Watts Bar Initial Exam 2011-302 Final SRO ... - NRC: Home Page · Page 1. 10-2011 Watts Bar SRO NRC License Exam 12/29/2011 2. Given the following:-Unit 1 is operating at 100% power

10-2011 Watts Bar SRO NRC License Exam12/29/2011

1. Given the following:

- A reactor trip occurs on Unit 1.

- ES-Ui, “Reactor Trip Response,” has been implemented.

- Shutdown Bank ‘B’ rod G3 remains at 228 steps.

- Control Bank ‘D’ rod M8 sticks at 16 steps while inserting.

- Tavg dropped to 549°F before stabilizing.

Which ONE of the following completes the statement below?

Conditions indicate Immediate Boration is

_______

to satisfy ShutdownMargin.

A. NOT required

B. required due to the RCS temperature ONLY

C. required due to the stuck control rods ONLY

D. required due to the RCS temperature and the stuck control rods

Page 1



- Unit 1 is operating at 100% power with Pressurizer Heater Group Cenergized.

- Pressurizer PORV 68-340A leakage exceeds spray flow.


Assuming NO operator action, 1-Tl-68-318, PZR SURGE LINE TEMP,indication will (1) and the Tech Spec Operational Leakage limit would beexceeded when the leakage reached C2)

LIJ

A. Rise >1.0 gpm

B. Rise >logpm

C. Lower >1.Ogpm

D. Lower >logpm

Page 2



- Unit 1 is operating at 18% power.

- RCP #2 motor winding temperatures have increased to 304°F.

Which ONE of the following identifies the action required and the reason for thesequence?

A. Trip the reactor and then stop RCP #2 because the unit will not be operatedon 3 loop operation in Modes I or 2 due to conservative industry operatingprinciples.

B. Trip the reactor and then stop RCP #2 because Tech Spec LCO 3.4.4 doesnot allow 3 loop operation with the Unit in Mode 1.

C. Stop RCP #2 and then trip the reactor because the challenge is to the pumpand there is no challenge to DNB during 3-loop operation at the currentreactor power level.

D. Stop RCP #2 and then trip the reactor because the challenge is to the pumpand stopping the pump does not challenge the reactor trip system at thecurrent reactor power level.

Page 3



- Unit I is operating at 100% power.

- The C-S CCS Pump trips while supplying the B Train CCS.

- Operators have not taken any action.

Which ONE of the following completes the statements below?

To restore flow, the 2B-B CCS pump (1)

If the I B-B CCS pump is used to supply B Train CCS, its suction valve mustbe re-aligned to (2)

A. (1) must be manually started(2) protect train separation within the CCS surge tank

B. (1) must be manually started(2) ensure a suction path to the 1 B-B CCS pump

C. (1) will automatically start(2) protect train separation within the CCS surge tank

D. (1) will automatical[y start(2) ensure a suction path to the I B-B CCS pump

Page 4




- 1-XS-68-340D, PZR PRESS CONTROL CHANNEL SELECT, is selectedto PT-68-340 & 334.

- 1-XS-68-340B, PZR PRESS RECORDER CHANNEL SELECT, isselected to PT-68-334.

- 1-PI-68-334, PRESSURIZER PRESSURE, fails to the bottom of the scaledue to transmitter failure.

- The other three pressurizer pressure instruments indicate:

1-Pl-68-340A - 2235 psig1-Pl-68-323 - 2220 psig1-Pl-68-322 - 2230 psig

- Operators are performing AOI-18, “Malfunction of Pressurizer pressureControl System,” and have placed 1-XS-68-340D, PZR PRESSCONTROL CHANNEL SELECT, to PT-68-340 B322.

Which ONE of the following identifies how 1-XS-68-340B, PZR PRESSRECORDER CHANNEL SELECT, will be positioned and the reason why?

A. PT-68-323 because it is the channel with the lowest reading.

B. PT-68-322 because it is the channel replacing the control function ofI -PT-68-334.

C. PT-68-323 or PT-68-322 because neither is the channel selected for control.

D. Any position other than PT-68-334 because each is an operable channel.

Page 5



- Unit us at 45% power when the reactor fails to trip from a valid trip signaland cannot be tripped from the MCR handswitches.

- FR-S.1, “Nuclear Power Generation/ATWS,” is entered and theimmediate actions are in progress.

- RCS Tavg is 548°F and dropping.


Both MFPTs will be tripped by a Feedwater Isolation Signal

____

is/areopened.

A. after the first reactor trip breaker

B. after the first MG set output breaker

C. only after both reactor trip breakers

D. only after both MG set output breakers

Page 6


7. The following conditions exist on Unit 1:

- A SIG tube rupture is in progress.

- The crew is backfilling at 125 gpm per ES-3.1, “Post-SGTR CooldownUsing Backfill.”

- A 75 gpm and the 45 gpm orifices are in service.

- The TSC has requested the crew to reduce the backfill rate from 125 gpmto 75 gpm.

Which ONE of the following actions would the crew take to reduce the backfillrate?

A. Lower RCS pressure

B. Raise RCS pressure

C. Lower ruptured SG pressure

D. Raise ruptured SG pressure

Page 7



- Unit us operating at 75% power steady-state conditions.

- A steam line leak occurs on a steam header outside the north valve room.


(1) is the time in core life that results in the largest addition ofpositive reactivity and a manual reactor trip is required in accordance withAOl-38, “Main Steam or Feedwater Leak,” if (2)

A. BOL final reactor power rises to 79%

B. BOL Tavg/Tref cannot be maintained within 4°F

C. EOL final reactor power rises to 79%

D. EOL Tavg/Tref cannot be maintained within 4°F

Page 8



- Unit I is operating at 100% power when an ATWS occurs.


To ensure long term reactor protection, the AFW pumps are assumed to bestarted within a maximum of (1) and the limiting ATWS accidentwhich determines this maximum AFW start time is (2)

wA. 30 seconds

B. 30 seconds

C. 60 seconds

D. 60 seconds

turbine trip

loss of main feedwater

turbine trip

loss of main feedwater

Page 9



- Unit 1 is in Mode 3 following a loss of offsite power 20 minutes ago.

- Both of the Unit 1 diesel generators failed to start.

- A fire on the lower level of the Control Building results in the loss of both250v DC Station Batteries.


The MCR will be able to monitor Core Exit Thermocouples on(1) and to prevent entry into a REQUIRED ACTION in Tech

Spec LCO 3.3.3, Post Accident Monitoring, a minimum of (2)operable thermocouples per train are required.

A. (1) Plasma displays on the control board or Integrated Computer System (ICS)(2) 2 quadrants with at least 4

B. (1) Plasma displays on the control board or Integrated Computer System (ICS)(2) 4 quadrants with at least 2

C. (1) Plasma Displays ONLY(2) 2 quadrants with at least 4

D. (1) Plasma Displays ONLY(2) 4 quadrants with at least 2

Page 10


11. Which ONE of the following identifies the pump that will be sequenced on firstfollowing a blackout signal on a 6900v Shutdown board and a reason?

First Pump Reason

A. COP Largest blackout load on the board.

B. CCP To restore Reactor Coolant Pump seal cooling.

C. ERCW pump Largest blackout load on the board.

D. ERCW pump To restore Diesel Generator engine cooling.

Page 11

10-2011 Watts Bar SRO NRC license Exam12/29/2011



- A loss of 125V DC Vital Battery Board lii occurs.

- Operators are performing AOl-21.03, “Loss of 125V DC Vital BatteryBoard Ill,” Appendix A, “Transfer of 125v DC Buses.”


The operator is directed to ‘DEPRESS and HOLD’ the 6.9kV SD Bd 2A-ABC-RESET switch in logic Panel 2A-A when control power is being restored toShutdown Board 2A-A to (1)

The switch to transfer the 6.9kV SD Bd 2A-A 125V DC NORMAL BUS powersupply is located (2)

A. (1) prevent inadvertent equipment tripping(2) inside the 125V DC Vital Battery Board III room

B. (1) prevent inadvertent equipment tripping(2) inside a compartment on 6.9kV Shutdown Board 2A-A

C. (1) prevent unwanted starts of equipment(2) inside the 125V DC Jita! Battery Board Ill room

D. (1) prevent unwanted starts of equipment(2) inside a compartment on 6.9kV Shutdown Board 2A-A

Page 12




- All available Train A ERCW pumps are in service.

- ERCW pump B-A trips.


If needed to maintain CCS temperature on the Unit 1 Miscellaneous EquipmentHeader, the CCS heat exchanger (1) outlet flow control bypass valve willbe adjusted. As the valve is adjusted, the ERCW flow rate on CCS HeatExchanger B will (2)

wA. C drop

B. A drop

C. C remain constant

D. A remain constant

Page 13

10-2011 Watts Bar SRO NRC License Exam12129/2011


- Unit 1 is currently in Mode 3, with the reactor trip breakers open.

- A control air leak develops inside containment.

- 1-FCV-62-86, Alt Charging to Loop 4, is in service and 1-FCV-62-85,Norm Charging to Loop 1, begins drifting open.

- AOl-i 0, “Loss of Control Air,” is entered.

- The operating crew stops RCPs #1, #3, and #4 in accordance withAOl-b guidance.


The leak is on the (1) header and stopping the RCPs will (2)

A. Auxiliary Air Train B reduce the increase in the pressurizer level

B. Auxiliary Air Train B stop uncontrolled pressurizer spray flow

C. Non-essential Control Air reduce the increase in the pressurizer level

D. Non-essential Control Air stop uncontrolled pressurizer spray flow

Page 14



- Unit 1 is operating at 100% power with the following conditions:

Megawatts 1210 MWeMegavars +20 MvarsGenVoltage 23.6Kv

- A disturbance occurs on the Transmission Grid resulting in the following:

Megawatts 1210 MWeMegavars -180 MvarsGen Voltage 23.6 Ky

- Annunciator 1-C, STATOR TEMP HI, alarms.

- The Stator Coil Outlet temperature is determined to be 177°F and risingat 2°F/minute.


Under the conditions, the timer to trip the turbine (1) been initiated.

The stator temperature can be reduced by (2) generator excitationcurrent.

A. has lowering

B. has raising

C. has NOT lowering

D. has NOT raising

Page 15



- Unit I was operating at 100% power when a small break LOCA occurred.

