oyster Creek Scenario No.: g Op Test No.: 13-1 NRC


Initial Conditions: • 97% power • Main Generator voltage control is in Manual Turnover: • Place the AVR in automatic service lAW 336.1, section 8, starting at Step 8.2 • Raise reactor power to 100% with recirculation flow

Event No. Malf. No. Event Type* Event Description

1 N/A N BOP Return the AVR to service lAW 336.1.

2 N/A R ATC Raise reactor power to 1 00% with recirculation flow.

3 MAL- c BOP Trip of Steam Packing Exhauster 1. MSSOOSA

MAL-NIS020F I ATC APRM 6 fails upscale with a failure of V2 scram on 4 RLY-

RPS0038, TS SRO RPS2. 0048

5 MAL- c BOP Trip of USS 1 A3. EDS003C TS SRO ICH-

6 TSI15A, c ATC Turbine high vibration requiring a manual scram. TSI014A

MAL-CFW012B

Feedwater line break with failure of Feedwater check SRV-7 CFW002B M Crew valves and loss of all Feedwater and Condensate

SRV- Pumps. CFW003B

VLV-

8 CSS004, c Crew Failure of Core Spray Isolation Valves to auto open. 006, 011'

012

* (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs


IL T 13-1 NRC Scenario 2 (New)

Simulator Summary

Event Event Summary

1 The BOP will return the AVR to automatic service lAW 336.1. The BOP will place the AVR MODE Switch to the AUTO position and confirm indications voltage regulation is in automatic. (BOP: Normal Evolution)

2 The ATC will raise reactor power to rated power (100%) with recirculation flow using the Master Recirc Speed Controller. (ATC: Reactivity Manipulation)

3 The BOP will respond to the failure of the in-service steam packing exhauster. The BOP will start the standby Exhauster and throttle open its discharge valve to maintain the correct vacuum. (BOP: Component Malfunction)

4 APRM 6 will fail high with no expected% scram on RPS 2. The SRO will direct entry into ABN-39, RPS Failures. The ATC will insert a manual% scram on RPS 2. The SRO will apply Tech Spec 3.1.1. (ATC: Instrument Malfunction; SRO: Tech Spec)

5 The BOP will respond to a loss of USS 1 A3 and execute ABN-46, Loss of USS 1 A3. The BOP will start Service Water Pump 1-2, restore power to ER-42, and confirm HP Screen Wash Pump 1-2 and LP Screen Wash Pump 1-4 are running. The SRO will review and apply Tech Spec 3.7. (BOP: Component Malfunction; SRO: Tech Specs)

6 The crew will respond to turbine VIBRATION HI annunciator and recognize rising bearing vibrations to the level that requires a power reduction and manual scram. The ATC will manually scram the reactor and BOP will confirm trip of the turbine. ABN-1, Reactor Scram, and ABN-10, Turbine Trip, procedures will be entered. The crew will be required to open the Main Condenser Vacuum Breaker to mitigate the turbine high vibration.(ATC: Component Malfunction)

5 The crew will respond to a large Feedwater line break compounded with the failure of the Feedwater isolation check valves. The crew will enter the RPV Control- no ATWS EOP. During the event, all condensate and feedwater pumps will trip. The crew will Emergency Depressurize (ED) if RPV water level reaches 0'' OR lower RPV pressure to allow low pressure systems to inject. (Crew: Major Evolution) (PRA)


6


The crew will respond to the failure of the Core Spray Parallel Isolation valves to automatically open. The valves will open manually from their control switches on panel 1 F/2F. (Crew: Component Malfunction After EOP) (PRA)

Critical Task 1

The crew must manually scram the reactor on Turbine High Vibration. An automatic scram may not occur and turbine damage may result in entry into Emergency Action Levels for a loss of the primary decay heat removal mechanism.

Critical Task 2

The SRO will direct Emergency Depressurization when RPV water level reaches 0" T AF provided at least one injection source is lined up and running OR with low pressure injection systems running that have the capacity to restore and maintain RPV water level the SRO will direct lowering RPV pressure as necessary to allow low pressure systems to inject.

Critical Task 3

The crew recognizes that the Core Spray Parallel Isolation Valves failed to automatically open at- 300# reactor pressure and manually opens at least one valve in each Core Spray system to allow Core Spray to inject into the RPV to restore RPV water level above TAF.

ES-301-4 Target Quantitative Actual Event Attributes Attributes Number{s}

1. Total malfunctions (5-8) 6 3-8

2. Malfunctions after EOP entry (1-2) 1 8

3. Abnormal events (2-4) 3 4-6

4. Major transients (1-2) 1 7

5. EOPs entered/requiring substantive 2 7 actions (1-2)


7. Critical tasks (2-3) 3 6-8



Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 2 Event No.: 1 Event Description: Return the AVA to service lAW 336.1.


Cues: As directed by the SAO following shift turnover


SAO • Directs the BOP to shift from manual to automatic voltage regulation lAW 336.1, section 8, starting at Step 8.2

BOP • Shifts from manual to automatic voltage regulation lAW 336.1, section 8, step 8.2.

0 Verifies the EX2100e TRANSFER VOLTMETER (8F/9F) is reading Zero (± 1 %)

0 Places the AVA MODE Switch (AVR\97CS Panei8F/9F) to the AUTO position and allow switch to return to center. (Panel 8F/9F)

0 Confirms the AUTO light illuminated above AVA MODE Switch. (AVR\97CS Panel 8F/9F)

0 Confirms the PSS Status is Enabled locally at the HMI

ROLE PLAY: As the EO at the HMI, report that the PSS is active (336.1 step 8.5)

0 Removes VOLTAGE CONTROL IN MANUAL operator aids installed per Section 7.0.

0 May verify Terminal Voltage or Excitation are within the requirements of 336.1, section 5.0, on the PJM website. [FLOOR ROLE PLAY]

FLOOR ROLE PLAY: If the applicant requests (or attempts to verify on the PJM website) that Terminal Voltage or MG Excitation (VARS) are within the limits of section 5.0, inform them that the requirements of section 5.0 are satisfactory.

0 May notify the Power team when in auto

Terminus: The AVA is in automatic voltage control



Notes/Comments



Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 2 Event No.: g Event Description: Raise reactor gower to rated lAW the ReMA

Initiation: After the AVR is placed in automatic voltage control, or as directed by the Lead Examiner

Cues: As directed by the SRO


SRO • Approves the ReMA and provides to the ATC

• Directs the ATC to raise power to rated lAW the ReMA

• Acts as the reactivity Manager

• Provides a reactivity brief (may have been completed prior during scenario pre-brief)

• May notify the Power team when at rated power

ROLE PLAY: If Reactor Engineering is contacted inferring about the rate of power ascension, inform them there is no limit on the rate of power ascension.

