CCNPP Units 1 2 2008 RO Examination Outline · requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. EA1.13 -Steam flow indicators

CCNPP Units 1 & 2 2008 RO Examination Outline ~ ~ ~ ~~~

Facility: CCNPP Units 1 & 2 RO EXAM Date of Exam: 6/13/2008

Note: 1.

2.

3.

4.

5.

6.

7.‘

a.

9.

Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the ‘Tier Totals” in each WA category shall not be less than two). The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by *l from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

Systemdevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systemdevolutions that are not included on the outline should be added. Refer to Section D.l .b of ES-401 for guidance regarding the elimination of inappropriate WA statements.

Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected, Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable WAS.

On the following pages, enter the WA numbers, a brief description of each topic, the topics’ importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G’ on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

CCNPP Units 1 & 2 2008 RO Examination Outline - -

IR

4.2

- # Q#

450230

WA Topic(s)

AK3.04 RCP tripping requirements I 000008 Pressurizer Vapor Space

000009 Small Break LOCA 13 EK2.03 S/Gs 3 .O 1 45023 1

11 000015117 RCP Malfunctions 14 AK2.08 - CCWS 2.6 1 450232

3.0

- 3.2'

- 2.9

1 450250 000022 Loss of Rx Coolant Makeup 12

000025 Loss of RHR System 14

000026 Loss of Component Cooling Water 18

AK1.03 - Relationship between charging flow and PZR level

AK2.02 - LPI or Decay Heat Removal RHR pumps AA2.02 -The cause of possible CCW loss

1 420569

415864 1

4.0 - 3.2

- 3 . F

1

~~

Q5025 1

444467

000027 Pressurizer Pressure Control System Malfunction 1 3

AA1.O1 - PZR heaters, sprays, and PORVs

2.3.12 - Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

EA1.13 -Steam flow indicators

AKl.01 - MFW line break depressurizes the S/G(similar to a steam line break)

1

1 11 000038 Steam Gen. Tube Rupture 1 3 450252

000054 (CWEOG) Loss of Main Feedwater 14 ll 4.1 1

~~

450253

11 000055 Station Blackout I 6 EK1.02 - Natural circulation cooling 4.1 1 450254

4.4

- 3.1

- 2.9

3 .I -

1 450255 000056 Loss of Off-site Power I 6

000057 Loss of Vital AC Inst. Bus 16

000062 Loss of Nuclear Svc Water 14

AK3.02- Actions contained in EOP for loss of offsite power

AA2.04 - ESF system panel alarm annunciators and channel status indicators

AA2.02- The cause of possible SWS loss

AK3.08 - Actions contained in EOP for loss of instrument air

2.4.28 - Knowledge of procedures relating to a securitv event non-safegaurds information)

