Text

Initial Exam 2012-301 Draft RO Written Exam
	ML12194A396
Person / Time
Site:	Harris
Issue date:	07/12/2012
From:	; NRC/RGN-II
To:	; Progress Energy Co
References
	50-400/12-301
	Download: ML12194A396 (166)
	v • d • e

Name: 2012 NRC RO

- Form:

Version: 0

1. 2O12NRCR0001 Given the following plant conditions:

- The plant has just tripped following 100 days of operation at 100% power Which ONE of the following decribes the actions necessary to maintain a constant value of Shutdown Margin following the trip?

A Dilute for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months , then borate for the next 70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months B. Borate for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months , then dilute for the next 70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months C. Dilute for 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months , then borate for the next 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months D. Borate for 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months , then dilute for the next 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months Plausibility and Answer Analysis Reason answer is correct: Following a trip, xenon will require 80 hours9.259259e-4 days 0.0222 hours 1.322751e-4 weeks 3.044e-5 months to reach equilibrium. During this time, xenon will be building in for the first 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months , then decaying to xenon-free conditions over the remaining 70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months .

A. Correct.

B. Incorrect. Plausible because it is the reverse of the correct answer.

C. Incorrect. Xenon will reach pre-trip levels about 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months following a trip, after it has peaked. Since 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months is a number related to xenon transients related to a trip, this number is plausible. 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months represents the remaThder of the time to xenon-free conditions.

D. Incorrect. Combination of errors B and C.

Tuesday, March 20, 2012 2:44:56 PM

2012 NRC RO EPE: 007 Reactor Trip Stabilization Recovery / 1 OO7EK1 .02 Knowledge of the operational implications of the following concepts as they apply to the reactor trip: Shutdown margin (CFR41.8/41.10/45.3)

Importance Rating: 3.4 3.8 Technical

Reference:

Curve B-17-5, Rev 0 References to be provided: None Learning Objective: EOP Users Guide, EOP3-19, Obj. 4.v Question Origin: Bank OIT Development 004 K5.19 1 Comments: 2011 Audit RO-16 Tier/Group: T1G1 Tuesday, March 20, 2012 2:44:56 PM 2

2012 NRC RO

2. 2012 NRC RO 002 - - - -

Given the following plant conditions:

- 1 Sl-3, BIT Outlet Valve, is under clearance for MOV maintenance.

- A Reactor trip and Safety Injection occurred.

- All RCPs are running.

- RCS pressure is 1370 psig and stable.

- SIflowisi5OGPM.

- Containment pressure is 4.5 psig and slowly rising.

- SG pressures are 1020 psig and stable.

- The OAC reports 1 SI-4, BIT Outlet Valve, indicates dual position (red/green light lit).

Which ONE of the following completes the statement below upon transition from PATH-i?

RCPs (1) be tripped AND SGs are (2) for subsequent RCS heat removal.

A (1) should NOT (2) required B. (1) should NOT (2) NOT required C. (1) should (2) required D. (i)should (2) NOT required Tuesday, March 20, 2012 2:44:56 PM 3

2012 NRC RO Plausibility and- Answer Analysis Reason answer is correct: With RCS pressure higher than SG pressure, a secondary heat sink is required. RCPs will be running because SI flow is not adequate to secure them and CS has not occurred.

A. Correct.

B. Incorrect. Plausible because SGs are available and required to remove heat from the RCS.

C. Incorrect. Plausible because A SBLOCA is in progress as indicated by RCS pressure being above RHR Pump shutoff head. SGs would not be required for heat removal if LBLOCA in progress.

D. Incorrect. Plausible because SGs are required.

EPE: 009 Small Break LOCA /3 009EK2.03 Knowledge of the interrelations between the small break LOCA and the following: S/Gs (CFR 41.7/45.7)

Importance Rating: 3.0 3.3 Technical

Reference:

PATH-i, Foldout A, Rev 32 References to be provided: None Learning Objective: FRP-H, Heat Sink Status Tree, EOP3-1 1, Obj. 4.e Question Origin: Bank CIT Development 009 EK2.03 Comments:

Tier/Group: T1G1 Tuesday, March 20, 2012 2:44:56 PM 4

2012 NRC RO 3 2012 NRC R0003 -

Given the following plant conditions:

- The plant is operating at 45% power

- RCP C #1 seal leakoff is 9 gpm and rising Which ONE of the following describes the correct sequence of actions lAW AOP-0l 8, Reactor Coolant Pump Abnormal Conditions?

A. Trip the Reactor, secure RCP C and then implement PATH-i B. Trip the Reactor, implement PATH-i, secure RCP C as time permits C Secure RCP C, shut iCS-437, RCP C #1 Seal Water Return and initiate a plant shutdown lAW GP-006, Normal Plant Shutdown from Power Operation to Hot Standby D. Initiate a plant shutdown lAW GP-006, Normal Plant Shutdown from Power Operation to Hot Standby, secure RCP C and shut 1 CS-437, RCP C #1 Seal Water Return Plausibility and Answer Analysis Reason answer is correct: Per AOP-O 18, with power less than P-8, the RCP is secured, seal return isolated, and commence a plant shutdown.

A. Incorrect. RCP C seal has failed as evidenced by the magnitude of seal leakoff and continuing degrading conditions. This is plausible because when above P-8, the correct action is to trip the reactor, go to Path-i, and secure the RCP as time allows.

B. Incorrect. This would be the correct sequence per AOP-018 if power was greater than P-8. Plausible if applicant does not recognize that power is below P-8.

C. Correct.

D. Incorrect. This is plausible because icontainsns the correct actions in the wrong sequence.

Tuesday, March 20, 2012 2:44:56 PM 5

2012 NRC RO 015 RCP Malfunction / 4 01 5AG2.1 .20 Ability to interpret and execute procedure steps.

Importance Rating: 4.6 4.6 Technical

Reference:

AOP-018, Step 4, 12, 12 RNO, Pages 12, 13, 14, Rev 39 References to be provided: None Learning Objective: Reactor Coolant Pump abnormal conditions, AOP3.18, Obj. 3 Question Origin: Previous Exam - Bank CIT Development 015 AK1 .02 Comments: 2009B NRC RO Tier/Group: T1G1

. Giex the fc1o,,ir plant ccn&ions

- The clant s operating ar4%

- RCP C #1 seal leakoff is Q gpm and rising Which ONE of e tcIc.sn scibes the ccr secuerce of acons ht operacrs wl oerform lAW AOP-c1, Reactor Coolant Pump Abromal Ccnrfrions?