ATC • Raises power lAW the ReMA

0 May review 202.1, section 5.0, Raising Power

0 Rotates the MASTER RECIRC SPEED CONTROLLER manual knob CW

0 Monitors power, level, pressure

0 Reports to SRO when rated power is reached

BOP • Provides second check for the reactivity manipulation

Terminus: Reactor power is at rated or at the discretion of the Lead Examiner



Notes/Comments



Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 2 Event No.:~

Event Description: TriQ of Steam Packing Exhauster 1 [Trigger 1]

Initiation: Reactor power is at rated, or as directed by the Lead Examiner

Cues: Annunciator Q8c, EXHAUSTER TRIP


BOP • Responds to annunciator Q8c, EXHAUSTER TRIP

0 Reports Exhauster Blower 1 has tripped

0 Verifies gland steam pressure

0 Closes Exhauster Blower 1 Valve V-7-38

0 Starts Exhauster Blower 2 and verifies the red light on

0 Throttles open Exhauster Valve 2 V-7-39

0 Adjusts Exhauster Valve 2 V-7-39 to maintain GLAND STM HEADER VACUUM at 15 - 17.5 inches of water

0 Reports Exhauster Blower 2 is in service

• Directs EO to investigate the trip of Exhauster Blower 1 [Role Play]

As the EO sent to investigate the trip of Exhauster Blower 1 , report there

ROLE PLAY are indications of an overload on the breaker.

May send an EO to the Turbine Building operating floor to investigate; report as the EO you are on the TB operating floor.

SRO • Notifies SM/WWM for repair

• May direct condenser vacuum as key parameter

• May evacuate the TB operating floor

Terminus: Exhauster Blower 2 has been started and proper gland steam header vacuum is established



Notes/Comments



Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 2 Event No.: 1 Event Description: APRM 6 UQscale Failure with no RPS 2% Scram [Trigger 3]

Initiation: Exhauster Blower 2 has been started and proper gland steam header vacuum is established, or as directed by the Lead Examiner

Cues: Annunciators G2f, APRM HIHIIINOP II; G3f, APRM HI; APRM 6 indicates 150 with the HI-HI and HI lights on


ATC • Responds to annunciators G2f, APRM HIHIIINOP II and G3f, APRM HI

0 Reports APRM 6 indicates 150 and that an RPS 2 % scram should have occurred

0 Checks the following:

0 recirculation flow

0 feedwater flow and temperature

0 reactor pressure

0 reactor water level

• Performs ABN-39

0 Inserts a% scram on RPS 2 by pressing the MANUAL SCRAM RPS 2 push button

0 Refers SRO to Tech Spec 3.1

• May Bypass APRM 6 lAW 403 if directed

SRO • Directs entry into ABN-39, RPS Failures and directs the ATC to insert a % scram on RPS 2 (may direct inserting a % scram prior to referencing ABN-39)

• Reviews Tech Spec 3.1 and verifies RPS 2 and APRM 6 are in the tripped condition and meeting their design function

• Notifies SM/WWM for the APRM and RPS failures

• Notifies the Director of Operations I SM I RE

• Determines no other action is currently required

• May direct bypassing APRM 6

BOP • Makes plant page for entry into ABN-39, RPS Failures



• May verify APRM 6 indication on Panel 5R

Terminus: RPS 2 is tripped and the SRO has reviewed/applied the Tech Specs

Notes/Comments




Event Description: Loss of 480 VAC Bus USS 1A3 [Trigger 5].

Initiation: RPS 2 is tripped and the SAO has reviewed/applied the Tech Specs, or as directed by the Lead Examiner.

Cues: Annunciators S8f, FOR TO 460V 1A3 TRIP, and U5a, 1A3 MN BRKR TRIP


BOP Per RAPs S-8-f, FOR TO 460V 1A3 TRIP, and U-5-a, 1A3 MN BRKR TRIP (NOTE: Applicant may directly enter and execute ABN-46 instead of RAP).

• Checks Breaker position and Bus amps

• Has EO check at the local breaker cubicle for relay targets

• Verifies trip of 4160V Breaker 1 A3P

• Refers to ABN-46

• Checks Bus loads have shed

• Determines cause of Breaker trip [BOOTH]

BOOTH: When requested to investigate cause of USS 1A3 trip, report that the 1A3P breaker tripped on overload

Per ABN-46, LOSS OF USS 1 A3:

IMMEDIATE OPERATOR ACTIONS

• Starts 1-2 Service Water pump

SUBSEQUENT OPERATOR ACTIONS

• Has an EO restore power to Panel ER-42 [BOOTH]

BOOTH: When requested, insert LOA-CWS0049 to B31 (Trigger 7) to restore power to B31. Report to Control Room when complete. (ABN-46 step 4.2.1)



• Has an EO confirm HP Screen Wash Pump 1-2 and LP Screen Wash Pump 1-4 are running [BOOTH]

BOOTH: NOTE: Screen Wash Control Panel and Low Pressure Screen Wash (2Um(2s are not modeled. When requested to confirm HP Screen Wash Pump 1-2 and LP Screen Wash Pump 1-4 are running, report they are both running. May request EO to check intake dp.

• Monitors North intake DP, Circ Water pump amps and main condenser vacuum

• Notifies Security of the loss of security lighting at the intake

• Requests Work Week Manager to mobilize Electrical Maintenance for troubleshooting and repair

ATC • May assist in communications associated with execution of RAPs and ABN-46

SRO • Directs entry into ABN-46, Loss of USS 1 A3

• Determines that USS 1A3 is inoperable per Tech Spec 3.7 and determines that the plant must be placed in the cold shutdown condition

Terminus: ABN-46 has been performed and the SRO has addressed Tech Specs.