- The crew has implemented ECA-1 .2, “LOCA Outside Containment,”due to alarm “AUX BLDG HIGH ENERGY LINE BREAK” being LIT.

- When the crew closes RHR Train A cold leg injection valve, 1-FCV-63-93,the RCS pressure begins to rise.

- RCS pressure is now 1520 psig and slowly rising.


The (1) are currently contributing the most ECCS flow to the core andECA-1 .2 will require (2) to be stopped.

A. Safety Injection Pumps only RHR pump IA-A

B. Safety Injection Pumps both RHR pumps

C. Centrifugal Charging Pumps only RHR pump lA-A

D. Centrifugal Charging Pumps both RHR pumps

Page 16



- The crew has entered FR-H.1, “Loss of Secondary Heat Sink,” due to aloss of inventory in the S/Gs and failure of the AFW pumps to start.

SG Wide Range Levels (%) AFW CnmtTime SG#1 SG#2 SG#3 SG#4 Flow Press0800 41 39 38 37 0 gpm 1.70 psid0810 37 32 34 33 Ogpm 2.40 psid0820 30 28 27 26 0 gpm 2.70 psid0830 27 25 22 24 0 gpm 2.50 psid

Which ONE of the following is the earliest time, if any, that the initiation of Bleedand Feed is required?

A. Bleed and Feed NOT required.

B. 0810

C. 0820

D. 0830

Page 17



0900 - Areactortripoccurs.

0910 - A small break LOCA occurs.

0930 - The crew transitions to ECA-1 .1, “Loss of RHR Sump Recirculation,”due to the failure of both RHR pumps.

0940 - Crew reduces ECCS flow to I SIP and I CCP per ECA-1 .1.

0950 - Crew determines SI flow cannot be terminated due to lack ofsubcooling.

1000 - The crew is performing ECA-1 .1 Step 19 RNO to establish theminimum required ECCS flow to remove decay heat.

Which ONE of the following identifies the minimum flow rate that meets the intent ofECA-1.1, Step 19 RNO, and the flow adjustment methodology for meeting this flowrate?

REFERENCE PROVIDED

A. Establish 460 gpm ECCS flow.Starting and stopping ECCS pumps.

B. Establish 460 gpm ECCS flow.Throttling ECCS valves.

C. Establish 370 gpm ECCS flow.Starting and stopping ECCS pumps.

D. Establish 370 gpm ECCS flow.Throttling ECCS valves.

Page 18



- Unit I is operating at 60% power when the Control Rods begin anuncontrolled withdrawal at 72 steps/rn mute.

- The OAC places 1-RBSS, ROD BANK SELECT to MAN stopping the rodmovement.

- The operating crew determines a failure of the RCS temperature input tothe Rod Control System resulted in the uncontrolled rod movement.

- The temperature input to the system has been repaired.

- Current conditions are:

- Tavg is 1.4°F above Tref.- ROD SPEED indicates 48 Steps/mm.- PASSIVE SUMMER ROD DEMAND indicates slightly over +1.0.- Control Bank D rods are at 176 steps withdrawn.

If 1-RBSS, ROD BANK SELECT is returned to AUTO, which ONE of thefollowing identifies how the control rods will respond?

Control Rod position will...

A. remain at 176 steps withdrawn.

B. decrease because of the Tavg-Tref error.

C. increase because the Rod Speed has not decayed to ‘0’.

D. decrease because of the PASSIVE SUMMER ROD DEMAND.

Page 19

10-2011 Waifs Bar SRO NRC License Exam12/29/2011


- During receipt of new fuel, a non-irradiated fuel assembly is dropped onthe refueling floor.

- A plant announcement is made per AOl-29, “Dropped or Damaged Fuelor Refueling Cavity Seal Failure,” to evacuate the affected area.

In accordance with AOl-29, which ONE of the following completes thestatements below?

The affected area is required to be evacuated to protect against thepotential exposure to (1) radiation.

Non-fuel handling related work on the Refuel Floor can first be resumedwhen (2)

W L)

A. Alpha ONLY Radiation Protection grants approval to inspect thefuel assembly.

B. Alpha ONLY the damaged fuel assembly has been inspected andstored.

C. Alpha/Beta/Gamma Radiation Protection grants approval to inspect thefuel assembly.

D. Alpha/Beta/Gamma the damaged fuel assembly has been inspectedand stored.

Page 20



- Unit 1 was operating at 100% when a steam generator tube leakoccurred.

- The unit has been placed in Mode 3.

- The leaking steam generator pressure is 950 psig.

- The operating crew is currently determining the target incore temperaturefor RCS cooldown, per the following table in AOl-33, “Steam GeneratorTube Leak.”

LEAKING SG TARGET INCOREPRESSURE (PSIG) TEMP F)

1 100 491 F

1000 479T

900 466T

800 451F

700 434F

690 433F

Which ONE of the following identifies the steam pressure setpoint on the steamdump system that would maintain the target incore temperature?

A. 480 psig

B. 495 psig

C. 545 psig

D. 560 psig

Page 21



- Main Turbine load is 660 MWe.

- Condenser vacuum is decreasing at 0.1 in-HgAlmin due to air in-leakage.

- The crew has entered AOl-il, “Loss of Condenser Vacuum.”

- Currently Condenser pressures are:

Zone ‘A’ Zone ‘B’ Zone ‘C’3.75 in-HgA 4.93 in-HgA 6.06 in-HgA


The turbine automatic ‘low vacuum trip’ (1) failed.

Zone (2) is currently at a condenser pressure that requires a plant trip.

REFERENCE PROVIDED

Li)

A. has ‘B’

B. has NOT ‘B’

C. has ‘C’

D. has NOT ‘C’

Page 22



- Unit I was operating at 100% power when a Main Control Roomevacuation was performed in accordance with AOI-30.2, “Fire SafeShutdown,” Series procedure C.69, “Fire Safe Shutdown Control Building.”

Which ONE of the following completes the statements below with respect to AuxControl Room indications?

Tcold is determined using (1) installed instrumentation.

Thot is determined using (2) installed instrumentation.

A. RCS temperature Incore Thermocouple

B. RCS temperature RCS temperature

C. SG pressure Incore Thermocouple

D. SG pressure RCS temperature

Page 23



- Following a LOCA the operating crew is performing FR-C.1, “InadequateCore Cooling.”

- Containment pressure peaked at 5.2 psid.

- Depressurizing the S/Gs to atmospheric pressure is ineffective in reducingincore T/C temperatures.

- All RCP support systems are available for RCP5 2 and 4.

- RCP5 1 and 3 have no ERCW supply for the motor coolers.

- S/G Narrow Range levels are:#1 #2 #3 #4

40% 41% 32% 52%

- Core exit thermocouples have exceeded 1200°F.

- RCPs are to be started one at a time in an attempt to reduce core exitthermocouples below 1200°F.

Which ONE of the following identifies the RCP5 that would be started in anattempt to reduce core exit thermocouple temperatures?

A. RCP4ONLY

B. ALL four of the RCPs

C. RCP5 2 and 4 ONLY

D. RCPs1,2,and4ONLY

Page 24



- A small break LOCA occurred on Unit 1.

- ES-i .2, “Post LOCA Cooldown and Depressurization,” is in progress.

- RCS pressure is 1420 psig and one charging pump has been stopped.

- The crew is ready to stop the first SI pump.


When the SI pump is stopped, RCS subcooling will drop (1)

The minimum RCS subcooling value required to allow the second SI pump tobe stopped is (2) than the value required for stopping the first pump.

A. (1) and stabilize at a lower value due to an increase in RCS temperaturewith lower ECCS injection flow

(2) less

B. (1) and stabilize at a lower value due to an increase in RCS temperaturewith lower ECCS injection flow

(2) greater

C. (1) due to reduced ECCS injection flow and stabilize at a lower value whenbreak flow equals ECCS injection flow.

(2) less

D. (1) due to reduced ECCS injection flow and stabilize at a lower value whenbreak flow equals ECCS injection flow.

(2) greater

Page 25


26. Following a Small Break LOCA, the crew is performing the actions contained in FR-Ri,“Pressurized Thermal Shock.”

Which ONE of the following describes the reason for RCP restart in FR-P.i,“Pressurized Thermal Shock,” if the SI termination criteria cannot be satisfied?

An RCP running...

A. raises the RCS temperature entering the vessel downcomer.

B. prevents vessel head voiding as the RCS pressure is dropped.

C. restores pressurizer spray flow for reducing RCS pressure.

D. reduces the minimum required subcooling to terminate SI.

Page 26



- A large break LOCA has occurred on Unit 1.

- The crew is performing E-1, “Loss of Reactor or Secondary Coolant,” withthe ECCS aligned for cold leg recirculation.

- The operating crew determines the criteria for entering FR-Z.2,“Containment Flooding,” is met.


The implementation of FR-Z.2 is (1)

The procedure directs the sampling of the sump to (21

A. (1) required(2) ensure shutdown margin is being maintained, since non-borated water

has entered the containment sump

B. (1) at the discretion of the crew.(2) ensure shutdown margin is being maintained, since non-borated water

has entered the containment sump

C. (1) required(2) to allow the TSC to determine if excess sump water can be transferred

to tanks outside of containment

D. (1) atthe discretion of the crew(2) to allow the TSC to determine if excess sump water can be transferred

to tanks outside of containment

Page 27


28. Given the foflowing:

- Unit 1 is in Mode 5 preparing for an RCS heatup.

- RCP #2 is in service.

- RCP #4 has experienced the following start and run times as part of amaintenance PMT:

- 1615 - started but stopped before it reached rated speed.- 1655- started and then stopped after a 10 minute run.- 1740- started and then stopped after a 10 minute run.

- The time is now 1800 and RCP #4 is ready to be placed in service.

Which ONE of the following identifies the earliest time the pump can bestarted and the breaker handswitch that will be used to start the RCP motor?

Time Handswitch

A. 1820 1-HS-68-73AA, RCP 4 NORMAL BKR & LIFT PMP

B. 1820 1-HS-68-73BA, RCP 4 ALTERNATE BKR & XFER SELECTOR

C. 1850 1-HS-68-73AA, RCP 4 NORMAL BKR & LIFT PMP

D. 1850 1-HS-68-73BA, RCP 4 ALTERNATE BKR & XFER SELECTOR

Page 28




- Annunciator 95-C, RCP 1 STANDPIPE LEVEL HI/LO, alarms.