A. Trp the Reactor. secure RC? V and then irrplement PATH-i

. Thp the Peactor. implement PATH-i, secure RCP C as me permits C Secije RCP C, shut T 05-437, PC? V #1 Seal Water Return and initiate a plant slutdo, lAW GP-CO6 Normal Plant Shutdown from Power Operaon :o Hot Standby D initiate a plant shutdown lAW GP-D08, Normal Plant Shutdcwn from Power Operadon to Hot Standby, secure PC? C and shut 105437, RCP VM Seal Waler Return Tuesday, March 20, 2012 2:44:56 PM 6

2012 NRC RO

-4. 201-2 NRC RO 004 Given the following plant conditions:

- The plant is in Mode 5

- RHR A and B trains are in service for Shutdown Cooling

- The OAC reports Fl-605B1, RHR Hx B Header Flow AND PDI-5450B, RHR Pump B Diff Pressures are oscillating.

Which ONE of the following completes the statement below for actions required to be taken lAW AOP-020, Loss of RCS Inventory or Residual Heat Removal while Shutdown?

Stop (1) AND shut (2)

A. (1) RHR Pump B ONLY (2) 1 RH-39 RCS Loop C to RHR Pump B B. (1) BOTH RHR Pumps (2) 1 RH-39 RCS Loop C to RHR Pump B C. (1) RHR Pump B ONLY (2) 1 RH-i, RCS Loop A to RHR Pump A AND 1 RH-39 RCS Loop C to RHR Pump B D (1) BOTH RHR Pumps (2) 1 RH-i, RCS Loop A to RHR Pump A AND 1 RH-39 RCS Loop C to RHR Pump B Tuesday, March 20, 2012 2:44:57 PM 7

2012 NRC RO Plausibility and Answer Analysis -

Reason answer is correct: AOP-020 requfres all running RHR pumps to have normal operating indications and RPV level above 82 below the flange, if not the both RHR pumps are stopped and isolated from the RCS by at least one isolation valve A. Incorrect. Plausible as only the RHR pump B is demonstrating indications of pump cavitation and isolation of the pump maintains the loop suction filled and vented.

B. Incorrect. Plausible as only the RHR pump B is demonstrating indications of pump cavitation and stopping both RHR pumps prevents damage to the non cavitating pump while isolation of the cavitating pump maintains the loop suction filled and vented.

C. Incorrect. Plausible as only the RHR pump B is demonstrating indications of pump cavitation and RHR pumps are able to run on recirculation with the discharge valve shut, candidate may apply this knowledge to the loop suction valve.

D. Correct.

Tuesday, March 20, 2012 2:44:57 PM 8

2012 NRC RO APE: 025 Loss of RHR System 14 025AA2.07 Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System: Pump cavitation (CFR: 43.5 / 45.13)

Importance Rating: 3.4 3.7 Technical

Reference:

AOP-020, Section 3.1 Step #1 RNO, Page 5, Rev #35 References to be provided: None Learning Objective: AOP-020, Loss fo RCS Inventory or Decay Heat Removal while shutdown, AOP3-20, Obj. 3.b and 3.c Question Origin: NEW Comments: Answers came from OIT Exam Bank Q# AOP-020(03) 3 but stem is NEW need to write plausibility and possible new distractors.

Tier/Group: T1G1 Tuesday, March 20, 2012 2:44:57 PM 9

2012 NRC RO

-5. 201 2 NRC RO 005 Given the following plant conditions:

- The plant is operating at 100%

- CCW Pump A in service and CCW pump B in standby.

- A leak occurs in the CCW system causing CCW Surge Tank level to decrease.

The following CCW surge tank level indications exist as leakage from the system continues:

Ll-670A1 SA LI-676A1 SB Time 0933 39% 41%

0935 37% 38%

1003 3% 14%

1005 0% 3%

lAW AOP-014, Loss of Component Cooling Water, what is the EARLIEST time the operating crew is required to place and hold the control switches to STOP for affected CCW pumps?

A. 0933 B. 0935 C 1003 D. 1005 Plausibility and Answer Analysis Reason answer is correct: AOP-014 Section 3.2; Leakage From CCW System step 2 RNO directs the operator to place and hold the control switch for ALL affected CCW Pumps to STOP until CCW header pressure is <52 psig when: ALL operable CCW Surge Tank level indicators are <4% and CCW Pump flow indication is NOT normal.

A. Incorrect. Plausible because when the CCW Surge Tank A level is <40% this will cause the Gross Failed Fuel Detector and RCS sample panel to isolate.

B. Incorrect. Plausible because both A and B level detectors are <40% and either condition will cause the Gross Failed Fuel Detector and RCS sample panel to isolate.

C. Correct.

D. Incorrect. Plausible because both CCW Surge Tank level transmitters are below 4%. Step 2 could be misinterpreted that it takes BOTH operable CCW Surge Tank level indicators to be <4% before the RNO action is taken.

but IA WAOP-014 it takes either operable CCW Surge Tank level indicators to be <4% prior to stopping both of the CCW pumps.

Tuesday, March 20, 2012 2:44:57 PM 10

2012 NRC RO APE: 026 {.oss of Component Cooling Water /8 026AA1 .05 Ability to operate and / or monitor the following as they apply to the Loss of Component Cooling Water: The CCWS surge tank, including level control and level alarms, and radiation alarm (CFR41.7/45.5/45.6)

Importance Rating: 3.1 3.1 Technical

Reference:

AOP-014, Section 3.2, Step 2 RNO, Page #14, Rev #34 References to be provided: None Learning Objective: AOP-014, Loss of Component Cooling Water, AOP3-14 Obj. 3 Question Origin: Bank LORNRCBNKAOP-3.142 Comments: Revised answer to D to agree with AOP-01 4 revisions since the question was originally written Tier/Group: T1G1 Tuesday, March 20, 2012 2:44:57 PM 11

2012 NRC RO

- 6. 2012 NRC RO 006 -

Given the following plant conditions:

- The plant is operating at 100%

- The OAC reports to the CRS that PRZ pressure is 2260 psig and slowly rising

- The crew enters AOP-01 9, Malfunction of RCS Pressure Control

- The OAC identifies that the PRZ group A backup heaters are ON and attempts to secure the heater group from the MCB have failed lAW AOP-019, (1) what action should be taken to control PRZ pressure AND (2) at what nominal pressure will the PRZ PORVs receive an open signal?