Notes/Comments




Event Description: Turbine VIBRATION HI annunciator reguiring a manual scram [Trigger 9] {See Lead Evaluator Cue below}

Initiation: ABN-46 has been performed and the SAO has addressed Tech Specs., or as directed by the Lead Examiner

Cues: Annunciator Q3b, VIBRATION HI; Turbine bearings 6 and 7 vibrations rising


BOP • Responds to annunciator Q3b, VIBRATION HI

0 Reports turbine bearing vibration levels

0 Reports Bearing 6 at 10 mils and rising and bearing 7 at 10 mils and rising. Reports that the RAP requires a manual turbine trip at any level > 12 mils

LEAD EVALUATOR: IF the simulator fails to provide indications of Turbine mils rising, THEN inform the crew that Bearing 6 & 7 are at 11 mils and rising. One minute later report that BearinQ 6 & 7 are at 13 mils and steady.

• Controls RPV water level as directed following the scram

0 Reports entry into RPV Control- No ATWS on low RPV water level

0 When RPV level begins to rise following the scram, then performs the following:

0 Trips 2 Feed Pumps with their control switches

0 Places all MFRVs in MANUAL

0 Closes all MFRVs

0 Directs the EO to close CAD Supply Water Valve to Charging Water Header valve V-15-52 [ROLE PLAY]

ROLE PLAY: As the EO directed to close CAD Supply Water Valve to Charging Water Header valve V-15-52, insert Trigger 30. Report when complete.

0 Enters SP-2 (Cond/FW) when directed

0 Controls RPV water level using the following as necessary:

0 Feedwater Regulating valves

0 Main Feed Regulating Valve (MFRV) Block valves

0 Feedwater Low Flow valves


SRO

CRITICAL TASK 1


o Heater Bank Outlet Isolation valves

o Feedwater and Condensate pumps

• Performs SP-1 as directed

• Makes plant announcement for reactor scram

• Directs the ATC to reduce reactor power with Recirc Flow

• Directs the ATC to manually scram the reactor lAW ABN-1

• Directs entry into RPV Control- No ATWS

o Directs the Crew to maintain RPV water level 138"- 160" using SP2 (Cond/FW) and/or SP3 (CRD)

o Directs the Crew to maintain RPV pressure (approximately) 800 - 1000 psig using the Isolation Condensers (SP-11) and/or EMRVs (SP-12)

o May direct pressure control on TBV before Vacuum Breaker is opened lAW ABN-10 and if an RPV isolation has not occurred

• Directs entry into ABN-10, Turbine Trip

o Directs main condenser Vacuum Breaker, V-2-44 opened

NOTE: When V-2-44 is opened, The Main Turbine vibration (high mils) malfunction will automatically be deleted (return to normal) AND Event #7 will initiate.

ATC

CRITICAL TASK 1

• Directs SP-1 (Confirmation of Automatic Initiations and Isolations)

• Reduces power with Recirc Flow prior to reaching 12 mils on bearing 6 or 7

• Scrams the reactor lAW ABN-1 o Depresses both Manual Scram Pushbuttons o Places the Reactor Mode Selector switch in SHUTDOWN o Verifies all control rods fully inserted

o Reports immediate scram actions complete

• Performs ABN-1 0, Turbine Trip

o Verifies turbine valves closed

o Verifies 230 KV breakers open

o Verifies GENERATOR FIELD BREAKER open

o Verifies plant loads supplied by Startup Transformers

o Confirms CLOSED HWC H2 Inlet Isolation Valve, V-567-005



0 Requests SRO confirmation to open main condenser Vacuum Breaker, V-2-44

0 Opens main condenser Vacuum Breaker, V-2-44 with its control switch

0 Starts the Auxiliary Oil Pumps

0 Starts the Turbine Bearing Oil Lift Pump


0 SP-11 (ICs)

0 Trips Recirculation Pump A for use with IC-A (or Recirculation Pump E for use with IC-B)

0 Verifies RPV water level< 160"

0 Cycles Condensate Return Valve V-14-34 as necessary to maintain RPV Pressure with IC-A (or V-14-35 for IC-B)

0 SP-12 (EMRVs)

0 Verifies Torus water level is> 90"

0 Places one or more EMRV control switch in the MAN position, then back to AUTO

Terminus: The reactor is scrammed, the main condenser vacuum breaker is open, and RPV water level and pressure are under control

Notes/Comments



Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 2 Event No.: 7/8

Event Description: Feedwater line break in the Turbine Building with the failure of Feedwater Check Valves and the loss of all Condensate/Feedwater Pumgs [Automatically initiates when V-2·44 is opened in Event #6]. Core Spray Parallel Isolation Valves fail to automatically open.

Initiation: The reactor is scrammed, the main condenser vacuum breaker is open, and RPV water level and pressure are under control, or as directed by the Lead Examiner

Cues: Feedwater Flow rises greater than Steam Flow; Annunciators P2f, CONDENSER BAY 1-2 LEVEL HI; J8c, FCS/RFRC TROUBLE; P3f, PUMP ROOM 1-3 LEVEL HI; Feedwater flow rising; Annunciator J8a, TRUNNION ROOM TEMP HI; Turbine Building ~P goes positive; Annunciatots K1 b, K2b, K3b, PUMP A, B, C TRIP


Crew • Responds to Annunciators P2f, CONDENSER BAY 1-2 LEVEL HI

0 Directs an EO to perform the following:

• Verify level locally

• Verify pumps are in AUTO

• VERIFY pump discharge valves are open [ROLE PLAY]

ROLE PLAY: As the EO directed to investigate the Condenser Bay hi level, report the following: all pumps are in AUTO and operating, pump discharge valves are open, and level is 36" water column and rising. Also report there is water raining down from the ceiling in the Feed Pump Room (this is also stated on Page 15 but should be promptly reported to the Control Room).

• Responds to annunciator J8c, FCS/RFRC TROUBLE

0 Checks for feedpump runout condition and feed/steam flow

0 Reports feedwater flow is rising and A/C MFRVs are opening further

• Responds to annunciator J8a, TRUNNION ROOM TEMP HI

0 Reads individual readouts of tunnel temperature on Panel 1 OR and reports

0 Monitors Trunnion Room temperatures

ROLE PLAY: When directed as the EO to perform in-plant SP-3 actions, insert Trigger 13. Report when complete.



• Responds to annunciators K1 b, K2b, K3b, PUMP A, B, C TRIP

o Reports all Condensate and Feedwater Pumps tripped

o Dispatches EO to investigate [ROLE PLAY]

ROLE PLAY: When directed as the EO investigate the loss of Condensate/Feeedwater Pumps, report that water is raining down from the ceiling in the Feedwater Pump Room.