The operating crew will first attempt to clear the alarm by (1) thestandpipe and if this action clears the alarm, the condition indicates apossible problem with the (2) seal on the RCP.

wA. filling #3

B. filling #2

C. draining #3

D. draining #2

Page 29



- Unit I is operating at 100% power after restart following a refuelingoutage.

- Rod Control in MANUAL.

- VCT level is currently at 32%.

- An AUO places an un-borated mixed bed demineralizer in service.


Assuming NO operator action is taken, the VCT level will (1)

In accordance with AOI-3, “Malfunction of Reactor Makeup Control,” the firstcorrective action the RO will take that will stop the event in progress is to

(2)

A. (1) remain constant(2) place 1-HS-62-79A, LTDN HI TEMP DIVERT, to ‘V.C. TK’

B. (1) remain constant(2) initiate normal boration

C. (1) rise overtime(2) place 1-HS-62-79A, LTDN HI TEMP DIVERT, to ‘V.C. TK’

D. (1) rise overtime(2) initiate normal boration

Page 30




- Annunciator 110-D, LTDN TO DEMINS TEMP HI, alarms.

- The OAC determines the indication on 1-Tl-62-78, letdown temperature.has slowly increased from 120°F to 132°F and is stable.


The letdown temperature rise results in reactor power (1)

The action required by the OAC is to (2) in accordance with the ARI.

Note: 1-HIC-62-78A - Letdown Heat Exch Outlet Temp Control

A. (1) increasing(2) ensure CVCS demineralizers bypassed and adjust 1-HIC-62-78A

B. (1) decreasing(2) ensure CVCS demineralizers bypassed and adjust 1-HIC-62-78A

C. (1) increasing(2) adjust 1-HIC-62-78A ONLY

D. (1) decreasing(2) adjust 1-HIC-62-78A ONLY

Page 31



- Unit 1 is in Mode 5, midloop operation.

- RHR Train A in service at a flow rate of 2100 gpm.

- The RCS temperature is stable at 126°F.

- The operator throttles open 1-FCV-74-32, RHR HXS BYPASS.


As 1-FCV-74-32, RHR HXS BYPASS is throttled open, the RCS temperaturewill (1) and the RHR flow rate indicated on 1-M-6 will (2)

A. decrease increase

B. decrease decrease

C. increase increase

D. increase decrease

Page 32



- Unit 1 was operating at 100% power when a reactor trip and SI withloss of offsite power occurred 20 minutes ago.

- Pressurizer pressure dropped to 1750 psig, then recovered fiveminutes later to 2235 psig.

Current conditions:

- Offsite power has been restored.

- Pressurizer level is currently at 68% and stable.

- RCS cold leg temperatures are 561°F and stable.

- RCS hot leg temperature is 590°F and slowly decreasing.

- RVLIS indicates 96%.

- All SGs are at 1125 psig and controlled by the SG PORVs.

- ES 1.1, “SI Termination,” is being performed and is at the step fordetermining RCP status.

Which ONE of the following identifies the impact of the above conditionson RCP restart?

A. RCP restart is NOT allowed; The resulting injection of cold watercould result in reactor restart.

B. RCP restart is NOT allowed; The resulting heat transfer from the steamgenerators could result in a pressure surge in the RCS.

C. RCP restart is allowed only after an engineering analysis of the borationfrom ECCS injection during natural circulation operation.

D. RCP restart is allowed; Natural circulation flow has been established andhas removed the cold ECCS water from the cold legs.

Page 33


34. The pressurizer (PZR) cold cal level is at 40% with a nitrogen blanket present.

Which ONE of the following choices completes the statement below?

When establishing a steam bubble, in accordance with GO-i, “Unit Startup FromCold Shutdown To Hot Standby,” the pressurizer administrative maximumheat-up rate limit is (1) and the PORVs are closed and placed inP-AUTO when (2)

wA. 75°F in one hour

B. 75°F in one hour

C. 100°F in one hour

D. 100°F in one hour

Letdown flow exceeds charging flow

PZR Liquid Temperature reaches 235°F

Letdown flow exceeds charging flow

PZR Liquid Temperature reaches 235° F

Page 34



- Unit us at 100% power with Thermal Barrier Booster Pump (TBBP)lB running.

- TBBP handswitches on 0-M-27 are aligned with:

1-HS-70-131A, THRM BAR BSTR PMP IA (TBBP) is ‘PULL A-PAUTO’.

1-HS-70-130A, THRM BAR BSTR PMP IB(TBBP)is ‘IN A AUTO’.

- Loss of Offsite Power occurs.


During the blackout relay sequencing to restore equipment, only the (1)TBBP will start after a (2) second time delay.

Li) L?)

A. IA 20

B. lB 20

C. IA

D. lB 35

Page 35




- Abnormal RCS leakage has been detected.

- One of the pressurizer PORVs is suspected to have seat leakage.


Without any additional operator action, the operator could use the MCRindication for (1) to identify which PORV was leaking.

If the PORV is declared inoperable, the crew is required close the PORVBlock valve within (2)

wA. TAILPIPE TEMPS on 1-M-4 1 hour

B. TAILPIPE TEMPS on 1-M-4 30 minutes

C. PZR VALVES ACOUSTIC MONITOR on 0-M-25 1 hour

D. PZR VALVES ACOUSTIC MONITOR on 0-M-25 30 minutes

Page 36


37. Unit I is operating at 100% power when the following sequence of eventsoccurs:

- Pressurizer Power Operated Relief Valve (PORV) I -PCV-68-334 opensand fails to reseat when closed.

- Pressurizer PORV Block valve, 1-FCV-68-332, for PORV 334 cannot beclosed.

- Pressurizer Relief Tank (PRT) pressure begins to slowly rise.

- The PRT pressure continues to rise until the PRT ruptures.


1-PCV-68-301, PRT VENT TO WDS VENT HDR, will automatically closewhen the PRT pressure reaches (1) psig.

When the PRT ruptures, the PORV tailpipe temperature will (2)

wA. 6.5psig begintodrop

B. 6.5 psig rise at a faster rate

C. 8.0 psig begin to drop

D. 8.Opsig rise atafasterrate

Page 37


38. Which ONE of the following identifies the plant electrical boards that supplypower to the listed components on Unit 1?

SSPS Train B Reactor Reactor Trip Bypass Breaker ATrip Breaker 48v UV coil (BYA) Control Power Circuit

A. 120v AC Vital Instrument 125V DC Vital Battery Board IPower Boards II and IV

B. 12OvAC Vital Instrument 125V DC Vital Battery Board IIPower Boards II and IV

C. 12OvAC Vital Instrument 125V DC Vital Battery Board IPower Board II ONLY

D. 120v AC Vital Instrument 125V DC Vital Battery Board IIPower Board II ONLY

Page 38



- Unit 1 has been shutdown for a refueling outage.

- GO-6, “Unit Shutdown from Hot Standby to Cold Shutdown,” is inprogress.

- The lowest RCS Tcold temperature and pressure trend is:

Time Temp Pressure0500 349°F 395 psig0530 337° F 380 psig0600 324°F 345 psig0630 302°F 340 psig0700 280°F 340 psig0730 257° F 340 psig0800 235°F 340 psig0830 214°F 340 psig0900 199°F 330 psig0930 185°F 330 psig

Which ONE of the following is the earliest of the identified times that one of theCentrifugal Charging Pumps is required to be tagged with its breaker rackeddown and the reason for the requirement?

Time Reason

A. 0600 to be in compliance with TR 3.1.3 - ChargingPump, Shutdown.

B. 0600 to be in compliance with LCO 3.4.12 - ColdOverpressure Mitigation System.

C. 0900 to be in compliance with TR 3.1.3 - ChargingPump, Shutdown.

D. 0900 to be in compliance with LCO 3.4.12 - ColdOverpressure Mitigation System.

Page 39



- Unit 1 was operating at 100% power when a design basis LOCA occurred.

Which ONE of the following identifies system(s) directly providing ContainmentCooling during the first minute following the Phase B containment isolation?

A. Containment Spray only

B. Air Return Fans and Ice Condenser

C. Containment Ventilation System and Ice Condenser

D. Air Return Fans and Containment Spray

Page 40


41. Given the foHowing:

- Unit I is operating at 100% power when a LOCA occurs.

- A Safety Injection has been actuated.

- Containment pressure is 1 .1 psig and slowly rising.

Which ONE of the following identifies the expected position of I -FCV-61-1 10,GLYCOL COOLED FLOOR RETURN HEADER ISOL?

A. CLOSED due to a containment isolation signal.

B. CLOSED due to an Auxiliary Building isolation signal.

C. OPEN unless the containment pressure rises to Hi-Hi setpoint.

D. OPEN unless Glycol Storage Tank level reaches Lo-Lo setpoint.

Page 41


42. Which ONE of the foflowing is required to automatically start the Containment SprayPump IA-A room cooler?

A. Containment Spray Pump lA-A running ONLY.

B. Room temperature increases to 95°F ONLY.

C. Either Containment Spray Pump IA-A running OR room temperatureincreases to 95° F.

D. Room temperature increases to 95°F ONLY if the Containment Spray pumprunning.

Page 42



- Containment spray pumps are running after automatically starting during aLOCA.

- Containment pressure has dropped and the procedure directs the pumpsbe stopped.

Which ONE of the following identifies the minimum signals required to be resetto allow the Containment Spray pumps to remain off when their control switchesare returned to ‘A AUTO’ after the pumps are stopped?

A. Containment Spray, only

B. Phase B and Containment Spray, only

C. Safety Injection and Containment Spray, only

D. Safety Injection, Phase B and Containment Spray

Page 43



- At EOL, a reactor startup is in progress following a 6-day outage.

- The Reactor Engineer has provided an ECP which predicts the reactor goingcritical at 120 steps on Control Bank D.


(1) will result in the critical rod height being HIGHER than the valuepredicted by the ECP.

(2) is the maximum allowed tolerence between the ECP and theactual critical position before the insertion of all control banks is required.