1 450256

I 450474

450258

~~~

000065 Loss of Instrument Air / 8 H 1

000077 Generator Voltage and Electric I Grid Disturbances 16 3.2 1

~~

450259

CWEO2 Reactor Trip- Stabilization - Recovery11 i CEIEOS Steam Line Rupture - Excessive

Heat Transfer14

KIA Category Totals:

3.1

- - t.5

a

1 420628 EAl. 1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features

2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operation procedures

Group Point Total:

1 Q50261

=

18

WAPE # t Name I Safety Function

000001 Continuous Rod Withdrawal / 1

000003 Dropped Control Rod t 1 AA1.05 - Reactor power - turbine

WA Topic(s) IR # Q#

2.17 - Ability to make accurate, clear 3.9 1 450262 and concise verbal reDorts

CWA16 Excess RCS Leakage t 2

450264

450265

450266 I

450267

4.50268

450475

450270

450273 EK3.3 - Manipulation of controls required to obtain desired operating results during abnormal and emergency

3.3 1

I WA Category Point Totals: I Group Point Total: 9 I I

CCNPP Units 1 & 2 2008 RO Examination Outline

System # / Name

003 Reactor Coolant Pump

004 Chemical and Volume Control

WA Topic(s) IR

K6.14 - Starting requirements 2.6

K5.43 - Saturation subcooling, 3.6 SuDerheat in steadwater

450476

450275

013 Engineered Safety Features

005 Residual Heat Removal

012 Reactor Protective System

006 Emergency Core Cooling

007 Pressurizer RelieWQuench Tank

008 Component Cooling Water

008 Component Cooling Water

010 Pressurizer Pressure Control

5.02 - Safety system logic and 2.9 1 450276 reliability

A4.05 -Position of RWST 2.8 1 450290 recirculation valve (locked when not in use, continuously monitored when in use)

2.1.32 Ability to explain and apply 3.8 1 450350 system limits and precautions

A1.09 - Pump amperage, including 2.8 1 45031 1 start, normal and locked

*

A1 .O3 - Monitoring quench tank 2.6 1 450335 temperature

K3.01- Loads cooled by CCWS 3.4 1 450337

A4.09 - CCW temperature control 3.0 1 450338 valve

K2.02 - Controller for pZR spray 2.5 1 450339

012 Reactor Protection

K1.02 - SEChemote monitoring systems K4.04 - Reduction of temperature and pressure in containment after a LOCA by condensing steam, to reduce radiological hazard, and protect equipment from corrosion damage (spray)

K2.02 - MOVs

013 Engineered Safety Features Actuation

022 Containment Cooling 3.7 *

3,7

2.7 *

026 Containment Spray

1

026 Containment Spray

450342

valve I

1

1

K3.04 - ESFAS

K6.01 - Sensors and detectors

450343

450345

A1.09 - Main steam line radiation monitors

2.1.43 - Ability to use procedure to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

450340

450341

2.5 1 450347 *

4.1 1 450348

039 Main and Reheat Steam

039 Main and Reheat Steam

CCNPP Units 1 & 2 2008 RO Ex

059 Main Feedwater A2.07 - Tripping of MFW pump turbine

059 Main Feedwater A3.04 - Turbine driven feed pump

061 Auxiliary/Emergency K3.01- RCS Feedwater

062 AC Electrical Distribution 2.141 - Knowledge of the refueling process

062 AC Electrical Distribution K1.02- ED/G

063 DC Electrical Distribution K1.02 - Ac electrical svstem

064 Emergency Diesel Generator K4.01 - Trips while loading the ED/G(frequency, voltage, speed)

A2.01 - Erratic or failed power SUDDlV

073 Process Radiation Monitoring

076 Service Water A2.01 -LOSS of SWS

078 Instrument Air

103 Containment

A3.01 - Air pressure

K4.06 - Containment isolation svstem

WA Categoty Point Totals: Group Point Total:

2.5 I- 4.4 - 2.8

- 4.1

2.7

3.8

2.5

3.5 * - 3.1

3.1

ation Outline

1 450349

1 1 450351

450354

420632

450358

1 I 450359

1 450361

1 420392

440363

450364

1 450365

WA Category Point Totals: Group Point Total:


- - #

1

- - IR

4.0

-

2.9

3.3

3.2

3.1 * - 3.5

3.2

_.

* - 4.5

3.3

2.7

-

- -

WA Topic(s)

K6.14- Location and interpretation of reactor triD breaker

Q#

450366

System # / Name

001 Control Rod Drive

01 1 Pressurizer Level Control 1 450368 K4.07 - Cold calibrated channel

K2.01 - NIS channels, components, and interconnections

K1.O1 -Plant computer

K5.01 -Purpose of charcoal filters

015 Nuclear Instrumentation 1 450369

01 7 In-core Temperature Monitor 1 450370 ~~

027 Containment Iodine Removal 1 45037 1

035 Steam Generator A1.02 - S/G Dressure 1 450373

1