CRITICAL TASK 3

• Reports RPV water level lowering

• Reports RPV water level low-low (90")

• Performs SP-1

• Bypasses ADS by placing ADS TIMER keylock switches to BYPASS

• Performs SP-7 o Starts a SLC Pump by placing key into the STANDBY

LIQUID CONTROL keylock and rotating to FIRE SYS 1 or FIRE SYS 2

o Verifies proper indications

o Reports SLC injecting lAW SP-7

• Bypasses ADS Timers

• Initiates Isolation Condensers for Level Restoration (cycles IC DC Condensate Return Valves open then closes them)

• Performs SP-9 (Core Spray) o Verifies Core Spray suction valves open o Confirms closed Core Spray Test Flow Return valves

o Confirms one Core Spray Main pump operating in each Core Spray System

o Confirms one Core Spray Booster pump operating in each Core Spray System

o Confirms open Core Spray Discharge valves

o When RPV pressure is< 305 psig, recognizes/reports Core Spray Parallel Isolation Valves did not open as expected

o Manually opens all Core Spray Parallel Isolation Valves by placing their control switches to OPEN (Critical Task)

• Reports Core Spray injecting



• Reports RPV water level rising

• Lowers RPV pressure by opening some EMRVs by placing CRITICAL TASK 2 AUTO DEPRESS VALVE switches to MAN (or all available

EMRVS to ED) or with Isolation Condensers

• Bypasses ROPS by placing ROPS in BYPASS, if directed

• Performs SP-4

0 Presses the OVERRIDE switches that are lit

0 Presses all ACTUATED switches

0 Cycles the Parallel Isolation valves as required to maintain RPV water level

• Reports Torus Water temperature> 95 °F- EOP entry (due to using EMRVs for pressure control)

• Performs SP-25 (Torus Cooling)

0 Confirms the SYSTEM MODE SELECT switch in TORUS COOLING position

0 Starts the selected ESW Pump by placing its control switch to START

0 Places and holds the SYSTEM PUMPS START PERMISSIVE keylock switch in the selected pump position

0 Starts the selected Containment Spray Pump by placing its control switch to START

0 Reports Torus Cooling is in service

SRO • Directs RPV pressure control lAW SP-11 (Isolation Condensers) and/or SP-12 (EMRVs)

• May direct a reactor power reduction with recirculation flow or control rods when the rising feedwater flow is reported

• If required, may direct the following:

0 When Trunnion Room temperature is anticipated to exceed 176° F, directs the ATC to manually scram the reactor lAW ABN-1 OR enters RPV Control EOP based on conserving RPV inventory

0 Directs SP-2 (Feedwater) and SP-3 (CRD) to maintain RPV water level 138" - 160"

0 Directs SP-1 (Auto Initiation Verification)

0 Directs SP-7 (SLC)

0 With RPV water level below 61 ":

• Directs ADS bypassed

• Directs Isolation Condensers initiated, then



removed

• Directs lining up Core Spray lAW SP-9 (Core Spray)

• Directs lowering RPV pressure as required to allow low pressure systems to inject (Critical Task)

• If RPV water level reaches 0", directs entry into CRITICAL TASK 2 Emergency Depressurization- No ATWS

(Critical Task) 1. Directs ROPS bypassed

2. Verifies Torus water level> 90"

3. Directs all EMRVs open CRITICAL TASK 3 0 Directs RPV water level 1 00"- 175" with Core Spray

lAW SP-4 (Critical Task)

• If Torus Temperature exceeds 95F, may enter and direct Primary Containment Control EOP on high Torus water temperature

0 Directs Torus Cooling initiated lAW SP-25

Terminus: RPV pressure has lowered to allow Core Spray injecting into the RPV and RPV water level is rising.

Notes/Comments



Procedures Used

Event Procedure

1 • Copy of 336. 1 handed out

2 • Copy of REMA handed out

3 • RAP-Q8c

4 • ABN-29

• RAP-G2f

• RAP-G3f

• TS 3.1

• 403

• 403-2 in 403 book

5 • ABN-46

• RAP-S8f

• RAP-U5a

6 • RAP-Q3b

• ABN-10

• ABN-1

• RPV Control- No ATWS EOP

• SP-2

• SP-3

• SP-11

• SP-12

7 • RAP-J3e

• 317

• 317.1

• 317.4

• 317.5



• ABN-17

• 202.1

8 • RAP K1b

• RAP-K1c

• RAP-K1d

• RAP P2f

• RAP-P3f

• RAP-J8a

• RAP-J8c


• Primary Containment Control EOP

• ED- No ATWS EOP

• Secondary Containment Control EOP

• SP25

• SP2

• SP3

• SP4

• SP7

• SP9



Simulator Setup

1. ResettoiC-115 2. Lower reactor power to 97% with recirc flow 3. Place the AVR in manual voltage control lAW 336.1, section 7 4. Have copy of 336.1 (complete procedure) for applicants; mark step 8.1.1

and 8.1.2 complete 5. Have a copy of REMA NRC Sim2 for students 6. Have a copy of 202.1 section 5 marked up to raise power 7. Have a copy of 301.2 available 8. Have a blank copy of 302.1 available to reference 9. Have a blank copy of Attachment 403-2 in the 403 binder 10. Ensure Service Water Pump 1-1 is running and Service Water Pump 1-2

is secured

NOTE: If snapping this scenario to 0 (zero), when resetting, the AVR may return to AUTO on reset. The AVR must then be returned to manual.


1 N/A N/A

2 N/A N/A

3 Trigger 1 --4 MAL-MSS005A

• Trips Steam Packing Blower 1

4 Trigger 3--4 MAL-NIS020F to 150

• This causes APRM 6 to fail upscale

Presets RL Y-RPS003B

RL Y-RPS004B

• This causes a failure of RPS 2 to% scram from the upscale APRM 6

5 Trigger 5--4 MAL-EDS003C

• This will insert a loss of USS 1A3

Trigger 7--4 LOA-CWS049 to 831



• This will restore power to ER-42

6 Trigger 9-+ ICH-TSI015A starting at 1 0 going to 13 over a 6 minute ramp

ICH-TSI014A starting at 10 going to 13 over an 6 minute ramp

• This creates a high vibration to turbine bearing 7 (10 mils) and bearing 6 (10 mils)

Trigger 30 -+ LOA-CRD024 to 0

• This closes CRD Supply Water Valve to Charging Water Header valve V-15-52

NOTE: The following Presets will delete the high Turbine Vibration when the crew opens V-2-44, Main Condenser Vacuum Breaker AND initiate Event #7