A. (1) An inadvertent drop in steam pressure of 50 psig(2)1000 pcm

B. (1) A closure of all MSIVs(2)1000 pcm

C. (1) An inadvertent drop in steam pressure of 50 psig(2) 750 pcm

D. (1) A closure of all MSIVs(2) 750 pcm

Page 44



- Unit 1 is operating at 550 MWe.

- Operators have placed the second main feed pump in service.

- Annunciator 49-E, MN/STBY FWP SUCTION NPSH LO. alarms.

- The operating crew determines Main Feed Pump Suction pressure to be120 psig.

Which ONE of the following identifies the action required by the AnnunciatorResponse Instruction?

A. If suction pressure cannot be restored to greater than 250 psig, a turbine tripis required.

B. Suction pressure is low and needs to be raised but currently is above theminimum required.

C. Unless suction pressure is restored to greater than 250 psig, a trip of oneMFP is required.

D. Unless suction pressure is restored to greater than annunciator 49-Esetpoint, a trip of both MFPs is required.

Page 45



- Unit 1 was at 100% power with the TD AFW pump unavailable.

- S/G #2 experiences a steam line break inside containment.

- S/G #2 conditions are as follows:

- Level is currently 12% WR.- Pressure is 80 psig and decreasing.

- No operator action has been taken on the AFW system.


(1) will have been automatically closed to prevent (2)

Note: 1-LCV-3-156 is MD AFW PUMP IA-A SG 2 LEVEL CONTROLI-LCV-3-156A is SG 2 AUX FEED WA TER I-LCV-3-156 BYPASS

A. (1) 1-LCV-3-156 ONLY(2) Cavitation damage to the valve

B. (1) 1-LCV-3-156 ONLY(2) AFW pump runout

C. (1) Both 1-LCV-3-156 and 1-LCV-3-156A(2) Cavitation damage to the valves

D. (1) Both 1-LCV-3-156 and 1-LCV-3-156A(2) AFW pump runout

Page 46




- Main Feed Pump ‘B’ is in service.

- Main Feed Pump ‘A’ is NOT reset.

- All Steam Generator levels are at 38% NR.

Which ONE of the following identifies the status of the AFW Pumps immediatelyafter Main Feedwater Pump ‘B’ trips?

A. Only the TDAFW pump has automatically started.

B. Only the MDAFW pumps have automatically started.

C. Both the MDAFW pumps and TDAFW Pump have automatically started.

D. Neither the MDAFW pumps nor TDAFW Pump have automatically started.

Page 47




- 480V Shutdown Board 1A2-A de-energizes due to an internal fault.

- The crew enters AOl-43.01, “Loss of Unit 1 Train A Shutdown Boards.”


The loss of the board results in (1) and the condition can be mitigatedby (2) in accordance with AOl-43.01.

A. (1) increasing Main Turbine Oil temperature(2) placing 1-TIC-24-69, MTOT TEMP TEMP CONTROL, in MAN and

opening the TCV

B. (1) the loss of most radiation monitor rate meters in the MCR(2) transferring Instrument Power Rack A to ALTERNATE

C. (1) a turbine trip due to Stator Cooling Water temperature increasing(2) transferring Instrument Power Rack A to ALTERNATE

D. (1) increasing Generator Hydrogen temperature(2) placing 1-TIC-24-48, GENERATOR H2 TEMP CONTROL, in MAN and

opening the TC’V’

Page 48




- A battery discharge test is in progress on 125v DC Battery IV and the125v DC Battery Board V is connected to the 125v DC Battery Board IV.

- 0-Sl-0-3, “Weekly Log,” is being performed.

Using 0-Sl-0-3, Appendix A, which ONE of the following identifies the status ofthe 125v DC Baffery Board IV and the 120v AC Vital Inverter 2-IV?

REFERENCE PROVIDED

1 25v DC Battery Board IV Vital Inverter 2-IV

A. Operable Inoperable

B. Operable Operable

C. Inoperable Inoperable

D. Inoperable Operable

Page 49


50. Given the fobwing

- Unit 1 was operating at 100% power when a safety injection occurred.

- Eighteen (18) seconds after Safety Injection, a loss of I 25v Vital DCPower Channel II occurs.

Which ONE of the following identifies the current status of RHR pump I B-B?

A. RHR pump 1 B-B is NOT running but can be started from the MCRhandswitch.

B. RHR pump lB-B is NOT running and can NOT be started from the MCRhandswitch.

C. RHR pump lB-B is running and can be stopped from the MCRhandswitch.

D. RHR pump I B-B is running but can NOT be stopped from the MCRhandswitch.

Page 50



- Unit 1 is operating at 100% power with DG IA-A connected to theshutdown board during performance of the monthly surveillanceinstruction.

- CCP lA-A is in service.

- I phase of the 50 overcurrent relay acutates on Shutdown Board lA-AEmergency Feeder Breaker 1912.

- I second later Offsite power is lost.

Which ONE of the following identifies how the RHR pump lA-A and CCP lA-Aare affected?

A. The CCP will continue to run and the RHR pump will not be started.

B. The CCP will be tripped and neither pump will sequenced on by blackout relays.

C. Both the CCP and the RHR pump will be sequenced on by blackout relays.

D. Only the CCP will be sequenced on by blackout relays.

Page 51



- Annunciator 186A, MCR INTAKE 0-RM-90-1 25/1 26 RAD HI, alarms.

- Both 0-RM-90-125, “MCR INTAKE” and 0-RM-90-126, “MCR INTAKE”have the RED light LIT on 0-M-12.


The MCR is maintained at a positive pressure by the (1) and if0-RM-90-206A, MCR EMERG INTAKE, subsequently detects high radiation, theoutside air supply will (2) to the alternate source.

A. (1) Main Control Room Air Handling Units(2) automatically realign

B. (1) Main Control Room Air Handling Units(2) require manual action to realign

C. (1) Control Building Emergency Air Pressurization Fans(2) automatically be realigned

D. (1) Control Building Emergency Air Pressurization Fans(2) require manual action to realign

Page 52




- ERCW pump handswitch status:

- A-A is in P-T-L- B-A is in A-AUTO and pump stopped.- C-A is in A-AUTO and pump running.- D-A is in A-AUTO and pump stopped.- Emergency Power Selector Switches are positioned to B-A and C-A,

respectively.

- A loss of offsite power occurs.


Prior to the loss of the offsite power, Tech Spec LCO 3.7.8 Essential RawCooling Water (ERCW) System (1) met.

After the blackout sequence relays complete restoration of loads on theShutdown Boards, 0-Pl-67-18A, A ERCW SUP HDR PRESS, will indicate

(2) before the loss of offsite power.

Li)

A. was same as

B. was higher than

C. was NOT same as

D. was NOT higher than

Page 53



- Unit I is in Mode 3 following a reactor trip when a loss of off-site poweroccurs.

- All Diesel Generators start and restore the shutdown boards.


As control air pressure drops, Control and Station Air Compressor ‘A’(1) as needed automatically.

The compressor is supplied from (2)

A. (1) will start and load(2) 480V SD Bd 1A2-A

B. (1) will start and load(2) 480V SD Bd 2A2-A

C. (1) must be manually started but will load(2) 480V SD Bd 1A2-A

D. (1) must be manually started but will load(2) 480V SD Bd 2A2-A

Page 54


55. Which ONE of the following identifies ventilation systems that exhaust out aShield Building Exhaust Vent?

A. EGTS Cleanup Fans and Annulus Vacuum Control Fans

B. EGTS Cleanup Fans and Containment Purge Exhaust Fans

C. Fuel Handhng Exhaust Fans and Annulus Vacuum Control Fans

D. Fuel Handling Exhaust Fans and Containment Purge Exhaust Fans

Page 55



- 480v Emergency Common Transformer is out of service.

Which ONE of the following describes the effect on the Control Rod Drive MGSets if 6900v Unit Board IC is de-energized by relay operation?

A. Both MG sets lose power to the motor.

B. Neither MG set loses power to the motor.

C. Only “A” MG set loses power to the motor.

D. Only “B” MG set loses power to the motor.

Page 56



- Unit 1 is operating at 80% steady state power with all controls in automatic.

Which ONE of the choices below completes the following sentence?

Assuming no operator action, RCS temperature will INCREASE if the(1) fails (2)

wA. N43 Power Range lower detector HIGH

B. N43 Power Range upper detector LOW

C. Rod control auctioneered high nuclear power signal HIGH

D. Rod control auctioneered high nuclear power signal LOW

Page 57



- Unit I is operating at 100% power with all controls in automatic.

- 1-XS-68-339E, PZR LEVEL CONTROL CHANNEL SELECT, is selectedto the Ll-68-339/B320 position.

- A small leak develops on the upper tap fitting for Pressurizer leveltransmitter 1 -LT-68-339.


1-Ll-68-339 indication will start (1) and the actual pressurizer levelwill (2)

A. rising remain constant

B. rising be dropping

C. dropping remain constant

D. dropping be dropping

Page 58



- Unit I was operating at 100% power when a small break LOCA resultedin a reactor trip and safety injection.

- The crew is now performing E-1, “Loss of Reactor or Secondary Coolant,”and is determining if the Hydrogen Recombiners are to be placed inservice.

- Containment Hydrogen analyzers 1-H21-43-200 and 1-H21-43-210indicate 0.5%.

Assuming conditions do not change, which ONE of the following identifies thehydrogen mitigation systems that will be in service when E-1 is completed?

A. ONLY the hydrogen igniters

B. ONLY the hydrogen recombiners

C. BOTH the hydrogen igniters and the hydrogen recombiners

D. NEITHER the hydrogen igniters nor the hydrogen recombiners

Page 59



- Unit 1 isatlOO%RTP.

- Fuel Assembly shuffles are being made in the Spent Fuel Pit.

- 0-RM-90-102, Spent Fuel Pit Radiation Monitor, has been declaredINOPERABLE and removed from service due to an instrumentmalfunction.

- Auxiliary Building Supply fans 1A and 2B are running.


Technical Specifications would (1) continued movement of fuelassemblies in the Spent Fuel Pit.

If 0-RM-90-1 03, Spent Fuel Pit Radiation Monitor, subsequentlydetected Hi Radiation, (2) Auxiliary Building General Supplyfan(s) would trip.