A. (1) an operator should be dispatched to locally open the malfunctioning heater breaker (2) 2315 psig B. (1) take manual control of the PRZ spray valves and fully open the valves (2) 2315 psig C (1) an operator should be dispatched to locally open the malfunctioning heater breaker (2) 2335 psig D. (1) take manual control of the PRZ spray valves and fully open the valves (2) 2335 psig Plausibility and Answer Analysis Reason answer is correct: Per AOP-01 9 it pressurizer heater fault to operate from the MCB then the operator is directed to cycle the heater breaker locally to control pressurizer pressure. Pressurizer PORV open setpoint is 2335 psig A. Incorrect. Plausible because the action to control pressure are correct, but the pressure for which the PORV is designed to shut as pressure is relieved B. Incorrect. Plausible as this action will reduce the pressure, but is not directed per A OP-U 19 because the PRZ Spray Valves are functioning properly and manual control is not desired and pressure for which the PORV is designed to shut as pressure is relieved C. Correct.

D. Incorrect. Plausible as this action will reduce the pressure, but is not directed per A OP-U 19 because the PRZ Spray Valves are functioning properly and manual control is not desired.

Tuesday, March 20, 2012 2:44:57 PM 12

2012 NRC RO 027 P essurizerPressure CorTtroI System Malfunutian/3 027AG2.4.35 Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

(CFR: 41.10/43.5/45.13)

Importance Rating: 3.8 4.0 Technical

Reference:

AOP-01 9, Step 15 and 1 6.b RNO, Page 11, and Attachment 1 page 2 of 2, Rev 22 References to be provided: None Learning Objective: AOP-01 9, Malfunction of Reactor Coolant System Pressure Control, AOP3-1 9 Obj. 3.a & Obj. 6 Question Origin: New Comments:

Tier/Group: T1G1 Tuesday, March 20, 2012 2:44:57 PM 13

2012 NRC RO 7.2o12NRQoo7 Given the following plant conditions:

- The plant was operating at 100%

- A Tube Rupture occurred on the SG A

- Offsite power was lost

- The crew implemented PATH-i and transitioned to PATH-2 then transitioned to EPP-017, Post-SGTR Cooldown Using Backfill

- A RCS cooldown on natural circ is now required lAW EPP-017, which ONE of the following is the preferred order of dumping steam from the intact SGs to accomplish the cooldown?

1) SG PORV controlled at MOB

2) Locally operate SG PORVs

3) Condenser steam dump

4) TDAFW pump A. 1,2,3 B. 3,4,2 Cv 1,2,4 D. 3,1,4 Plausibility and Answer Analysis Reason answer is correct: The Condenser steam dumps will NOT be available since 0-9 (Condenser interlock) is not functional without any Circ Water pump breakers closed (due to loss of offsite power).

A. Incorrect. Plausible because operating the SG PORVs from the MCB is first and if they did not operate from the MCB one could assume that local operation would be the second choice. The Condenser steam dumps would not be available due to the loss of C-9 but would be a first choice IA W EPP-O1 7 if they were available.

B. Incorrect. Plausible if the candidate believes that the SG PORVs cannot be controlled at all from the MCB but lAW EPP-OO1 Note prior to step 28, even during a loss of all AC power the C SG PORV can be controlled from the MCB for a limited number of operations.

C. Correct.

D. Incorrect. Plausible since the three choices do not include the non-available Condenser steam dumps but the order that the list is in is not correct.

Tuesday, March 20, 2012 2:44:57 PM 14

2012 NRC RO EPE: O8 Steam Qnratçr Tvb ptur (SQTR) /3 038EA1 .33 Ability to operate and monitor the following as they apply to a SGTR: Use of S/G for natural circulation cooldown (CFR 41.7/ 45.5 / 45.6)

Importance Rating: 4.4 4.3 Technical

Reference:

EOP-EPP-017, Step 1O.b, Page 20, Rev. 14 References to be provided: None Learning Objective: EPP-017, 018 & 019, Post SGTR Cooldown, EOP3-4 Obj. 4.d Question Origin: New Comments: Original K/A was 038EA1 .40 but was replaced on 11/3/2011 by Richard Baldwin at Archie Luckys request.

(Unable to write a question to the original K/A).

Tier/Group: T1G1 Tuesday, March 20, 2012 2:44:57 PM 15

2012 NRC RO 8.2012 NRCRO 008 Given the following plant conditions:

- FRP-H.1, Response to a Loss of Secondary Heat Sink, is being implemented

- RCS bleed and feed has been initiated

- Subsequently, Auxiliary Feedwater (AFW) capability is restored

- All SGs are completely dry and depressurized Under these conditions, which ONE of the following describes the strategy used to re-establish Feedwater?

A. Feed ONLY one (1) SG to ensure RCS cooldown rates are established within Technical Specification limits B Feed ONLY one (1) SG to minimize excessive thermal stresses to SG components C. Feed ALL SGs to establish subcooled conditions in the RCS as soon as possible D. Feed ALL SGs to allow termination of RCS bleed and feed as soon as possible Plausibility and Answer Analysis Reason answer is correct: One SG is fed at minimal rate to minimize thermal shock and potential damage to the SG tubesheet when SGs are hot and dry. After feeding a minimal rate, flow may be raised later. One at a time to determine if tube leakage is occurring A. Incorrect. Plausible as operator is cautioned to control feedwater rates to prevent excessive cooldown for enhanced plant control not to comply with tech spec requirements.

B. Correct.

C. Incorrect. Plausible as the operator is allowed to depressurize multiple steam generators to allow condensate flow to be used for recovery of heat sink may be confused with actions to max rate cooldown during SGTR events D. Incorrect. Plausible as the operator is allowed to depressurize multiple steam generators to allow condensate flow to be used for recovery of heat sink.