PRESET-+ Insert the following Event Trigger (1) and Command (2) on Trigger 15:

1) hwx05o094r

2) DMF ICH-TSI015A

PRESET-+ Insert the following Event Trigger (1) and Command (2) on Trigger 17:

1) hwx05o094r

2) DMF ICH-TSI014A

7 Trigger 15 -+ SRV-CFW002B to 100%

(auto initiates SRV-CFW003B to 100% from preset from MAL-CFW012B to 10% over 20 minutes

Event #6) • This fails feedwater check valves to

leak and inserts a feedwater line break in the Turbine Building (RPV coolant will flow back through the



check valves into the TB)

ANN-J-8A to OFF

• Disables the Trunnion Room high temperature alarm

PRESET~

MAL-CFW003A with a 3 minute time delay

MAL-CFW003A with a 5 minute 0 second time delay

Trigger 15 ~ MAL-CFW003B with a 5 minute 15 second time delay

MAL-CFW003C with a 5 minute 30 second time delay

• This results in the trip of each Condensate Pump at 300 seconds, 315 seconds, and 330 seconds after the Main Condenser Vacuum Breaker is OPEN

LOA-CRD024 to 0 (also in Event #6)

• This will close the CRD charging header isolation valve V -15-52

Trigger 30 ~ LOA-CRD052 to 1

• This will open CRD valve V-15-237

LOA-CRD051 to 1

Trigger 13 ~ • This will open CRD valve V-15-30

8 Preset~ VLV-CSS011 to FAIL AUTO OPEN (for V-20-40)

VLV-CSS004 to FAIL AUTO OPEN (for V-20-15)



• This prevents the auto opening of all Core Spray Parallel Isolation valves, but does allow manual manipulation



Shift Turnover


• 97% power

• Main Generator voltage control is in Manual

Shift Activities:

• Place the AVR in automatic service lAW 336.1, section 8, starting on step 8.2

• Raise reactor power to 1 00% with recirculation flow


IL T 13-1 NRC Scenario 3 (Modified)

Scenario Outline

Facility: Ovster Creek Scenario No.: .2 Op Test No.: 13·1 NRC


Initial Conditions:

• 95% power

• EDG-2 is 008 for maintenance • Surveillance 636.4.003, Diesel Generator Load Test, is in progress on EDG-1

• An operator is stationed at EDG-1 for the surveillance

• All EDG-1 diesel alarms are in their normal state

Turnover: • Complete surveillance 636.4.003, Diesel Generator Load Test, starting at step 6.7, due to a

question of operability (oil sight glass was low on the last shift)

Event No. Malf. No. Event Type* Event Description

1 MAL- c BOP Trip of EDG-1 during performance of surveillance DGN004A TS SRO 636.4.003.

MAL- I ATC 2 NIS019_0

TS BOP LPRM 28-25A upscale failure (input to APRM 4). 18A SRO

MAL- c ATC 3 CRD005 - TS BOP Outward drifting control rod (rod 18-11 ).

18-11 SRO

4 MAL- R ATC Fuel failure requiring power reduction with recirc

RXS001 flow

5 MAL- M Crew Fuel failure will increase requiring a reactor scram

RXS001 and reactor isolation MAL- Isolation Condenser B tube leak with steam valves ICS002B M

6 VLV- c Crew failing to close leads to RPV Emergency ICS007, Depressurization

008

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs



Simulator Summary

Event

1

2

3

4

5

Event Summary

The BOP will continue with 636.4.003, Diesel Generator #1 Load Test at step 6.7. One minute after the diesel starts it will trip and the BOP will momentarily place the EDG-1 NORMAL START switch in the STOP position. Investigation will reveal EDG-1 tripped on an overspeed condition. The SAO will determines a COLD SHUTDOWN CONDITION LCO applies lAW TS 3.7.C.3 due to neither diesel being available. (BOP: Component Malfunction; SRO: Tech Specs)

The BOP will respond to an LPRM upscale failure, affecting APRM 4. The ATC will bypass APRM 4 and reset the % scram and the BOP will bypass the LPRM from the APRM and the alarm circuit lAW procedure 403. Following successful LPRM bypass, the ATC will unbypass APRM 4. The SAO will verify APRM 4 operability with Tech Spec 3.1. (ATC: Instrument Malfunction; BOP: Instrument Malfunction; SRO: Tech Specs)

The ATC will respond to an outward drifting control rod (rod 18-11 ). The ATC will enter ABN-6 and attempt to drive the rod to its original position. The rod will continue to move out at which time the ATC will drive the rod to position 00. The BOP will manually scram the rod from panel 6XR. The Reactor Building Operator will Isolate the HCU for rod 18-11. The SAO will evaluate TS 3.2. B.4, Reactivity Control, for applicability and determine that it does not apply since there are not more than six control rods inoperable. (ATC: Component Malfunction; BOP: Component Malfunction; SRO Tech Spec)

The crew will respond to rising Off-Gas activity and enter ABN-26, High Main Steam/Off-Gas/Stack Effluent Activity. When the Off-Gas HI HI alarm is received, the ATC will reduce power with Recirculation Flow to attempt to lower Off-Gas activity. (ATC: Reactivity Manipulation) (PRA)

The fuel failure will increase and activity will continue to rise and the crew will scram the reactor and shut MSIVs lAW ABN-26, High Main Steam/Off-Gas/Stack Effluent Activity. (Crew: Major)


6

ILT 13-1 NRC Scenario 3 (Modified)

A tube leak will occur in Isolation Condenser B and the steam line will not be able to be isolated. Entry into Radioactivity Release Control EOP. The Shift Dose Assessor will call the control room and report that offsite dose has exceeded that required for a General Emergency. This will require the SAO to direct an Emergency Depressurization from the Radioactivity Release EOP. This will render the EMRVs as the only method available for RPV pressure control. (Crew: Major; Crew: Component Malfunction After EOP) (PRA)

Critical Task 1

When Main Steam Line Radiation Monitors are> 800 mr/hr and OffGas activity is rising OR if the Off-Gas HI HI alarm is received and does not clear within 15 minutes, THEN scram the reactor and manually isolate the reactor if it doesn't isolate automatically.

Critical Task 2

When aGE from offsite dose has been declared, then Emergency Depressurize the RPV.