- 1

041 Steam Dumvurbine Bypass Control

450374

450376

K3.01 - S/G

2.4.4 - Ability to recognize abnormal indications for system operating parameters that lare entry-level conditions for emergency and abnormal oDerating Drocedures

056 Condensate

071 Waste Gas Disposal A4.09 Waste gas release rad monitors 1 450377

086 Fire Protection 450378 A2.03 - Inadvertent actuation of the FPS due to circuit failure or welding


2.1.30

Generic Knowledae and Abilities Outline (Tier 31

IR #

Ability to locate and operate components, including local 4.4 1 450381 controls.

I

Facility: CCNP

Categoly

Ability to recognize system parameters that are entry-level conditions for Technical Specifications.

1. Conduct of Operations

~~

3.9 1 450384 2. Equipment Control

3. Radiation Control

Units 1 & 2 Date of Exam: 611 312008

WA # Topic RO Q# I

2.2.22 I Knowledge of limiting conditions for operations and safety I 4.0 I 1 I 450385

2.2.42

2.3.4

2.3.12

2.3.1 3

Subtota

Knowledge of radiation exposure limits under normal or emergency conditions.

Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning

~~

2.4.32

2.4.37

Knowledge of operator response to loss of all annunciators.

Knowledge of the lines of authority during implementation of

3.6 I 1

3.0 I 1

450388

450389

450390

450395

Q50398

CCNPP Units 1 & 2 2008 RO Examination Outline ES-401 Record of Rejected WAS Form ES-401-4

Reason for Rejection

CCNPP Units 1 & 2 2008 SRO Examination Outline

Note: 1.

2.

3.

4.

5.

6.

7.*

8.

9.

Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the ‘Tier Totals” in each WA category shall not be less than two). The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by i 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

Systemdevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systemdevolutions that are not included on the outline should be added. Refer to Section D.l .b of ES-401 for guidance regarding the elimination of inappropriate WA statements.

Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.l .b of ES-401 for the applicable WAS.

On the following pages, enter the WA numbers, a brief description of each topic, the topics’ importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G‘ on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.


WA Topic(s)

EA2.05 - Reactor trip first out indication

ES-401 2

IR

3.9 000007 Reactor Trip-Stabilization -

00001 1 Large Break LOCN3 ~ ~

2.2.20 - Knowledge of the process for managing troubleshooting activities

EA2.09- Existence of adequate natural circulation

2.4.9 - Knowledge of low powerlshutdown implications in accident (e.g., loss of coolant laccident or loss of residual heat removal) mitigation strategies.

occurred, verification that substitute power sources have come on line

2.4.46 - Ability to verify that the alarms are consistent with the plant conditions.

AA2.01- That a loss of dc power has

000009 Small Break LOCA 13 I

~~

3.8

4.3

4.2

4.1

4.2

II 000040 Steam Line Rupture - Excessive Heat Transfer/4

000058 Loss of DC Power/6

CWEO6 Loss of Main Fedwater14 ll

#

1 -

I

1

1

- 1

- 1 - 6 -

Q #

450399

450402

450404

420393

450407

450409


E/APE # I Name / Safety Function

1 000028 Pressurizer Level Malfunctionl2

000060 Accidental Gaseous Radwaste Release/S

000061 ARM System Alarmsii’

CWEOS Functional Recovery

WA Category Point Totals:

licensed operator responsibilities related to shift staffing, such as medical requirements, “n0-s0l0”

during shutdown operations, such as


System # / Name

003 Reactor Coolant Pump

012 Reactor Protection

013 Engineered safety Features Actuation

WA Topic@) IR

3.9 A2.01 - Problems with RCP seals, especially rates of seal leak-Off.

A2.03 - Incorrect channel bypassing

2.2.21 Knowledge of pre- and post- maintenance operability requirements.

3 .I

4.1

026 Containment Spray A2.03 - Failure of ESF 4.4

+-p 450432

076 Service Water

Q.50450

Q504.5 1

Q50453

2.2.43 Knowledge of the process used to track inoperable alarms.

3.3 I Q50455 t WA Category Point Totals: Group Point Total: 5 I


System # / Name

028 Hydrogen Recombiner and Purge Control

WA Topic(s)

A2.01 - Hydrogen recombiner power setting, determined by using plant data

IR

5.6