Tuesday, March 20, 2012 2:44:57 PM 16

2012 NRC RO APE: 054 LQSs of Main Feedwater (MFW) /4 054AK1 .02 Knowledge of the operational implications of the following concepts as they apply to Loss of Main Feedwater (MEW): Effects of feedwater introduction on dry S/G (CER41.8/41.10/45.3)

Importance Rating: 3.6 4.2 Technical

Reference:

FRP-H.1 Pg 57 Rev. 27, WOG background document FR-H.1 pg5l References to be provided: None Learning Objective: Heat Sink Status Tree, EOP3.1 1 Obj. 4.c Question Origin: Bank OIT Development 054 AK1 .02 Comments: 2006 NRC RO Tier/Group: T1G1 Tuesday, March 20, 2012 2:44:57 PM 17

2012 NRC RO 9.. 21)12 NRC RL) 009 Given the following plant conditions:

- The plant was operating at 100% when a loss of off-site power occurred

- EDG A fails to start

- EDG B output breaker closes, but trips open

- Ten minutes later, the following plant conditions exist:

RCS pressure is 2235 psig and stable RCS Loop THOT is 596°F in all 3 loops and lowering RCS Loop TCOLD is 559°F in all 3 loops and lowering Core exit TCs indicate approximately 600°F and lowering SG pressures are approximately 1108 psig and stable Which ONE of the following completes the statement below describing current plant conditions?

Natural circulation (1) exist AND RCS heat removal (2)

A. (1)doesnot (2) must be established by opening the Condenser steam dumps B. (1)does (2) is being maintained by Condenser steam dumps C. (1)doesnot (2) must be established by opening the SG PORVs D (1)does (2) is being maintained by SG PORVs Tuesday, March 20, 2012 2:44:57 PM 18

2012 NRC RO Plausibility and Answer Analysis Reason answer is correct: Natural Circulation is establishing, Hot leg and Core Exit Thermocouple temperatures are lowering. Cold leg tempertures are lowering, but are not at the saturation temperature for the PORVs opening pressure causing them to open to maintain Natural circulation.

A. Incorrect. Plausible because the Condenser steam dumps are normally used following a trip, but would not be available due to the LOSP. N. C. is occurring.

B. Incorrect. Plausible because the Condenser steam dumps are normally used following a trip, but would not be available due to the LQSP.

C. Incorrect. Plausible because SG pressure is stable just above PORV setpoint and temperatures stable or lowering, heat removal is occurring.

D. Correct.

Tuesday, March 20, 2012 2:44:57 PM 19

2012 NRC RO EPE: 055 Loss of Offsite and Onsite Power(Station Blackout) /6 055EK1 .02 Knowledge of the operational implications of the following concepts as they apply to the Station Blackout: Natural circulation cooling (CFR 41.8/41.10/45.3)

Importance Rating: 4.1 4.4 Technical

Reference:

EPP-004, Step 17.d RNO, Page 30, Rev 24 References to be provided: Steam Tables Learning Objective: EPP-001, 002 & 003, Loss of All AC Power and recovery WI or w/o Safety Injection, EOP3-7 Obj. 6 Question Origin: Bank CIT Development 056 G2.1 .2 Comments:

Tier/Group: T1G1 Tuesday, March 20, 2012 2:44:57 PM 20

2012 NRC RO

.10o42NRcRo-o1o -

Given the following plant conditions:

- The plant is operating at 100%

- A lightning strike results in a bus differential lockout on the South 230 kV Bus

- Breaker 52-7, Generator to South Bus, fails to open

- Annunciator ALB-01 11-4, Reactor Trip RCP Bus/P7 Undervoltage is received Which ONE of the following identify the alarms on ALB-022 that are consistent with a loss of offsite power?

1) 1-2, Start Up Xfmr-A Both 230kv Bkrs Open

2) 2-1, Start Up Xfmr-A Bkrs 52-2/3 Mech Trouble

3) 8-1, Start Up Xfmr-B Bkrs 52-13/14 Mech Trouble

4) 9-2, Start Up Xfmr-B Both 230kv Bkrs Open A 1,4 B. 1,2 C. 2,3 D. 3,4 Plausibility and Answer Analysis Reason answer is correct: SUT A is supplied offsite power from the 230KV Bus via Breakers 52-2 or 52-3, SUT B is supplied offsite power from the 230KV Bus via Breakers 52-13 or 52-14.

Alarms 1 and 4 indicate that both SUT have no power from offsite sources.

A. Correct.

B. Incorrect. Plausible due to this alarm affecting the same breakers, but Mechanical Trouble occurs due to low gas pressure for the breaker and should not be in for LOOSP.

C. Incorrect. Plausible due to this alarm affecting the same breakers, but Mechanical Trouble occurs due to low gas pressure for the breaker and should not be in LOOSP.

D. Incorrect. Plausible due to this alarm affecting the same breakers, but Mechanical Trouble occurs due to low gas pressure for the breaker and should not be in for LOOSP.

Tuesday, March 20, 2012 2:44:57 PM 21

2012 NRC RO APE: 056 Loss of Offsite Power/

056AG2.4.46 Ability to verify that the alarms are consistent with the plant conditions.

I (CFR: 41.10/43.5/45.3/45.12)

Importance Rating: 4.2 4.2 Technical

Reference:

ALB-022, Window 1-2, Window 9-2, Page 5, 58, Rev 63 References to be provided: None Learning Objective: Off Site Power Obj. 9 Question Origin: New Comments:

Tier/Group: T1G1 Tuesday, March 20, 2012 2:44:57 PM 22

2012 NRC RO 1I.2QI2NRCRL1OH -

Given the following plant conditions:

- The plant is operating at 100%

- PRZ Level Control is selected to position 459/460

- Instrument Bus S-Il is lost

- The crew is implementing AOP-024, Loss of Uninterruptible Power Supply Which ONE of the following completes the statements below?

Letdown flow will be isolated because (1) went SHUT.

The OAC should control PRZ level in manual with (2) to minimize the level increase with letdown isolated.

Av (1) 1CS-1, Letdown Isolation LCV-460 (2) FK-122.1, Charging Flow B. (1) 1 CS-i, Letdown Isolation LCV-460 (2) LK-459F, PRZ Level Controller C. (1) 1 CS-2, Letdown Isolation LCV-459 (2) FK-122.i, Charging Flow D. (1) 1CS-2, Letdown Isolation LCV-459 (2) LK-459F, PRZ Level Controller Plausibility and Answer Analysis Reason answer is correct: Instrument Bus SII supplies Pressurizer Level channel 460 and the affected of losing power is the channel failing low, which causes the its associated letdown isolation valve 1 CS-i to shut. With letdown isolated to reduce charging flow to the minimum amount the FK-122 must be placed in manual. This is required because the minimum flow while in automatic control is 15 gpm.