ES-301-4 Target Quantitative Actual Event Attributes Attributes Number{s}

1. Total malfunctions (5-8) 6 1-6

2. Malfunctions after EOP entry (1-2) 1 6

3. Abnormal events (2-4) 2 3-4

4. Major transients (1-2) 2 5-6

5. EOPs entered/requiring substantive 1 5 actions (1-2)


7. Critical tasks (2-3) 2 5-6


I L T 13-1 NRC Scenario 3 (Modified)

Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 3 Event No.: 1 Event Description: Trig of EDG-1 during gerformance of surveillance 636.4.003.


Cues: Annunciator T4b, EDG 1 DISABLED; T1 b, LK OUT RELAY TRIP; EDG-1 UNIT START light extinguishes


BOP • Continues with surveillance 636.4.003 at starting at step 6.7 .

0 Verifies the following for EDG-1:

• UNIT START and UNIT IDLE lights are extinguished

• EDG-1 diesel alarms are in their normal state

• EDG-1 MODE SELECTOR switch is in the PEAKING position

0 Verifies an operator is stationed at EDG-1 [part of initial conditions]

0 Positions the NORMAL START switch for EDG 1 to the START position

NOTE: 45 seconds after starting EDG-1 it will trip.

• Responds to annunciator T-4-b

0 Positions the NORMAL START switch for EDG 1 to the STOP position (per step 6.10 of surveillance)

0 Directs EO at EDG-1 to investigate cause of the trip. [ROLE PLAY]

ROLE PLAY: Report that EDG-1 tripped on overspeed.

SRO • Provides oversight for EDG-1 surveillance .

• May direct RAP-T 4b be performed [may designate T4b as an expected alarm]

• Declares EDG-1 INOPERABLE .

• Applies Tech Spec 3.7.C.3

0 If both diesel generators become inoperable during power operation, the reactor shall be placed in the COLD SHUTDOWN CONDITION.

• Notifies SMNVWM about EDG status



Terminus: EOG-1 has been declared INOPERABLE and the SRO has reviewed/applied Tech Specs.

Notes/Comments



Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 3 Event No.: g Event Description: LPRM 28-25A upscale failure (input to APRM 4)

[Trigger 31

Initiation: EDG-1 has been declared INOPERABLE and the SRO has reviewed/applied Tech Specs., or as directed by the Lead Examiner

Cues: Annunciators G1c, SCRAM CONTACTOR OPEN; G1d, CHANNEL I; G1f, APRM HI-HIIINOP I; G3f, APRM HI; G6f, LPRM HI; APRM 4 indicates high; LPRM 28-25A indicates high; Annunciator H7a, ROD BLOCK


BOP • Responds to annunciators G1c, SCRAM CONTACTOR OPEN; G1 d, CHANNEL I; G1f, APRM HI-HI/INOP I; G3f, APRM HI; G6f, LPRM HI

o Monitors recirculation flow, feedwater flow and temperature, reactor pressure, and RPV water level

o Checks APRM 4 drawer for LPRM failures

o Reports LPRM 28-25A indicates high

• Bypasses LPRM 28-25A lAW 403

o Obtain permission from the US to bypass an LPRM associated with an APRM

o Directs the ATC to bypass APRM 4

o Perform the following for an LPRM detector in an APRM channel:

• Rotate red input bypass switch in the counterclockwise direction

• Position alarm bypass toggle switch to BYPASS • Verify white BYPASS light Lit

• Verify amber light Lit adjacent to bypassed detector

• Verify white INPUT BYP light for the APRM channel Lit • Adjusts APRM 4 gain if not within 1%

• Directs SRO to update Attachment 403-2

• Notify Reactor Engineer



ATC • Reports % scram RPS 1

• Reports APRM 4 indicates high with HI and HI-HI lights lit

• Reports all other APRMs indicate normal

• Monitors reactor power

• Bypasses APRM 4 by placing the APRM BYPASS to CH 4 prior to bypassing the LPRM; may reset the % scram at this point

• Monitors APRM 4 output to insure proper response with the LPRM detector bypassed when the LPRM is bypassed

• Un-bypasses APRM 4 after the LPRM is bypassed

• Resets the % scram

SRO • Directs BOP to bypass APRM 4 and LPRM 28-25A lAW 403

• Directs ATC to un-bypass APRM 4

• Directs ATC to reset the % scram (when APRM 4 is bypassed or after APRM 4 is returned to normal)

• Notifies Reactor Engineer, SMMIWM of the event

• Reviews Tech Specs 3.1.B.1

0 Determines that an operable APRM Channel only requires 4 operable inputs and that APRM 4 is still operable

0 Failure of four chambers assigned to any one APRM shall make the APRM inoperable

Terminus: LPRM 28-25A is bypassed and the SRO has reviewed Tech Specs 3.1.B.1

Notes/Comments



Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 3 Event No.:~ Event Description: Respond to an outward driftina control rod trod 18-11) rTRIGGER SJ Initiation: LPRM 28-25A is bypassed and the SRO has reviewed Tech Specs 3.1.B.1, or as directed by the Lead Examiner Cues: Annunciator H6a, ROD DRIFT; Control rod position indication for control rod 18-11 is rising Time Position Applicant's Actions or Behavior

ROLE PLAY

ATC • Responds to Annunciator H6a, ROD DRIFT o Reports control rod 18-11 is drifting outward of the core o Reports entry into ABN-6

• Places ROD POWER Switch to ON • Selects control rod 18-11 • Applies an insert signal to the control rod • When the control rod is returned to its

programmed position, then removes the insert signal

• Reports that the control rod continues to drift outward

• Applies a continuous INSERT signal to the control rod using the ROD CONTROL switch

• Following the rod scram, removes the insert signal

• Reports that control rod 18-11 remains at position 00

• Directs the EO to isolate the associated HCU lAW with Procedure 302.1, Control Rod Hydraulic System [ROLE PLAY]

• Places ROD POWER switch to OFF • Notifies Chemistry to sample Reactor Coolant

for activity • Monitors Off-gas activity, Reactor coolant

activity, and Main steam line radiation • Notifies Reactor Engineering • Informs US to consult Tech Spec, Section 3.2.

As the EO directed to isolate HCU 18-11, report that HCU 18-11 is isolated (no booth actions required)

BOP • Scrams the affected control rod from Panel 6XR lAW procedure 235

o May direct the EO to verify the following valves open at HCU 18-11:101, 102,&108[ROLEPLAY]

ROLE PLAY: When directed as the EO to verify the 101, 102, and 108 valves open at HCU 18-11, report that the valves are open OR directs the EO to isolate HCU 18-11 with cooling water.