~~~

029 Containment Purge

072 Area Radiation Monitoring

450456

A2.03 - Startup operations and the associated required valve lineups

3.1

2.1.39 Knowledge of conservative 4.3

1 420602

1 450458


2.4.5

2.4.21

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Knowledge of the organization of the operating procedures 425069 4.3 1

Knowledge of the parameters and logic used to assess the status 450470 4.6 1

network for normal, labnormal, and emergency evolutions.

of safety Ifunctions, such as reactivity control, core cooling and heat removal, reactor coolant system integritv, containment

Facility: CCNP I

Units 1 & 2 Date of Exam: 6/13/2008

Category k 1. Conduct of Operations

Equipment Control

Radiation

4. Emergency Procedures I Plan

W A # I Topic SRO-On1

I I #

I 450469 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments,

CCNPP Units 1 I& 2 2008 SRO Examination Outline ES-401 Record of Rejected WAS Form ES-401-4

Tier I Randomly Reason for Rejection Group Selected K/A

NONE NIA

CCNPP Units 1 & 2 2008 RO Walkthrough Exam Outline

ES-301 Administrative Topics Outline Form ES-301-1

Facility: CCNPP Units 1 & 2 Date of Examination: 6/16/2008 Examination Level: RO SRO 0

Administrative Topic (see Note)

Conduct of Operations

Radiation Control

Type Code*

M, C

M, S

Operating Test Number: 2008

Describe activity to be performed

2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9 ,4.2)

Determine Power Ratio Recorder Setpoints for Loss of Plant computer.

2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports. (3.6,3.8)

Determine 1 hour reportability requirements based on plant events

2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (4.2 ,4.4)

Determine that RCP restart criteria are met following a station blackout

2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (3.5,3.6)

Determine radiological conditions for personnel exposure

Emergency Procedures/Plan

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

* Type Codes & Criteria: (C)ontrol room, (Sjimulator, or Class(R)oom (D)irect from bank (I 3 for ROs; I 4 for SROs & RO retakes) (N)ew or (M)odified from bank (2 1) (P)revious 2 exams (I 1; randomly selected)

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2

CCNPP Units 1 & 2 2008 RO Walkthrough Exam Outline

Faci I i ty: Exam Level: RO 0 SRO-I 0 SRO-U Operating Test No.: 2008

CCNPP Units 1 & 2 Date of Examination: 6/16/2008

b. RCS - Respond to a loss of RCS inventory while SDC is in use

c. PPCS - Respond to a Pressurizer spray valve failure

~_____ 11 Control Room Systems" (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

A,M,L,S 2

A,NS 3

System / JPM Title I

e. RHR - Respond to a loss of all LPSl pumps while on SDC

f. 480VAC - Return a 480VAC bus to service following maintenance

Type Code*

A, M,L, S 4(pri)

M,S 6

Safety Function

1

I d. MFW - Respond to a feedwater rupture at power ~

4( sec)

11 g. NIS - Calculate Tq using the excore Nls 7

11 h. CCW- Respond to a CCW malfunction I N S I 8

11 In-Plant Systems" (3 for Ro); (3 for SRO-I); (3 or 2 for SRO-U)

11 i. IA - Respond to a loss of IA while shutdown 1 E D I 8

j. 41 6OVAC - Denergize a 4KV Bus during a Control Room Evacuation I 6

11 k. MRSS - Locally Shut MSlV due to Control Room Evacuation I E, N,R l 4 Q All RO and SRO-I control room (and in-plant) systems must be different and serve different safety

functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

~

* Type Codes Criteria for RO / SRO-I / SRO-U

(A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (WCA (S)imulator

4-6 14-6 / 2-3

1 9 / 5 a / s 4 2 1 / 2 1 / 2 1

2 1 1 2 1 1 2 1 2 2 / 2 2 / 2 1 I; 3 / I 3 1 5 2 (randomly selected) 21 121 1 2 1

- / - / 21 (control room system)