A. Correct.

B. Incorrect. Plausible since 1 Ca-i will shut, but the LK-459F controller will not be used due to limited control with FK- 122.1 in automatic.

C. Incorrect. Plausible since Charging flow will be controlled with FK-122. 1, but 1CS-2 will remain OPEN since it is controlled by LT-459.

D. Incorrect. Plausible since Letdown flow will be lost due to 1 CS-i shutting, not 1 CS-2, but the LK-459F controller will not be used due to limited control with FK- 122.1 in automatic.

Tuesday, March 20, 2012 2:44:57 PM 23

2012 NRC RO APE: 057 Loss of Vital AC Electricalinstrument Bus 16 057AK3.01 Knowledge of the reasons for the following responses as they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital ac electrical instrument bus (CFR 41.5,41.10/45.6/45.13)

Importance Rating: 4.1 4.4 Technical

Reference:

AOP-024-BD, 1.0 discussion and section 3.1 step 3, page 5 and 7, Rev 15 References to be provided: None Learning Objective: AOP-024, Loss of Uniterruptible Power Supply, AOP3-24 Obj. 4 Question Origin: New Comments: Need to talk with Rick Baldwin for concurrence to use AOP-024 in place of EOPs for K/A match Tier/Group: T1G1 Tuesday, March 20, 2012 2:44:57 PM 24

2012 NRC RO i22o12NRcRoo12 Given the following plant conditions:

- The plant is in Mode 3

- MDAFW Pump A and B are in service feeding all 3 SGs

- 125 VDC control power to the MDAFW Pump B is lost Which ONE of the following completes the statement below?

MDAFW Pump B breaker indication on the MCB is (1) AND the pump will (2) ?

A. (1)available (2) remain running B (1) lost (2) remain running C. (1)available (2) trip D. (1)lost (2) trip Plausibility and Answer Analysis Reason answer is correct:125 VDC control power is supplied to the breaker cubicle to provide remote indication of breaker status on the MCB and allows for the operation of the breaker from the MCB. With the loss of control power the indication on the MCB is not availalbe and the ability to remotely operate the breaker is lost as well.

A. Incorrect. Plausible because the breaker will remain closed for the MDAFW pump B and if the power supply that is loss were the 125 VAC UPS then the indications for the breaker would still be available.

B. Correct.

C. Incorrect. Plausible because the 6.9KV bus undervoltage will result in a safety bus B being stripped which will trip the breaker open automaitically and the MCB indications will remain available D. Incorrect. Plausible because the breaker MCB indication is lost when smaller 480 VAC MCC trip open.

Tuesday, March 20, 2012 2:44:57 PM 25

2012 NRC P0 AP:058LossofDCPower/ -

058AA2.O3Ability to determine and interpret the following as they apply to the Loss of DC Power: DC loads lost; impact on ability to operate and monitor plant systems (CFR: 43.5 /45.13)

Importance Rating: 3.5 3.9 Technical

Reference:

Drawing 2166-B-401-1922, Rev 12 References to be provided: None Learning Objective: DC Power Obj. 9 Question Origin: Bank OIT Development 058 AA2.03 Comments: 2007 Audit P0 Tier/Group: T1G1 Tuesday, March 20, 2012 2:44:57 PM 26

2012 NRC RO 1-32o1zNRcgooi Given the following plant conditions:

- The plant is operating at 100%

The following MCB indications exist:

Time 1135 1138 1140 ESW Header A PI-9101A SA, A Disch Press 88 psig 86 psig 94 psig Fl-9101A1 SA, A Hdr Flow 14550 gpm 11820 gpm 13390 gpm ESW Header B Pl-9101B SB, B Disch Press 89 psig 85 psig 81 psig Fl-9101B1 SB, B Hdr Flow 15725 gpm 18550 gpm 13600 gpm NSW Header P1-9302.1, Disch Hdr Press 82 psig 80 psig 112 psig Fl-9304, WPB SW Flow 9800 gpm 8250 gpm 11800 gpm Fl-9276, Cnmt Coil Units SW Return 1840 gpm 1560 gpm 2900 gpm AOP-022, Loss of Service Water has been entered and both ESW pumps have been started.

Which ONE of the following completes the statements below?

The Service Water line rupture is located in the (1) ESW Header. lAW AOP-022 to isolate the ESW Header leak the operator will be directed to place and hold (2) control switch(es) to STOP.

A. (1)A (2) the ruptured header ESW Pump B. (1)A (2) both ESW Pump A and B C (1)B (2) the ruptured header ESW Pump D. (1)B (2) both ESW Pump A and B Tuesday, March 20, 2012 2:44:57 PM 27

2012 NRC RO Plausibility anctAswerAn&lysis -

Reason answer is correct: The ruptured ESW or NSW header is typically indicated by lower pressure and higher flow in the same header than those existing prior to the breach. By utilizing the data trends the candidate should be able to identify the ruptured header as the B header. IAWAOP-022 to isolate the rupture ESW Header the operator is directed to place and hold the ruptured header ESW Pump control switch to STOP.

A. Incorrect. Plausible because the decreasing pressure and flow indications on A ESW header could lead someone to believe the rupture is on the A line.

The second part of the answer is correct.

B. Incorrect. Plausible because the decreasing pressure and flow indications on A ESW header could lead someone to believe the rupture is on the A line.

The second part of the answer is plausible if the system were crosstied but the ESW has two seperate trains.

C. Correct.

D. Incorrect. The first part is correct. The second part of the answer is plausible if the system were crosstied but the ESW has two seperate trains.

Tuesday, March 20, 2012 2:44:57 PM 28

2012 NRC P0 APE: 062 Loss of Nuclear Service Water /4 062AA2.OlAbility to determine and interpret the following as they apply to the Loss of Nuclear Service Water: Location of a leak in the SWS (CFR: 43.5 / 45.13)

Importance Rating: 2.9 3.5 Technical

Reference:

AOP-022 Section 3.0, Steps 8 and 10, Pages 8 and 9, Rev. 34 References to be provided: None Learning Objective: AOP-022, Loss of Service Water, AOP3-22 Obj. 4 Question Origin: New Comments:

Tier/Group: T1G1 Tuesday, March 20, 2012 2:44:58 PM 29

2012 NRC RO 14.2ol2NRcRcwI4 - -

Given the following plant conditions:

- The plant is operating at 100%

- IA header pressure lowers as indicated below:

Time IA Header Pressure 0800 85 psig 0805 70 psig 0810 60 psig 0815 45 psig 0820 35 psig Which ONE of the following completes the statements below?