0 Obtain Key #129 from the key locker located in the Shift Managers office for Panel 6XR

0 Unlocks Panel 6XR 0 Selects the control rod 18-11 and places the toggle

switch to the open (scram) position (up position) 0 Verifies that the scram display illuminates for 18-11 rod

position indicator (Panel 4F) [BOOTH]

BOOTH: When control rod 18-11 indicates in a scrammed condition, then DELETE MAL-CRDOOS 1811.

0 When rod movement stops, removes the scram signal by placing the 18-11 toggle switch to the closed position (down position)

0 Verifies the scram signal is removed 0 Locks Panel 6XR 0 Returns the key to the key locker in SM office


• Notifies SM/WWM and Reactor Engineering about the drifting control rod

• Declares control rod 18-11 inoperable

• Reviews/applies Tech Spec 3.2.8.4

Terminu Control rod 18-11 is valved out at position 00, and the SRO has s: reviewed/applied the Tech Specs

Notes/Comments



Op-Test No.: 13-1 NRC Scenario No.: NRC Sim 3 Event No.: 1 Event Description: Fuel Failures Leads to a Reactor Power Reduction [Trigger 9]

Initiation: Control rod 18-11 is valved out at position 00, and the SRO has reviewed/applied the Tech Specs, or as directed by the Lead Examiner

Cues: Annunciators 1 OF1 k, AREA MON HI; 1 OF2c, OFF GAS HI; Offgas radiation monitors rising


BOP • Reports Main Steam and Off-Gas radiation rising (may be reported by ATC)

• Responds to annunciator 10F1k, AREA MON HI

0 Reports the SJAE AREA ARM is above the high setpoint

• Responds to Annunciator 1 OF2c, OFFGAS HI

• Reports offgas radiation monitors rising

• Performs ABN-26, High Main Steam I Off-Gas I Stack Effluent Activity

0 Directs Chemistry to sample the following for offgas and reactor coolant activity

0 Informs the Unit Supervisor of Technical Specifications 3.6.E & 4.6.E

0 Informs Reactor Engineering of the rise in Off gas effluent activity

0 When the OFFGAS HI (10F1c) annunciator is received, notifies Chemistry of the changes

• Makes plant announcement of entry into ABN-26 (may be performed by A TC)

SRO • Directs entry into ABN-26, High Main Steam I Off-Gas I Stack Effluent Activity

ATC • Reports Main Steam and Off-Gas radiation rising (may be reported by BOP)

• Performs ABN-26, High Main Steam I Off-Gas I Stack Effluent Activity

0 When the OFFGAS HI (10F1c) annunciator is received, reduces reactor power taking the MASTER RECIRC



SPEED CONTROLLER knob in the CCW direction

0 May insert Cram rods

Terminus: The ATC reduced reactor power when the OFFGAS HI (10F1c) annunciator was received

Notes/Comments




Event Description: Fuel Failure Will Rise Resulting In A Reactor Scram and Reactor Isolation

Initiation: The ATC reduced reactor power when the OFFGAS HI (10F1c) annunciator was received, or as directed by the Lead Examiner

Cues: Annunciator 10F1c, OFFGAS HI-HI; Offgas radiation monitors rising


FLOOR At the Lead Evaluator's discretion, when the OFF GAS HI-HI (1 OF2c) Evaluator annunciator is received and reactor power is reduced again to clear the

alarm, a 15-minute waiting period begins to see if the alarm will clear. The alarm is designed to NOT clear. Therefore, announce to the SAO that time compression is being used here and that 15 minutes have elapsed and Offgas has isolated [BOOTH]

BOOTH When the Floor Evaluator has announced time compression above, insert Trigger 13 to isolate the AOG system.

ATC • Performs ABN-26, High Main Steam I Off-Gas I Stack Effluent Activity

0 When the OFFGAS HI-HI (10F2c) annunciator is received, reduces reactor power taking the MASTER RECIRC SPEED CONTROLLER knob in the CCW direction

CRITICAL TASK 1 • Scrams the reactor lAW ABN-1 (may also scram due to offsite dose rate)

0 Depresses both Manual Scram Pushbuttons

0 Places the Reactor Mode Selector switch in SHUTDOWN

0 Verifies all control rods fully inserted

0 Reports immediate scram actions complete

• Performs ABN-26

0 Confirm V-7-31, Off Gas Exhaust Isolation Valve closed

0 Confirms AOV-0001 A/-0001 B, AOG Inlet Valves closed

0 Places Drain Valves V-7-291SOV-016 control switch in the CLOSE position

0 Closes the following valves (the following valves will be



closed if RPV Lo-Lo level was reached post scram):

0 MSIVs

0 Isolation Condeser tube side vent valves

0 V-24-29, Reactor Water sample valve

0 V-24-29, Reactor Water sample valve

0 V-6-395, Drywell Air Supply valve

0 May evacuate the Reactor Building and Turbine Building

0 Refers SRO to EP-AA-1010

SRO • When the time compression has been announced, directs the

CRITICAL TASK 1 ATC to scram the reactor and perform ABN-1 [the SRO may direct a reactor scram prior to time compression being announced if they believe the rise in main steam activity cannot be turned]

• Following the scram, directs closure of the MSIVs and sample valves lAW ABN-26 (the valves will be closed if RPV Lo-Lo level was reached post scram):

• Directs entry into RPV Control - No ATWS EOP

0 Directs the Crew to maintain RPV water level 138"- 160" using SP2 (Cond/FW) and/or SP3 (CRD)

0 Directs the Crew to maintain RPV pressure (approximately) 800 - 1 000 psig using the Isolation Condensers (SP-11) or EMRVs (SP-12)

BOP • Controls RPV water level as directed following the scram

0 Reports entry into RPV Control- No ATWS on low RPV water level

0 When RPV level begins to rise following the scram, then performs the following:

0 Trips 2 Feed Pumps with their control switches

0 Places all MFRVs in MANUAL

0 Closes all MFRVs

0 Directs the EO to close CRD Supply Water Valve to Charging Water Header valve V-15-52 [ROLE PLAY]

ROLE PLAY: As the EO directed to close CRD Supply Water Valve to Charging Water Header valve V-15-52, insert Trigger 11. Report when complete.