A. NOT allow ONLY 2B

B. NOT allow IA and 2B

C. allow ONLY 2B

D. allow IA and 2B

Page 60



- Unit I was operating at 100% power when a reactor trip occurred.

- A steam dump ‘Tavg Hi’ bistable malfuncUon resulted in 6 Steam Dumpvalves remaining full open as Tavg dropped following the reactor trip.


Tavg dropping to 550° F will result in (1)

If the operators had placed the handswitches listed below to OFF prior toTavg reaching 550°F, the steam dump valves would have closed (2)was/were placed to OFF.

Note:1-HS-1-103A, STEAM DUMP FSV “A”1-HS-1-103B, STEAM DUMP FSV “B”

A. (1) all 6 of the steam dump valves closing(2) after either switch

B. (1) all 6 of the steam dump valves closing(2) pjjjy after both switches

C. (1) only the 3 cooldown valves remaining open(2) after either switch

D. (1) only the 3 cooldown valves remaining open(2) jy after both switches

Page 61




- Waste Gas Decay Tank J relief valve develops a flange leak and the tankcontains high activity gas.

Which ONE of the following identifies how the radiation monitors listed below willrespond to the gas release?

Note:0-RE-90-1 18, Waste Gas Rad Monitor0-RE-90- 101, Auxiliary Building Ventilation Monitor1-RE-90-400, Unit 1 Shield Building Vent Monitor

A. Both 0-RE-90-1 18 and 1 -RE-90-400 will detect the release.

B. Only 0-RE-90-1 01 will detect the release.

C. Only 1 -RE-90-400 will detect the release.

D. Both 0-RE-90-1 18 and 0-RE-90-1 01 will detect the release.

Page 62




- While performing a board walkdown, the incoming DAC determinesannunciator 174-E, 1-RR-90-1 AREA MONITORS INSTR MALF, is LIT.


In accordance with ARI for window I 74-E, the operator would determine whichArea Radiation Monitor was the cause of the annunciator being LIT by the (1)on the associated rate meter.

A condition that would cause the alarm is the (2)

A. (1) GREEN light being DARK(2) rate meter function switch in ALARM ADJ

B. (1) GREEN light being DARK(2) sample flow less than setpoint

C. (1) RED, AMBER and GREEN lights all being LIT(2) rate meter function switch in ALARM ADJ

D. (1) RED, AMBER and GREEN lights all being LIT(2) sample flow less than setpoint

Page 63


64. Given the foflowing:

- Unit 1 has reduced power due to a condenser tube leak that has beenidentified in the East Side tubes.

- The unit is currently at 34% power.

- CCWP I D has been removed from service.

- CCWPs 1A, 1B, and 1C are each running 235 amps.

- East side amertap system has been shutdown.

- Condenser Vacuum Pumps IA and lB are in service.

Which ONE of the following identifies an additional operating condition thatMUST be established when removing the East Side Waterboxes from service inaccordance with SOl-27.01, “Condenser Circulating Water System?”

A. Turbine load MUST be reduced.

B. An additional CCWP is required to be stopped.

C. Stop one of the Condenser Vacuum Pumps.

D. Discharge valves on running CCWPs must be throttled.

Page 64


65. Which ONE of the following identifies why 0-SW-026-0320, RAW SERVICEWATER ISOLATION VALVE 0-FCV-26-320, located in the Makeup WaterTreatment Plant Control Room, would be placed to OFF?

A. Prevent exceeding maximum flow rating of the water treatment systemfollowing the start of any fire pump.

B. Prevent over-pressurizing the water treatment system following the start ofany fire pump.

C. Prevent the automatic closure of 0-FCV-26-320 due to a diesel fire pumpstart.

D. Prevent automatic closure of 0-FCV-26-320 when an electric fire pump startsignal is generated.

Page 65



- Unit 1 is being returned to service following a refueling outage.

Which ONE of the following is NOT identified in the GO procedures as requiringa Public Address (PA) announcement be made?

A. Entering Mode 4

B. Reactor Startup Initation

C. Reactor Critical

D. Opening MSIVs

Page 66


67. Using the attached ICS AFD TARGET DISPLAY screen printout, which ONE ofthe following choices completes the following statements?

The AFD HIGH LIMIT is Li)

If 2) outside of the limit, TS LCO 3.2.3, “Axial Flux Difference,” actionstatement will be entered.

REFERENCE PROVIDED

Li)

A. -5 any NIS channel is

B. -5 at least 2 NIS channels are

C. +7 any NIS channel is

D. +7 at least 2 NIS channels are

Page 67



- The Unit is in Mode 6, with refueling operations in progress.

- The 3Qth. fuel assembly is being loaded into the core.

Which ONE of the foliwing conditions, in accordance with FHI-7, “FuelHandling and Movement,” will require fuel handling activities be stoppedimmediately?

A. An unanticipated rise in count rate by a factor of two occurs on yresponding nuclear channel during any single loading step.

B. Communications is lost between Containment and the Control Room.

C. Water in the Spent Fuel Pit in not clear enough to view the Fuel topNozzles without supplemental lighting.

D. Boron concentration drops by 18 ppm as determined by two successivesamples of Reactor Coolant.

Page 68



- Unit i is operating at 100% power.

- Maintenance is to be performed on AFW Pump lB-B.

- ‘Protected Equipment’ portable sign stands have been placed locally atAFW Pump IA-A.

- An engineer request permission from the CR0 to enter the areaprotected.

Which ONE of the following completes the statements below in accordance withODM-4.0, “Protected Equipment?”

(1) is the organization responsible for the placement of the‘Protected Equipment’ portable sign stands.

The CRC would direct the engineer to contact the (2) to get approvalto enter the area being protected.

A. Operations Shift Manager

B. Operations Work Control SRO

C. Maintenance Shift Manager

D. Maintenance Work Control SRO

Page 69

10-2011 Watts Bar SRO NRC License Exam12/29)2011

70. During shutdown for a Refueling Outage, which ONE of the following identifiesthe highest level of risk that can be voluntarily entered and who must approveentering the risk in accordance with NPG-SPP-07.2.1 1, “Shutdown RiskManagement.”

A. ORANGE Plant Manager

B. ORANGE Outage Manager

C. RED Plant Manager

D. RED Outage Manager

Page 70



- The crew implemented AOI-33, “Steam Generator Tube Leak,” due to a tubeleak in SG #1 and has placed the unit in Mode 3.

- ES-0.1, “Reactor Trip Response,” has been completed and the crew hasresumed performance of AOI-33.

As a result of actions directed in AOl-33, which ONE of the following will requirean entry into a Technical Specification Action statement?

A. Closing the SG #1 Main Steam Isolation Valve.

B. Adjusting the SG #1 PORV controller setpoint to 90%.

C. Isolating the TD AFW pump steam supply valve from SG #1.

D. Blocking Low Steamline pressure and Low PZR pressure SI actuation.

Page 71



- Unit us operating at 100% power.

- Annunciator 183-C, AB VENT 0-RM-101 RAD HI, alarms.

- Operators have been unsuccessful in identifying the source of therelease.


If the alarm source is NOT known, the ARI directs the operators to

________

within 2 hours of the alarm receipt.

A. stop and lock out the Fuel Handling Area Exhaust fans

B. close LWR CNTMT PURGE EXH PRESS RLF, 1-FCV-30-40 & 1-FCV-30-37

C. manually initiate an Auxiliary Building Isolation signal

D. notify RADCON to restrict nonessential entry into the Auxiliary Building

Page 72



- A LOCA has occurred and a SAE has been declared.

- The TSC and OSC have been activated.

- To prevent damage to equipment needed for protection of the public, it isrecommended that an individual make an entry into the lA-A SafetyInjection Pump Room IA.

- Projected dose rate in the pump room is 1.0 xl 5 mRlhr.

- Duration of the exposure is expected to be 6 minutes.

Which ONE of the following individuals must authorize this exposure?

A. Radcon Manager ONLY

B. Site Emergency Director

C. Plant Manager

D. Radcon Manager OR Site Vice President

Page 73



- Unit us operating at 50% power, with all systems aligned normally withTrain A CCP and CCS pumps in service.

- A loss of lA-A 6.9KV Shutdown Board due a differential relay operationoccurs.

- The OAC observes RCP Seal Water Injection flow to all RCPs to be “0.”

- The Control Building AUO reports extensive damage to the lA-A 6.9 KVShutdown Board bus bars.

- The crew implements AOl-43.01, “Loss of Unit I Train A ShutdownBoards.”

Under these conditions, RCP seal cooling is (1) and in accordance withAOl-43.01, the crew will (2)

(I-)

A. available Isolate letdown prior to starting CCP 1 B-B.

B. unavailable Isolate letdown prior to starting CCP 1 B-B.

C. available Start CCP I B-B prior to isolating letdown.

D. unavailable Start CCP 1 B-B prior to isolating letdown.

Page 74



- The plant is operating at 100% power.

- Annunciator 114-A, SSPS-A GENERAL WARNING is LIT.


(1) will cause the alarm and the probable source of the alarm canbe determined locally by (2)

wA. Racking in Reactor Trip Semi-Automatic Tester Board edge

Bypass Breaker A LED lights

B. A blown Ground Return Fuse Semi-Automatic Tester Board edgeLED lights

C. Racking in Reactor Trip Status Lights on the outside of theBypass Breaker A SSPS Panels

D. A blown Ground Return Fuse Status Lights on the outside of theSSPS Panels

Page 75


76. Which ONE of the following completes the statements below?

(1) of the barriers in EPIP-1, “Emergency Plan ClassificationLogic,” Fission Product Barrier Matrix contain(s) a decision point baseddirectly on a RVLIS threshold level.

The RVLIS threshold level that first requires a classification declaration to bemade is (2)

wA. Only 1 <44%

B. 2 <44%

C. Only 1 <33%

D. 2 <33%

Page 76



- Unit I was shutdown 24 hours ago for a refueling outage.

- RHR pump I B-B is tagged for maintenance.

- Current RCS temperature is 135°F and 80 psig.

- RHR pump IA-A trips and cannot be restarted.

- RCS temperature begins to rise.

- The crew is performing AOl-I 4, “Loss of RHR Shutdown Cooling,” andSection 3.9, “RCS Alternate Cooling Method with RX Vessel HeadInstalled,” has been initiated.