At (1) an auto shut signal to the Main Feed Reg valves is generated. The reason these valves have a back up air supply in the form of air accumulators is to (2)

A. (1) 0800 (2) provide motive force to shut the valves B. (1) 0800 (2) provide the ability to open the valves for a short period of time following loss of air C (1) 0810 (2) provide motive force to shut the valves D. (1) 0810 (2) provide the ability to open the valves for a short period of time following loss of air Tuesday, March 20, 2012 2:44:58 PM 30

2012 NRC RO Plausibility and Answer AnalysLs - -

Reason answer is correct: During a loss of IA when pressure is < 60# the valves receive an auto shut signal. The motive force to shut each valve is provided by air accumulators for each valve. The reason the air accumulators are neccessary is the valves would fail in the last position if there was not a motive force to shut them.

A. Incorrect. Plausible because at 85 psig it has been determined that spurious valve actuations will begin to occur on the Letdown system due to air pressure not being able to overcome spring pressure to maintain the orifice isolation valve open. The second part of the answer is correct.

B. Incorrect. Plausible because at 85 psig it has been determined that spurious valve actuations will begin to occur on the Letdown system due to air pressure not being able to overcome spring pressure to maintain the orifice isolation valve open. The second part of the answer is plausible because other plant valves have hydraulic accumulators to allow operation during a loss of power C. Correct.

D. Incorrect. Plausible since the pressure is correct and because other plant valves have hydraulic accumulators to allow operation during a loss of power.

Tuesday, March 20, 2012 2:44:58 PM 31

2012 NRC RO APE: 065 Loss oflnstrument Air/B 065AK3.04 Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air: Cross-over to backup air supplies (CFR 41.5,41.10 / 45.6 / 45.13)

Importance Rating: 3.0 3.2 Technical

Reference:

AOP-01 7, Note prior to Step 1, Page 4, Rev 32 References to be provided: None Learning Objective: Condensate and Feedwater Obj. 8.j Question Origin: New Comments: The HNP IA system is not designed to have a backup air supply system that has cross over capability (like some plants with Service Air compressors). The closest thing to this is the backup air supplies on the Main Feed Reg Valves which is in the form of air accumulators. When IA pressure decreases to <60 psig the air in the accumulator provides motive force to shut the valve.

Without the accumulators the valve would fail as is (last position).

Tier/Group: T1G1 Tuesday, March 20, 2012 2:44:58 PM 32

2012 NRC RO l&2OI2NRcROO15-. - -

Given the following plant conditions:

- The plant is operating at 100%

- Annunciator ALB-22-5-3, GENERATOR VOLTAGE BALANCE RELAY OPERATED alarms

- The voltage regulator remains in AUTO

- MW and MVAR indications are erratic Which ONE of the following actions should be taken for these conditions?

A. Null the Voltage Regulator Output Voltage with the Generator Base Adjuster. If the Base Adjuster does not work, Trip the Reactor and enter PATH-i B. Adjust the Generator Output Voltage to 22KV with the Generator Voltage Adjuster switch. If the Voltage Adjuster does not work, Trip the Reactor and enter PATH-i C. Place the Generator Voltage Regulator switch to OFF and use the Generator Voltage Adjuster switch to restore Main Generator voltage D Operate the Generator Base Adjuster switch to null the Regulator Output Balance Voltage as close to zero as possible then place the Generator Voltage Regulator in manual by positioning the control switch to TEST Plausibility and Answer Analysis Reason answer is correct: Per APP-ALB-022 5-3, if the Generator voltage regulator is in Auto the Generator base adjuster is used to null the Reg output balance The generator voltage regular is then oplaced in test A. Incorrect. Plausible because the base adjuster is used for a bumpless transfer voltage regulator control and AOP-006 for turbine/generator trouble provides trip criteria when exceeding limits on the turbine.

B. Incorrect. Plausible because the voltage regulator is normally adjusted using this switch and AOP-006 for turbine/generator trouble provides trip criteria when exceeding limits on the turbine.

C. Incorrect. Plausible because during normal system shutdown the Generator Voltage Regulator is placed in the OFF position and the Generator Voltage Adjuster is used to null the regulator output balance meter D. Correct.

Tuesday, March 20, 2012 2:44:58 PM 33

2012 NRC RO APE: 077 Generator Voltage and Electric Grid DisturbanGes /

077AA1 .O3Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances: Voltage regulator controls (CFR: 41.5 and 41.10/45.5, 45.7, and 45.8)

Importance Rating: 3.8 3.7 Technical

Reference:

APP-ALB-022-5-3, Page 34, Rev 59 References to be provided: None Learning Objective: Main Generator Obj. 3.c Question Origin: Bank CIT Development GEN-R4 3 Corn rn ents:

Tier/Group: T1G1 Tuesday, March 20, 2012 2:44:58 PM 34

2012 NRC RO 162oi21,cRou16 Given the following plant conditions:

- A Reactor Trip and Safety Injection have occurred from 100% power

- The crew has transitioned to EPP-013, LOCA Outside Containment

- 1 RH-i and 1 RH-2, RCS Loop A to RHR Pump A-SA, BOTH indicate partially OPEN Which ONE of the following identifies (1) the action required to allow shutting 1 RH-i and 1 RH-2 from the MCB AND (2) the parameter used in EPP-01 3 to determine if this action has isolated the break?

A. (1) the control power switch must be turned ON (2) PRZ level increasing B. (1) the control power switch must be turned ON (2) RCS pressure increasing C. (1) the breakers for 1 RH-i and i RH-2 must be CLOSED (2) PRZ level increasing D (1) the breakers for 1 RH-i and 1 RH-2 must be CLOSED (2) RCS pressure increasing Plausibility and Answer Analysis Reason answer is correct:The breakers are NOT normally powered. Closing breakers is correct. RCS pressure increasing is correct.

A. Incorrect. The control power switch is plausible because other valves used for this alignment have a control power switch to prevent operation. PAZ level increasing is plausible because with the leak isolated, inventoiy would be recovered but some leak locations will result in increasing level so the EOP network does not use level.