0 Enters SP-2 (Cond/FW) when directed



0 Controls RPV water level using the following as necessary: 0 Feedwater Regulating valves

0 Main Feed Regulating Valve (MFRV) Block valves

0 Feedwater Low Flow valves

0 Heater Bank Outlet Isolation valves

0 Feedwater and Condensate pumps


0 SP-11 (ICs)

0 Trips Recirculation Pump A for use with IC-A (or Recirculation Pump E for use with IC-B)

0 Verifies RPV water level< 160"

0 Cycles Condensate Return Valve V-14-34 as necessary to maintain RPV Pressure with IC-A (or V-14-35 for IC-B)

0 SP-12 (EMRVs)

0 Verifies Torus water level is> 90"

0 Places one or more EMRV control switch in the MAN position, then back to AUTO

Terminus: The reactor has been scrammed, MSIVs closed, and RPV water level and pressure are under control

Notes/Comments




Event Description: Leak in Isolation Condenser Tube and Rising Isolation Condenser Area Radiation Levels Leading to Emergency Degressurization [Trigger 15]

Initiation: The reactor has been scrammed, MSIVs closed, and RPV water level and pressure are under control, or as directed by the Lead Examiner

Cues: Annunciators 10F1k, AREA MON HI; C6a, SHELL A LVL HI/LO; C7b, SHELL TEMP HI; Isolation Condenser shell water level rising


Crew • Responds to annunciators 1 OF1 k, AREA MON HI; C6a, SHELL A LVL HI/LO; C7b, SHELL TEMP HI

0 Reports Isolation Condenser shell level high and ARM rising

0 Diagnosis an Isolation Condenser tube leak

• Attempts to close IC-A steam valves and reports the valves will not close

0 May direct an EO to manually close the valves

• Reports when the IC ARM reaches 1000 mr/hr (MAX SAFE)

• Performs Emergency Depressurization - No ATWS EOP

CRITICAL TASK 2 0 Places ROPS in BYPASS when directed

0 Places all EMRV switches to MAN

• Secures Core Spray lAW SP-1 0 as directed

SRO • Directs entry into the Radioactivity Release Control EOP

0 Directs RO to close Isolation Condenser A isolation valves 0 Directs RO to monitor IC ARM

0 Determines fuel failures when the Isolation Condenser ARM reaches MAX SAFE or from Offgas HI-HI alarms

ROLE PLAY: When the IC ARM has reached the MAX SAFE value (1000 mr/hr) and the US has determined fuel failures, call the US as the Shift manager and report the following: As the Emergency Director, you are declaring a General Emergency EAL RG1.

CRITICAL TASK 2 • Directs entry into Emergency Depressurization- No ATWS EOP

0 Directs ROPS bypassed



0 Verifies Torus water level> 90"

0 Directs RO to manually open all EMRVs

• Directs securing Core Spray lAW SP-10 if not required for adequate core cooling

Terminus: Emergency Depressurization has been performed by the crew and RPV water level is under control.

The Emergency Plan call RG 1 was provided to the SRO as part of the scenario.

Notes/Comments



Procedures Used

Event Procedure

1 • TS 3.12

2 • RAP-G1c

• RAP-G1d

• RAP-G1f

• RAP-G3f

• RAP-G6f

• RAP-H7a

• 403

•

3 • RAP-h6a

• ABN-6

• TS 3.2.8.4

• 235

4 • RAP-1 OF1 k

• RAP-10F1c

• RAP-10F2c

• ABN-26

5 • ABN-1


• SP-2

• SP-3

6 • Secondary Containment Control EOP

• Radioactivity Release Control EOP

• RAP-C6a



Simulator Setup

1. Reset to IC-115, lower power to 95% with Recirc Flow 2. Have a copy of 636.4.003 marked up to and including step 6.6 3. Tag out EDG-2 4. Protect Core Spray System 1, EDG-1, CRD Pump A, & Containment

Spray System 1. 5. Display PPC point EDG1 KW (analog) on a PPC terminal screen 6. Place a signed copy of Att 403-2 in the 403 binder


N/A Preset----)- LOA-DGN012 to TRIP

LOA-DGN009 to STOP

STL-DGN004 to OFF

STL-DGN-005A to OFF

ANN-T-4F to ON

• This disables EDG-2

1 Preset----)- Insert the following Event Trigger (1) and Command (2) on Trigger 1:

1) Hwx06o118w.eq.1

Trigger 1- MAL-DGN004A on a 45 second delay

MAL-DGN005A on a 45 second delay

• This ensures EDG-1 trips

2 Trigger 3- MAL-NIS019_018A to 125

• This will cause LPRM 28-25A (input into APRM 4) to go upscale and result in Yz scram from APRM 4 being higher than scram setpoint.

3 Trigger 5- MAL-CRD005_ 4219

• This causes control rod 18-11 to drift outward from its current position 10

• This malfunction will be deleted within



the scenario, following the individual scram of the control rod

4 Trigger 9 _,. MAL-RXS001 to 0.0008, starting at 0.0002, over a 15 minute ramp

• This inserts a fuel failure

5/6 Trigger 11 _,. LOA-CRD024 to 0

• This closes CRD Supply Water Valve to Charging Water Header valve V-15-52

Trigger 13 _,. VLV-OGS042 to CLOSE (V-7-31)

VLV-OGS011 to CLOSE (V-7-29)

LOA-OGS007 to CLOSE (AOV001 A)

LOA-OGS008 to CLOSE (AOV001 B)

• This will isolate the AOG System from the Offgas Hi-Hi radiation monitor timeout

Presets_,. VLV-ICS005 to MECH SZ (V-14-30)

VLV-ICS006 to MECH SZ (V-14-31)

• This will keep the IC-A steam admission valves open

Trigger 15 _,. MAL-ICS002A to 25%

• This inserts a tube leak in Isolation Condenser A

ICH-RMS027 A to 3 over 2 minutes with a 1 minute time delay

• This raises the Isolation Condenser ARM to Max Safe value (1000 mr/hr)



Shift Turnover


• 95% power • EDG-2 is OOS for maintenance • Surveillance 636.4.003, Diesel Generator Load Test, is in progress on EDG-

1. • An operator is stationed at EDG-1 for the surveillance • All EDG-1 diesel alarms are in their normal state

Shift Activities

• Complete surveillance 636.4.003, Diesel Generator Load Test, starting at step 6.7, due to a question of operability (oil sight glass was low on the last shift)


Nuclear Regulatory Commission · Appendix C Facility: Oyster Creek Job Performance Measure WORKSHEET Task No.: 2230101504 Form ES-C-1 Task Title: Determine Bulk Drywell Temperature

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