CCNPP Units 1 & 2 2008 SRO Walkthrough Exam Outline

ES-301 Administrative Topics Outline Form ES-301-1

Faci I i ty: Examination Level: RO 0 SRO Operating Test Number: 2008

CCNPP Units 1 & 2 Date of Examination: 6/16/2008 // Administrative Topic I (see Note)

Radiation Control

Type Code*

M, c

N, c

M, S

Describe activity to be performed

2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports. (3.6,3.8)

Determine 1 hour reportability requirements based on plant events

2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc. (4.1,4.3)

Review a new Power Ratio Recorder setpoint calculation

2.2.36 Ability to analyze the effect of maintenance activities, such as degraded power Isources, on the status of limiting conditions for operations. (3.1,4.2)

Evaluate the affects of degraded equipment support on T.S.

2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (3.5,3.6)

Perform a Risk assessment of an activity in the RCA

2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required.( 2.4, 4.4)

Determine amrouriate EWE' remonse actions I

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

* Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (I 3 for ROs; 5 4 for SROs & RO retakes) (N)ew or (M)odified from bank (1 1) (P)revious 2 exams (I 1; randomly selected)

ES-301 Control Roodln-Plant Systems Outline Form ES-301-2

I

Type Code*


Facility: CCNPP Units 1 & 2 Date of Examination: 6/16/2008 Exam Level: RO SRO-I SRO-U Operating Test No.: 2008

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety Function

System / JPM Title

e. RHR - Respond to a loss of all LPSl pumps while on SDC-ESFAS A, M,L, S 4(P$

11 a. CEDS- Respond to CEA(s) Misaligned by 8" or more 1

1.

j. 41 GOVAC - Denergize a 4KV Bus during a Control Room Evacuation

C.

E,D

E, M 6

~~ 11 g. NIS - Calculate Tqusing the excore NIS

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

~~ 11 k. MRSS - Locally Shut MSlV due to Control Room Evacuation [ E, N

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

* Type Codes Criteria for RO / SRO-I / SRO-U I (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator

5 9 / s a / s 4 2 1 I 2 1 121

2 1 1 2 1 1 2 1 22/22/21 5 3 / S 3 / I 2 (randomly selected) 2 1 1 2 1 / 2 1


I


Facility: CCNPP Units 1 & 2 Date of Examination: 6/16/2008 Exam Level: RO 0 SRO-I SRO-U 0 Operating Test No.: 2008

Type Codes

(A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(R)CA (P)revious 2 exams

(S)imulator

11 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Criteria for RO / SRO-I / SRO-U

4-6 / 4-6 12-3

1 9 1 s a i s 4 2 1 / 2 1 / 2 1

2 1 12 1 / 2 1 2 2 / 2 2 / 2 1 I 3 / r; 3 15 2 (randomly selected) 2 1 1 2 1 1 2 1


System / JPM Title

a. CEDS- Respond to CEA(s) Misaligned by 8" or more

b. RCS - Respond to a loss of RCS inventory while SDC is in use

c. PPCS - Respond to a Pressurizer spray valve failure

11 e. RHR - Respond to a loss of all LPSl pumps while on SDC-ESFAS

f. 480VAC - Return a 480VAC bus to service following maintenance

g. NIS - Calculate Tq using the excore Nls

h. CCW- Respond to a CCW malfunction

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

Type Code* ~

Safety Function

i. IA - Respond to a loss of IA while shutdown 8

j. 41 6OVAC - Denergize a 4KV Bus during a Control Room Evacuation

k. MRSS - Locally Shut MSlV due to Control Room Evacuation

6

4( sec)

I'

pendix D Scenario Outline Form F,S - - D 1. Op-Test No.: 2008 Scenario No.: 1 Page a of A

Facility: Calvert Cliffs 1 & 2 Scenario No.: 1 Op-Test No.: 2008

Examiners: Operators:

Turnover: Unit 1 was EOL at 100% for previous 9 months 2 hours ago power was reduced to 75% power to perform valve testing which was completed SAT. 11 & 12 charging pumps are running with boron equalization in progress. CVCS makeup is aligned for direct. No equipment out of service. Instructions for the shift is to return to 100% power.