B. Incorrect. The control power switch is plausible because other valves used for this alignment have a control power switch to prevent operation. RCS pressure increasing is correct.

C. Incorrect. The breakers are NOT normally powered. Closing breakers is correct.

PRZ level increasing is plausible because with the leak isolated, inventory would be recovered but some leak locations will result in increasing level so the EOP network does not use level D. Correct.

Tuesday, March 20, 2012 2:44:58 PM 35

2012 NRC RO E04 +.DCA Outside Containment / 3 WEO4EK2.i Knowledge of the operational implications of the following concepts as they apply to the (LOCA Outside Containment) Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41 .8/41.10, 45.3)

Importance Rating: 3.5 3.9 Technical

Reference:

EPP-013 pp 3 and 5, Rev 10 OP-ill ppi25andi26,Rev54 References to be provided: None Learning Objective: EPP-010, 011, 012 & 013, Safety Injection Recirculation, Loss of Recirc and LOCA outside containment, EOP2-3 Obj. 2 Question Origin: Bank OIT Development E04 EK2.i Comments: Previous Exam 2009B NRC RO Tier/Group: T1G1 Tuesday, March 20, 2012 2:44:58 PM 36

2012 NRC RO 17.212NRcRoo17 Given the following plant conditions:

- The plant was operating at 100% power

- MDAFW pump A is out of service

- A manual Reactor Trip was initiated due to a loss of both MFPs

- The TDAFW pump tripped after starting

- MDAFW flow control valves are full open

- Containment pressure is 3.5 psig Which ONE of the following completes the statement below concerning the sets of conditions that would indicate that an entry into FRP-H.1, Response to Loss of Secondary Heat Sink is required?

Total AFW flow is (1) AND (2)

A (1)19OKPPH (2) All SG NR levels at 38%

B. (1)22OKPPH (2) A and B SGs NR Levels are at 24%, C SG NR level is at 42%

C. (1)19OKPPH (2) A and B SGs NR Levels are at 24%, C SG NR level is at 42%

D. (1)22OKPPH (2) All SG NR levels at 38%

Plausibility and Answer Analysis Reason answer is correct: Heat Sink CSFST indicates a loss of heat sink if AFW flow is less than 210 KPPH AND ALL SG NR levels are less that 40% with adverse containement conditions.

A. Correct.

B. Incorrect. Plausible since the heat sink woulld be in a degraded condition even with one SG greater than 40% level and AFW flow greater than 210 KPPH.

C. Incorrect. First part is correct. The second part is plausible since the heat sink would be in a degraded condition even with 1 SG greater than 40%.

D. Incorrect. The first part is plasuible because AFW flow rate of2lO KPPH could result in degraded heat sink condition. The second part is correct.

Tuesday, March 20, 2012 2:44:58 PM 37

2012 NRC RO E0&toss of Secondary Heat Sink! 4 WEO5EK2.2 Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following: Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

(CFR: 41.7/ 45.7)

Importance Rating: 3.9 4.2 Technical

Reference:

EOP-CSFST, pp 2, Rev 9 References to be provided: None Learning Objective: Heat Sink Status Tree, EOP3-1 1 Obj. 4 Question Origin: Bank CIT Development E05 EK2.2 Comments: 2009B NRC RO question with minor formating change Tier/Group: T1G1 Given the fcfioMng part cdrfons

- Th plant was cperatng at 1)0% power A MDAFW pump ts out of sarice A rranual Reactor Tro was initiated due to a oss of both MFPs The TDAFP AFW pi.rnp zrioed after startitg

- AFW flaw control vaNes are full open

- Containment Dressure is 3.5 seig Which ONE of the oIlctn sets of conditions would indicate that an enliy pta FRP-4-Lt, Response to Loss of Secondwy Heat Sink is eqired A Total AFW flaw is 191) KPPI-l All .5 NP tevels at 35%

B. Total AFW flow is 221) KPPH A and 3 SOs NP Levels are at 24%, C SO NP ieel is at 42%

C. TotsIAFW flow is 190 KPPH A andS SOs NP Levels are at 24%, C SO NRlevel is at 2%

4 D. Total AFW flow is 220 KPPH All SO NR eveis at 3B%

Tuesday, March 20, 2012 2:44:58 PM . 38

2012 NRC RO l82o12NRcRcIo1 -

Which ONE of the following describes (1) the reason AND (2) the requirements for depressurizing the RCS lAW EPP-01 2, Loss of Emergency Coolant Recirculation?

Ab/ (1) To minimize RCS break flow; (2) Depressurize the RCS to achieve RCS subcooling between 10°F and 20°F

[40°F and 50°F];

B. (1) To increase CSIP injection flow rate; (2) Depressurize the RCS to achieve RCS subcooling between 10°F and 20°F

[40°F and 50°F];

C. (1) To minimize RCS break flow; (2) Depressurize the RCS to maintain RCS subcooling just above 60°F [90°F];

D. (1) To increase CSIP injection flow rate; (2) Depressurize the RCS to maintain RCS subcooling just above 60°F [90°F];

Plausibility and Answer Analysis Reason answer is correct: The objective of the loss of ECR guideline is threefold: 1) to continue attempts to restore emergency coolant recirculation capability, 2) to delay depletion of the RWST by adding makeup fluid and reducing outflow, and 3) to depressurize the RCS to minimize break flow and cause SI accumulator injection.

A. Correct.

B. Incorrect. Plausible because depressurizing will increase the CSIP injection flow rate but the reason to depressurize is to minimize break flow. The second part of the answer is correct.

C. Incorrect. The first part of the answer is correct. The second part is plausible because the values given can be found for minimum subcooling requirements in EPP-012 for SI termination critela.

D. Incorrect. Plausible because depressurizing will increase the CSIP injection flow rate but the reason to depressurize is to minimize break flow. The second part is plausible because the values given can be found for minimum subcooling requirements in EPP-012 for SI termination criteia.

Tuesday, March 20, 2012 2:44:58 PM 39

2012 NRC RO Eli Loss of Emergency Coolant ReeFreulation /4 WE1 1 EK3.2 Knowledge of the reasons for the following: Normal, abnormal and emergency operating procedures associated with (Loss of Emergency Coolant Recirculation).