The cooling method that is directed to be attempted fjrt after AOl-I 4 Section3.9 is implemented is (1)

A condition that will result in a REP declaration being required is (2)

A. (1) RCS feed and bleed using a CCP and a pressurizer PORV(2) the RCS incore temperature > 200°F

B. (1) Natural circulation in the RCS using the steam generators(2) the RCS incore temperature > 200° F

C. (1) RCS feed and bleed using a CCP and a pressurizer PORV(2) a failure to establish RHR within 15 minutes

D. (1) Natural circulation in the RCS using the steam generators(2) a failure to establish RHR within 15 minutes

Page 77



- Unit 1 is operating at 100% power with the following components out ofservice and tagged for maintenance:

- CCP lB-B- CCSpumplB-B

- Component Cooling Water pump lA-A trips due to motor failure.

- AOl-i 5, “Loss of Component Cooling Water (CCS),” is implemented.

Which ONE of the following correctly completes the statements below?

In accordance with AOl-i 5, (1) minutes is the maximum time theReactor Coolant Pumps are allowed to remain in service.

Implementation of (2) is required.

Note:Attachment I - Alignment of ERCW to CCP IA-A Lube Oil CoolersAttachment 2 - Alignment of CCS Train B to SFP HX B

Li) L?)

A. 10 only Attachment 1

B. 10 both Attachments

C. 12 only Attachment I

D. 12 both Attachments

Page 78



- Unit 1 was operating at 100% power when a Safety Injection occurred dueto a tube rupture in SG #2.

- The crew determined a Target Incore Temperature of 466°F and hasinitiated a rapid RCS cooldown in accordance with E-3, “Steam GeneratorTube Rupture.”

- Before reaching the Target Incore Temperature, SG #2 pressure beginsdropping in a uncontrolled manner.


The basis for cooling the RCS to a Target lncore Temperature of 466°F is to(1)

Based on current plant conditions, the SRO will transition to ECA-3.1,“SGTR and LOCA Subcooled Recovery,” (2)

A. (1) ensure adequate RCS subcooling is maintained after the subsequentRCS depressurization

(2) immediately

B. (1) ensure adequate RCS subcooling is maintained after the subsequentRCS depressurization

(2) after the Target Incore Temperature is reached

C. (1) provide the maximum amount of RCS temperature reduction withoutexceeding Pressurized Thermal Shock limits

(2) immediately

D. (1) provide the maximum amount of RCS temperature reduction withoutexceeding Pressurized Thermal Shock limits

(2) after the Target Incore Temperature is reached

Page 79



- Unit I is operating at 100% power with I -FCV-68-332, BLOCK VALVEFOR PORV 334, closed as required by Tech Specs due to PZR PORV334 being inoperable but capable of being cycled.

- The following sequence of events occur:

1300 - Both 161 kV Offsite power supplies are lost.

1400 - Annunciator 91-A, PZR PORV/SAFETY OPEN, alarms due toPORV 340A opening and the PORV sticks open in mid-positionduring a pressure transient.

1401 - The QAC reports:

1-TI-68-331, PORV 340A & 334 TAILPIPE TEMP, rising,PORV 340A GREEN and RED indicating lights DARK, and1 -FCV-68-333A, BLOCK VALVE FOR PORV 340A has beenclosed.

1500 - Both offsite power supplies are restored.


The indicating lights on 1-HS-68-340A, PZR PORV 340AA, were DARK at1401 due to the (1)

Tech Specs, (2) allow continued operation in Mode I for an unlimitedperiod of time with the current status of the pressurizer PORVs.

A. (1) loss of offsite power(2) will

B. (1) loss of offsite power(2) will NOT

C. (1) valve being at mid-position(2) will

D. (1) valve being at mid-position(2) will NOT

Page 80



- During performance of ECA-1 .2, “LOCA Outside Containment,” the crewdetermines RCS pressure is rising after RHR Train B cold leg injectionvalve 1-FCV-63-94 is closed.

- The crew then stops and locks out RHR pump I B-B and closes its suctionvalve.

Which ONE of the following identifies the required procedure transition?

A. ES-i .1, “SI Termination”

B. E-1, “Loss of Reactor or Secondary Coolant”

C. ECA-1 .1, “Loss of Emergency Coolant Recirculation”

D. ES-i .2, “Post LOCA Cooldown and Depressurization”

Page 81



- Unit I power was reduced to recover a dropped control rod in ControlBank D, Group 2.

- Following recovery of the dropped rod, the lift coils for the appropriaterods are reconnected.

- Annunciator 86-A, CONTROL ROD URGENT FAILURE, has NOT beenreset.

- Rod Control is placed to MANUAL using 1-RBSS, ROD BANK SELECT.


When the OAC places the IN-HOLD-OUT switch lever to the IN position,(1)

The basis for the reactor power reduction required by Tech Spec 3.1.5,Group Rod Alignment Limits is to ensure (2)

A. (1) no rod motion will occur(2) AFD remains within limits

B. (1) ONLY Bank D Group 2 rods will step IN(2) Core design limits for local LHR are not exceeded

C. (1) no rod motion will occur(2) Core design limits for local LHR are not exceeded

D. (1) ONLY Bank D Group 2 rods will step IN(2) AFD remains within limits

Page 82



- Unit 1 was operating at 100% power with 1-RBSS, ROD BANK SELECT,in MAN.

- 1-XS-68-339E, PZR LEVEL CONTROL CHANNEL SELECT,is selected to LI-68-339 & 335.

- Performance of 1-Sl-68-33, “Measurement Of Reactor Coolant PumpSeal Injection Flow,” Section 6.2, “Determination of Seal Leakage,” is inprogress.

- The CR0 has adjusted 1-HIC-62-89A, CHRG HDR-RCP SEAL FLOWCONTROL, as required and is now ready to record the seal injection flowrates for each of the RCPs.

- The ‘Auctioneered High Tavg’ signal fails LOW.


Due to the ‘Auctioneered High Tavg’ signal failure, the RCP seal injectionflow indication will (1)

The Bases for Tech Spec LCO 3.5.5 requiring performance of this test is toensure (2)

A. (1) remain the same(2) sufficient CCP flow to the RCS through ECCS injection lines during an

accident

B. (1) remain the same(2) CCP flow to the RCP seals remains within 8-13 gpm after an actuation

of the ECCS during an accident

C. (1) decrease(2) sufficient CCP flow to the RCS through ECCS injection lines during an

accident

D. (1) decrease(2) CCP flow to the RCP seals remains within 8-13 gpm after an actuation

of the ECCS during an accident

Page 83



0915 - The crew establishes control in the Auxiliary Control Room.

0915 - Tech Spec 3.0.3 is entered.

1030 - The crew initiates a natural circulation cooldown and the following SIGpressure trends are observed:

Time S/G Pressures1030 1040 psig1050 825 psig1110 55opsig1130 470 psig1150 385 psig


In accordance with Tech Specs, the crew (1) violated the limit for RCScooldown rate.

The unit must be placed in Mode 5 no later than (2)

A. (1) has(2) 1515 the next day

B. (1) has(2) 2215 the next day

C. (1) has NOT(2) 1515 the next day

D. (1) has NOT(2) 2215 the next day

Page 84



- The Unit I operating crew is performing ES-0.3, “Natural CirculationCooldown with Steam Void In Vessel (With RVLIS).”

- The Chem Lab reports increasing radiation level in Steam Generator #3.


Based on the current plant conditions, the operating crew will (1)

In accordance with EPIP-1, “Emergency Plan Classification Logic,” theminimum amount of tube leakage that, if exceeded, would exceed theSystem Degradation EAL criteria is (2)

(Assume the tube leakage is the only RCS leakage present.)

A. (1) transition to E-3, “Steam Generator Tube Rupture”(2) 10 gpm

B. (1) transition to E-3, “Steam Generator Tube Rupture”(2) 25 gpm

C. (1) implement AOI-33, “Steam Generator Tube Leak,” in parallel with theperformance of ES-0.3

(2) logpm

D. (1) implement AOI-33, “Steam Generator Tube Leak,” in parallel with theperformance of ES-0.3

(2) 25gpm

Page 85



- All Shutdown Bank Rods are withdrawn to the full out position.

Which ONE of the following identifies the minimum required status of the ReactorCoolant Pumps and the bases for the requirement per Tech Spec 3.4.5 RCSLoops - MODE 3?

Two RCPs operable with...

A. at least one in operation to ensure adequate decay heat removal capability.

B. at least one in operation due to the postulation of a power excursion becauseof an inadvertent control rod withdrawal.

C. both in operation to ensure adequate decay heat removal capability.

D. both in operation due to the postulation of a power excursion because of aninadvertent control rod withdrawal.

Page 86


87. Given the foNowing:

- The crew is currently performing ECA-3.1, “SGTR and LOCA SubcooledRecovery,” with safety injection termination in progress.

- Maximum containment pressure reached during the event is 2.3 psid.

- After stopping the first charging pump, RCS subcooling drops andstabilizes at 64°F.


Based on the current plant conditions, the SRO will direct the crew to (1)and then (2)

A. (1) restart the charging pump(2) continue with ECA-3.1

B. (1) leave the charging pump off(2) continue with ECA-3.1

C. (1) restart the charging pump(2) transition to ECA-3.2, “SGTR and LOCA Saturated Recovery”

D. (1) leave the charging pump off(2) transition to ECA-3.2, “SGTR and LOCA Saturated Recovery”

Page 87




- Control Heater Bank ‘D’ is out of service and its breaker is tagged.

- The following annunciators alarm:

90-B - PZR PRESS LO-DEVIN BACKUP HTRS ON14-E - M-1 THRU M-6 MOTOR TRIPOUT

- Backup Heater Bank ‘C’ 6.9kv breaker is determined to be tripped.


Assuming no operator action is taken, the heater failure will causepressurizerpressuretobe (1)

The bases of the Tech Spec LCO required to be entered is (2)

A. (1) controlled less than 2235 psig(2) to maintain RCS subcooling following a loss of offsite power for an

extended period of time

B. (1) controlled less than 2235 psig.(2) to ensure the core operates within the limits assumed in the safety

analyses

C. (1) returned to and controlled at 2235 psig.(2) to maintain RCS subcooling following a loss of offsite power for an

extended period of time

D. (1) returned to and controlled at 2235 psig.(2) to ensure the core operates within the limits assumed in the safety

analyses

Page 88



- Unit 1 is in Mode 3 preparing for a reactor startup when Tech Spec LCO3.6.12, Ice Condenser Doors, is entered due to the following:

0600 - Annunciator window 144-A, ICE COND INLET DOOR OPEN, alarms.