Event

Auto Trip Relay Failure & Manual Trip Failure

. SGIS A & B Failure

Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes _ _ _- _ _ 1. Total malfunctions (5-8) I 1 6

2. Malfunctions after EOP entry (1-2) I 1 1

3. Abnormal events (2-4) I 1 4

4. Major transients (1-2) I 1 2

5. EOPs enteredlrequiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) I 1 1

7. Critical tasks (2-3) I 1 3

Appendix D Scenario Outline Form ES-D-1

5.

6.

EOPs enteredlrequiring substantive actions (1-2)

EOP contingencies requiring substantive actions (0-2)

7. Critical tasks (2-3)

Scenario No.: 2 Pa g e __ 1 of 10


I I 1

I 1 0

I 1 2


Turnover: Unit 1 is at 100% power at MOL. 12 AFVV pump tagged out for repair of overspeed trip device linkage (6 hours into 18 hour maintenance window).

Event

SIAS “B” Block

(N)orrnal, (R)eactivity, (I)nstrurnent, (C)ornponent, (M)ajor

Actual Attributes

1. Total malfunctions (5-8)

2. Malfunctions after EOP entry (1-2)

3. Abnormal events (2-4) I 1 4

4. Major transients (1-2) I 1 2

D Scenario Outline Form ES - - D 1

Event Malf. No. Event No. Type*

1 RCSO11-03 N (RO)

2 RPSOO7-02 I (CRO)

3 RCS013-03 C (RO)

4 NIA R (All)

Scenario No.: 3 Pa g e 1 of 11



Event Description

~~

12A RCP lSt Stage Seal Failure

Channel B RPS Matrix Power Supply Failure (TS CRS)

12A RCP 3rd Stage Seal Failure

Perform Expeditious Reactor Shutdown due to 2 failed seals on 12 RCP

Turnover: Unit 1 is at 100% power, MOL equilibrium conditions. 13 HPSI pump tagged out for repair of excessive vibration during last STP 0-7B (3 hours into 36 hour maintenance window) IAS LCO 3.5.2.A.

Target Quantitative Attributes (Per Scenario; See Section D.5.d)

1. Total malfunctions (5-8)

Actual Attributes _- -- _ _ I 1 5

2. Malfunctions after EOP entry (1-2)

3. Abnormal events (2-4)

4. Major transients (1-2)

I 1 1

I 1 3

I 1 1

5.

6.

EOPs enteredlrequiring substantive actions (1-2)

EOP contingencies requiring substantive actions (0-2)

7. Critical tasks (2-3) I I 1 3

I 1 1

1 1 0

Appendix D Scenario Outline Form ES-D-1

Event No.

0

1

2

3

5

6 I


Examiners: Operators: I

Malf. No. Event Event Type* Description

AFWOO1-02 12 AFW Pump Failure

NIOOl1-01 I (RO) Channel A NI Power Summer Failure

F W O 18-02 I (CRO) 12 FRV Controller Failure

SWYDOO2 M (ALL) Loss of Offsite Power

4KV001-01 C (CRO) 11 4KV bus fault

AFWOO1-01 C(CR0) 11 AFW Pump Failure

Turnover: Unit 1 is at 100% power, BOL, Equilibrium Conditions. 12 AFW pump tagged out for repair of overspeed trip device linkage (6 hours into 18 hour maintenance window).

Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5-8) 11

2. Malfunctions after EOP entrv (1-21 11

_ _ -_ _ _ 5

2

3. Abnormal events (2-4)

4. Major transients (1-2)

5. EOPs enteredhequiring substantive actions (1-2)

-

11 2

11 1

11 1

6.

7. Critical tasks (2-3)

EOP contingencies requiring substantive actions (0-2) 11 0

I 1 3

CCNPP Units 1 2 2008 RO Examination Outline · requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. EA1.13 -Steam flow indicators

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