0620 - An AUO reports one lower inlet door is cracked just off the closedposition, is free to open, but will not close completely.

1010 - Maximum ice bed temperature verified to be 24.6°F.



2050 - Inlet door is repaired, closed, and testing completed.


The purpose of the Ice Condenser lower inlet doors flow proportioningsprings is to (1)

The earliest of the listed times a Tech Spec violation has occurred was at(2)

REFERENCE PROVIDED

A. (1) limit the radiation at the inlet door to 5 rad/hr during normal operation(2) 1010

B. (1) limit the radiation at the inlet door to 5 rad/hr during normal operation(2) 1850

C. (1) ensures flow proportioning through the ice beds during an accident(2) 1010

D. (1) ensure a balanced flow through the ice beds during an accident(2) 1850

Page 89



- Unit I RCS temperature is 325°F with a heatup in progress following arefueling outage.

- During a board walkdown both indicating lights on 1-HS-72-40, RHRSPRAY HDR A. are discovered to be DARK.

- The AUO sent to investigate reports back:

- the valve is closed.- the 480v breaker for the valve is tripped and cannot be reset.


Based on current plant conditions, LCO 3.6.6 Containment Spray System(1) met.

The next Mode change as the heatup continues (2) be made using theprovisions of LCO 3.0.4.b.

A. (1) is NOT(2) may

B. (1) is NOT(2) may NOT

C. (1) is(2) may

D. (1) is(2) may NOT

Page 90



- Unit us defueled with fuel shuffles in progress in the spent fuel pool.

- Personnel report that a leak has developed and level is dropping in thespent fuel pool.

- The irradiated fuel assembly on the hoist is dropped from the Spent fuelHandling Tool while restoring it to a cell location in the storage rack.

- Gas bubbles are reported to be rising in the Spent Fuel Pool.

- Fuel Pool Rad Monitors 0-RM-90-102 and 0-RM-90-103 both increase tothe alarm setpoint.

- The spent fuel pool level stabilized one foot above the siphon breaker.

Which ONE of the following identifies the event declaration to be made and theexternal notification having the shortest allowed time?

REFERENCE PROVIDED

Declaration Notification

A. NOUE NRC

B. NOUE TEMA

C. ALERT NRC

D. ALERT TEMA

Page 91



- Unit 1 operating at 100% power.

- An internal electrical failure causes the output of 0-RM-90-103, “SpentFuel Pit Area Radiation Monitor,” to fail above the HI RAD setpoint.

- The operating crew is performing SOI-30.05, “Auxiliary Bldg HVACSystems,” Section 8.8, “Recovery from Aux Bldg Isolation (ABI),” torestore the system.


During performance of SOI-30.05 to recover from the ABI, a section of(1) will be required to be implemented.

The ABI actuation (2) required to be reported to the NRC as anImmediate Notification.

A. (1) SOI-30.06, “Auxiliary Building Gas Treatment System”(2) is

B. (1) SOl-31 .02, “Post Accident Sampling Facility Ventilation System”(2) is

C. (1) SOI-30.06, “Auxiliary Building Gas Treatment System”(2) is NOT

D. (1) S0I-31.02, “Post Accident Sampling Facility Ventilation System”(2) is NOT

Page 92



- Unit 1 is at 4% power after being restarted from a refueling outage.

- An Appendix R valve is determined to be out of its required Fire SafeShutdown (FSSD) condition.


A maximum time of (1) is allowed by OR 14.10 to restore the valveto the proper FSSD condition before additional action is required.

The planned entry into Mode I is (2)

wA. 14 days

B. 14 days

C. 30 days

D. 30 days

NOT restricted by the action statement

prohibited until the action statement is cleared

NOT restricted by the action statement

prohibited until the action statement is cleared

Page 93



- Unit 1 is in Mode 3 following a reactor trip on the previous shift.

- Auxiliary Air Compressor B is tagged for maintenance.

- A failed temperature switch results in an Auxiliary Building Isolation (ABI).

- ABGTS fan A-A trips due to motor failure when it attempts to start.


The OPDP-8, “Limiting Conditions for Operation Tracking,” LCO TrackingLog entry for the ABGTS Train A failure will be designated as an (1)

The ‘Loss of Safety Function’ evaluation will identify that a loss of safetyfunction (2)

L)

A. ‘Active’ LCO has occurred

B. ‘Information Only’ LCO has occurred

C. ‘Active’ LCO has NOT occurred

D. ‘Information Only’ LCO has NOT occurred

Page 94



- UnitlisinModel.

- To facilitate on-going work, ‘Status Control’ was relaxed on a section ofsafety related piping inside an existing clearance boundary.

- While the operators are re-establishing Status Control following release ofthe clearance, a valve that is required to be open by the valve checklist isfound to be closed and documented in an open work order.


The (1) is the lowest position in the Operations Organization that canauthorize the relaxing of ‘Status Control’ inside the clearnace boundary.

With the valve in the closed position, the valve checklist to re-establishstatus control (2)

A. Shift Manager or designee must remain open until the valve can berestored to the required position

B. Shift Manager or designee can be documented as complete andclosed

C. Operations Superintendent must remain open until the valve can berestored to the required position

D. Operations Superintendent can be documented as complete andclosed

Page 95


96. Which ONE of the following completes the statements below?

To be in compliance with Tech Spec LCO 3.1.5 - Rod Group AlignmentLimits, the performance of 1-SI-85-10, “Rod Drop Time Measurement UsingCERPI Rod Drop Test Computer,” is required prior to a reactor criticalityfollowing (1)

The performance of 1-Sl-85-10 requires a minimum of (2) Reactor CoolantPumps to be in service.

wA. a Mode 5 entry 4

B. a Mode 5 entry 3

C. reactor head removal 4

D. reactor head removal 3

Page 96



- Unit I reactor is critical below the ‘Point of Adding Heat’ in accordancewith GO-2, “Reactor Startup,” during startup following a refueling outage.

- Physics Testing has been declared, and PET-201, “Initial Criticality andLow Power Physics Testing,” is in progress.

- The Plant Manager designates the Site Engineering Director to exercisecontinuous responsibility for the oversight of PET-201.


The (1) the responsibility for control of PET-201.

The (2) is responsible for covering the items contained on the CIPTEPRE-TEST BRIEFING CHECKLIST for the test.

A. (1) Shift Manager retains(2) Test Director

B. (1) Shift Manager retains(2) Site Engineering Director

C. (1) Site Engineering Director assumes(2) Test Director

D. (1) Site Engineering Director assumes(2) Site Engineering Director

Page 97



- Unit 1 is in Mode 3 with RCS at normal operating temperature andpressure awaiting secondary plant equipment repair to continue thestartup.

- RCS Activity was determined to be 0.28 microcuries/gram DOSEEQUIVALENT 1-131 and Technical Specification LCD 3.4.16, RCSSpecific Activity, is entered.

- The DOSE EQUIVALENT 1-131 was unable to be restored to within theLCD limit in the required action time.


Technical Specification LCO 3.4.16 states the RCS Tavg must be reduced toless than 500° F within a maximum of (1) hours and the bases is to limitdoses at the site boundary in the event of a (2)

A. 8 LOCA in conjunction with the La value of 0.25%/day leakagefrom containment.

B. 6 LOCA in conjunction with the La value of 0.25%/day leakagefrom containment.

C. 8 Main Steam Line Break in conjunction with an existing SG tubeleakage of 150 gpd.

D. 6 Main Steam Line Break in conjunction with an existing SG tubeleakage of 150 gpd.

Page 98



- Unit 1 was operating at 100% power when a fire occurred outside of the125v Vital Battery I and II rooms.

- AOl-30.2, “Fire Safe Shutdown,” has been entered.

- Using AOl-30.2, Appendix B, “Fire Safe Shutdown Elevation Diagrams,”the determination is made that the fire involves both of the followingrooms:

- 480v Rx MOV Bd Rm I B (East)- 480v Rx MOV Bd Rm 1 B (West)

- While the fire is in progress, a Safety Injection signal is generated.


In accordance with AOI-30.2, Appendix B, “Fire Safe Shutdown ElevationDiagrams,” the minimum required action by the operating crew is theperformance of (I)

AOl-30.2 actions (2) precedence over the Emergency OperatingProcedures.

REFERENCE PROVIDED

A. (1) both AOI-30.2 C.3 and C.4(2) take

B. (1) both AOI-30.2 C.3 and C.4(2) doNOTtake

C. (1) either AOI-30.2 C.3 or C.4(2) take

D. (1) eitherAOl-30.2C.3orC.4(2) do NOT take

Page 99



0825 - Shift Manager/SED declares a Site Area Emergerency and initiatesthe Emergency Paging System to staff the TSC and OSC.

0830 - The Assembly and Accountability process is initiated.

Which ONE of the following completes the statements below in accordance withthe Radiological Emergency Plan?

A report from Security on the results of accountability will be provided tothe Shift Manager/SED no later than (1’)

The Shift Manager will be relieved of the SED status and the TechnicalSupport Center activated no later than (2)

w ()

A. 0900 0925

B. 0900 0955

C. 0915 0925

D. 0915 0955

Page 100

10-2011 Watts Bar SRO NRC License Exam1212912011

REFERENCE PACKAGE

1. Steam Tables

2. AOl-i 1, Appendix A, Condenser Vacuum ICS Graph, (1 page)

3. 0-SI-O-3, Weekly Log, Appendix A, (2 pages)

4. ICS ‘AFD TARGET DISPLAY’, (1 page)

5. ECA-i-l, Loss of RHR Sump Recirculation, (2 pages)

6. Tech Spec 3.6.12, Ice Condenser Doors (5 pages)

7. EPIP-1, “Emergency Plan Classification Logic,” (1 page)

8. AOI-30.2 APP B, Fire Safe Shutdown Elevation Diagrams 2.0 AB EL 772.0, 776.0 &763.5 ELEVATION DIAGRAM (1 page)

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L Page 20 of 43

SR 3.8.-L3

082810)

Appendix A(Page 9 of 24)

1808.1

2-SW-SOS-I 125 VITHLISO 150W POWER 3D 2-IVDISC

2-SD 215-4 123 Vat VITALO4STR POv’vER BOARD 2-SO

FROMO-XSW236-79002-S, OUTPUT 2I 20820 TRANSFER SWITCHSELECT CHARSERS 7-SIN-SROlE 2

2-BISOl-Z3-4CB1

NOTE (I) In Modes 5&6 only one train of ac/dc PWR is reouired, ii this train is nol required this nace rosy be N/A.(2) When 7-S or 8-S charQer is connected to Bait Sd Th rify aesoc. train Transf Switches are closed and.SJt bkrs are open.

NITIALS OF DATA COLLECTOR: J1i DATE

____________

REMARKS: //

NO (IDA)

ly

SR 3 8.5 1SR 3.8.7.1SR 3. 8. 8. 1SR 3.8.9.1SR 3.8.10.1

S- CLOSED

A- AVAUSELE

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SO 1-IVW.A3-ISVER

2-XOW-235-421T I 120 SAC VITAL(510) 8101 NOTE POWER

302-IS

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WRN Loss of RHR Sump Recircuation ECA-1.1LJrit I Rev. 0012

[Step j [Action/Expeed Response Response Not Obtained

19. CHECK SI termination criteria:

a. RVLIS greater than 60% a. F RVLIS is less than or equal tov’ith NO RCP running, setpoint, THEN

OR GO TO Step 25.

RVLIS greater than 63%with ANY RCP running.

b. RCS subcooling greater than b. ESTABLISH minimum ECCS flowrequired from table: for decay heat removal:

1) REFER TO Figure 1,Minimum SI Flow For DecayHeat Versus Time After Trip.

2) **GOTOStep25

RCS PRESS BETWEEN REQUIRED SUSCOOLING

285 AND 585 psig 1 15°F [135°F ADV]

585 AND 1085 psig 102°F [1 23°F ADV]

1085 AND 1885 psig 97°F [1 17°F ADV)

Greater than 1885 psig 94°F [1 14°F ADV]

20. RESET Phase A and Phase B.

Page 12 of 35

WBN Loss of RHR Sump Redrcu[atoF1 ECA-i.1L Unft I Rev. 0Q12

700.0

600.0

500.0

2400.0

300.0

200.0

100.0

0.0

Figure I(Page 1 ofl)

Mhirnurn S Fcw for Decay Heat vs. Tme After Thp

1000010 100 1000

Time After Trip (Minutes)

Page 29 of 35

Ice Condenser Doors3. 6.12

3.6 CONTAINMENT SYSTEMS

3.6.12 Ice Condenser Doors

LCO 3.6.12 The ice condenser inlet doors, intermediate deck doors, andtop deck doors shall be OPERABLE and closed.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

NOTESeparate Condition entry is allowed for each ice condenser door.

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more ice A.1 Restore inlet door to 1 hourcondenser inlet OPERABLE status.doors inoperabledue to beingphysicallyrestrained fromopening.

B. One or more ice B.1 Verify maximum ice bed Once percondenser doors temperature is 27°F. 4 hoursinoperable forreasons other than ANDCondition A or notclosed. B.2 Restore ice condenser 14 days

door to OPERABLE statusand closed positions.

(continued)

Watts Ear—Unit 1 3 . 6—31

ACTIONS (continued)

Ice Condenser Doors3.6.12

CONDITION REQUIRED ACTION COMPLETION TIME

C. Required Action and C.1 Restore ice condenser 48 hoursassociated door to OPEPABLE statusCompletion Time of and closed positions.Condition B notmet.

D. Required Action and D.l Be in MODE 3. 6 hoursassociatedCompletion Time of ANDCondition A or Cnot met. D.2 Be in MODE 5. 36 hours

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.6.12.1 Verify all inlet doors indicate closed by 12 hoursthe Inlet Door Position MonitoringSystem.

SR 3.6.12.2 Verify, by visual inspection, each 7 daysintermediate deck door is closed and notimpaired by ice, frost, or debris.

(continued)

Natts Bar—Unit 1 3.6—32 Amendment 3

Ice Condenser Doors3. 6. 12

SURVEILLANCE REQUIREMENTS (continued)

________________


SR 3.6.12.3 Verify, by visual inspection, each irilet——----NOTEdoor is not impaired by ice, frost, or The 3 monthdebris, performance due

September 9,1996 (per SR3.0.2) may beextended untilOctober 21,1996.

3 monthsduring firstyear afterreceipt oflicense

AND

18 months

SR 3.6.12.4 Verify torque required to cause each NOTEinlet door to begin to open is The 3 month

675 in—lb. performance dueSeptember 9,1996 (per SR3.0.2) may beextended untilOctober 21,1996.

3 monthsduringfirst yearafter receiptof license

AND

18 months

(continued)

Watts Ear—Unit 1 3.6—33 Amendment 3


SURVEILLANCE_REQUIREMENTS__(Continued)

________________


SR 3.6.12.5 Perform a torque test on a sampling of NOTE> 50% of the inlet doors. The 3 month

performance dueSeptember 9,1996 (per SR3.0.2) may beextended untilOctober 21,1996.

3 monthsduringfirst yearafter receiptof license

AND

18 months

SR 3.6.12.6 Verify for each intermediate deck door: 3 monthsduring first

a. No visual evidence of structural year afterdeterioration; receipt of

licenseb. Free movement of the vent

assemblies; and AND

c. Free movement of the door. 18 months

(continued)

Watts Bar-Unit 1 3.6—34 Amendment 3


SURVEILLANCE REQUIREMENTS (Continued)


SR 3.6.12.7 Verify, by visual inspection, each top 92 daysdeck door:

a. IS in place;

b. Free movement of top deck ventassembly; and

c. Has no condensation, frost, or iceformed on the door that wouldrestrict its opening.

Watts Bar—Unit 1 3.6—34a Amendment 3

WBN Emergency P’an Classification Logic EPIP-1Unit 0 Rev. 0035

Page 49 of 51

Attachment 7(Page 6 of 7)

Access restrictions impede operation ofsystems necessary for Safe Operation

the ability to establish ColdShutdown

UNPLANNED increase in Radiation levelswithin the Facility

1TI:fliTtlm

Mode InitiatinglCondition

Refer to “Gaseous Effluents” (7. 1)

Refer to “Gaseous Effluents” (7.1)

All Major damage to Irradiated Fuel, i: Loss ofwater level that has or will uncover IrradiatedFuel outside the Reactor Vessel(1 and2)

1. VALID alarm on 0-RE-90-l 01 B0-RE-90-l 02

0-RE-90-103 or l-RE-90-130/131 or• 1 -RE-90-1 12 1 -RE-90-400

2-RE-90-400

2. (aorb)

a. Plant personnel report damage ofIrradiated Fuel sufficient to rupture FuelRods

b. Plant personnel report water level drophas or will exceed makeup capacitysuch that Irradiated Fuel will beuncovered

All UNPLANNED loss of water level in Spent FuelPool Reactor Cavity Transfer Canal withfuel remaining covered (1 and 2 and 3)

1. Plant personnel report water level drop inSpent Fuel Pool, or Reactor Cavity,Transfer Canal

2. VALID alarm on 0-RE-90-1 02 orD-RE-90-103 1-RE-90-59 1-RE-90-60

3. Fuel remains covered with water.

Mode Ir

Refer to “Fission Product Barrier Matrix” or“Gaseous Effluents” (7.1)

Refer to “Fission Product Barrier Matrix” or“Gaseous Effluents” (7.1)

UNPLANNED increases in Radiation levelswithin the Facility that impedes SafeOperations or establishment or maintenanceof Cold Shutdown(1 cr2)

1.

2.

VALID, area Radiation Monitor readings gsurvey results exceed 15 mrem/hr in theControl Room or CAS

(a and b)

a. VALID area radiation monitor readingsexceed values listed in Table 7-2

b.

See UNUSUAL EVENT Note Below

1. VALID area Radiation Monitor readingsincrease by a factor 1000 over normal levels

Note: In Either the UE 0rALERT EAL, the SEDmust determine the cause of Increase inRadiation Levels and Review OtherINITIATING/CONDITIONS forApplicability (e.g.,a dose rate of 15 mrem/hr in the Control Roomcould be caused by a release associated with aDBA).

ROOM ROOM NAME PROCEDURE

772.0—Al 480V Rx MDV 3d Rm ADl30.2 0.21A

772.0—A2—E 480V Rx MDV AD30.2 C.33d Rm lB (East)

772.0—A2—W 480V Rx MDV Bd Rm A0l-3D.2 C.4I B (West)

772.0—A3 l25V Vital Batt Rm II AOl-30.2 0.5

772.0—A4 125V Vital Batt Rrn I AOI30.2 0.6

772.0—A5 480V Xfmer Rm lB ADl-30.2 0.7

772.0—A6 480V Xfmer Rm IA AOI-30.2 0.8

772.0—A7 Mech Equip Rm ADl-30.2 0.9

‘72.0—A8 5th Vit Batt & Bd Rm AOl-30.2 010

p 772.0—A9 HEPA Filter Plenum Rm AOl-30.2 0,44

ROOM ROOM NAME PROCEDURE

772.0—AlO Mech Equip Rm ADI-30.2 0.11

772.0—All 480V Xfmer Rm 2B AOl-30.2 0.12

772.0—A12 480V Xfmer Rm 2A AOl-30.2 0.13

772.0—A13 125V Vital Batt Rm IV ADl-30.2 0.14

772.0—Al4 125V Vital Batt Rm ill AOl-30.2 C.l5

772.0—A15—E 480V Rx MDV Bd Rm ADI-30.2 0.162B (East)

772.0—A15—W 480V Rx MDV Bd Rm ADl-30.2 0.1723 (West)

772.0—A16 480V Rx MDV Bd Rm AOl-30.2 0.182A

776.0—Al Elev Mach Rrn ADI-30.2 0.60

763.5—Al Ice Equip Rm A0l-30.2 0.45

757.0—A13 (Next Page)

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