Importance Rating: 3.5 4.0 Technical

Reference:

ECA-1.1 (EPP-012) Background HP-Rev.2 References to be provided: None Learning Objective: EPP-Ol 0, 011, 012 & 013, Safety Injection Recirculation, Loss of Recirc and LOCA outside containment, EOP2-3 Obj. 3.g Question Origin: Bank CIT Development Eli EK3.3 Comments: 2008 NRC RO, changed distractors C and D values to 60°F [90°F] which is SI termination criteria subcooling values Tier/Group: T1G1 Tuesday, March 20, 2012 2:44:58 PM 40

2012 NRC RO

19. 2O-I2NRCROo19 - -

Given the following plant conditions:

Time = 1200

- Reactor Power is 89% and stable

- Tavg Tref deviation is 0°F and stable

- PRZ level is 55% and stable

- Control Bank D DRPI indicates 198 steps Time =1202

- Reactor Power is approximately 90% and rising (no load change is in progress)

- Tavg Tref deviation is approximately +2°F and rising

- PAZ level 56% and rising

- PAZ spray valves have throttled open

- Control Bank D DRPI indicates 204 steps and stepping out at 8 steps per minute Which ONE of the following describes (1) the event in progress AND (2) the FIRST action that must be performed lAW AOP-001, Malfunction of Rod Control and Indication System?

A. (1) Selected first stage pressure channel high failure (2) Check that less than 2 control rods are dropped B. (1) Selected first stage pressure channel high failure (2) Place the Rod Bank Selector Switch to MAN C (1) Continuous spurious control bank withdrawal (2) Check that less than 2 control rods are dropped D. (1) Continuous spurious control bank withdrawal (2) Place the Rod Bank Selector Switch to MAN Tuesday, March 20, 2012 2:44:58 PM 41

2012 NRC RO Plausibility and AnswerAnalysis Reason answer is correct: During Control rod withdrawl Tavg will increase due to the addition of positive reactivity. The stem of the question states that intial DRPI is 198 steps and final position is 204 steps. Therefore a Control Rod withdrawl is taking place. With a +2°F Tavg Tref deviation the Control rods in auto should be stepping in.

Immediate actions for AOP-001 are to check that < 2 rods have dropped and then place rods in Manual and verify that rod motion is stopped.

A. Incorrect. Plausible because control rods are stepping out which indicated that 1st stage pressure is higher than Tavg, but the power rate mismatch circuit would demand rods step at a rate greater than 8 steps per mm.

B Incorrect. Plausible because control rods are stepping out which indicated that 1st stage pressure is higher than Tavg, but the power rate mismatch circuit would demand rods step at a rate greater than 8 steps per mm. Rod control is placed in manual after checking <2 rods have dropped C. Correct.

D. Incorrect. Plausible because rod control is placed in manuai but only after checking

<2 rods have dropped APE: 001 Continuous Rod Withdrawal / 1 OO1AA1 .07 Ability to operate and / or monitor the following as they apply to the Continuous Rod Withdrawal: RPI (CFR 41.7/45.5 / 45.6)

Importance Rating: 3.3 3.1 Technical

Reference:

AOP-001 immediate actions step 1, Rev 36 References to be provided: None Learning Objective: AOP-001, Malfunction of Rod Control and Indication, AOP3-1 Obj. 4 Question Origin: Bank OIT Development 001 AK2.01 2011 NRC RO-19 Comments: Modified 2011 RO question by changing stem to make answer C correct instead of answer D Original K/A was 001 AA1 .03 but was replaced on 11/3/2011 by Richard Baldwin at Archie Luckys request.

(Unable to write a question to the original K/A).

Tier/Group: T1G2 Tuesday, March 20, 2012 2:44:58 PM 42

2012 NRC RO OriginaIQuestion - -

1. Given the toMr plant ccndhionsc Time= 1000

- Resotor Power is 75% and stable

- Tavg Iref deviation is 0F and stable

- PZR level is 51% and stable

- Ccrhrol Bark 0 step counters are at 185 Time 1002 Reactor Power is approxirnate4y 75% and rising no load thange is in prcress)

- Tavg Tref deviaticn is apprctdrrately +2F ar4 hsirg PZR 1ev-el 52% and rising

- PZR spray valves have throttled coen Ccrhrcl Bank 0 step counters are at 174 steps and stepping out at 8 steps per minute Which ONE f the foilctig cescribes (ithe event in progress AND C2)the FIRST action that n,ust cc perfomied lAW AOP-CJ I Maffunction of Pod Control and Indicator System?

A. 1eelected first inane pressure channel high failure

2) Tip the Reactor and go to OP PATH-I, Reactor Trip or Safety Injection B. 1 selected first stage pressure channel high failure Place the Rod Bank Selector Switch to MAN C. (1 Continuous Spurics Control Bank WiThdrawal Trip the Reactor and go to EOP PATH-I Reactor Trip or Safety tnection D (1 Continuous Spunous Control Bank Withdrawal Place the Rod Banl Selector Swi1h to MAN.

Tuesday, March 20, 2012 2:44:58 PM 43

2012 NRC RO 20.2oI2NRcRo2o - - -

Given the following plant conditions:

- An irradiated Fuel Assembly was being withdrawn from the core when it was determined that the assembly was damaged.

- Containment Area Radiation is rising but monitors are NOT in alarm status.

- AOP-013, Fuel Handling Accident, has been entered.

Which ONE of the following describes the FIRST action required lAW AOP-013?

A. Evacuate Containment B. Initiate Containment Closure C. Place the affected fuel assembly on the floor of the Lower Refueling Cavity D Place the affected fuel assembly in an unobstructed opening in the Reactor Vessel Plausibility and Answer Analysis Reason answer is correct: AOP-013 states that fuel assembly must be placed in a safe storage location. Section 3.2 step 2 lists 3 locations given in order of preference with the first location being an unobstructted opening in the Reactor Vessel (2 X 2 element hole)

A. Incorrect. Plausible since this would be the first action in Section 3.2 but since the radiation monitors are only rising and NOT in alarm this answer is not correct.

B. Correct.

C. Incorrect. Plausible since placing the assembly on the floor of the Lower Refueling Cavity would provide more shielding due to the greater depth of the water but it is not a location listed in AOP-013.

D. Incorrect. Plausible since Containment closure will be established but after the other actions are completed. This would NOT be the first action required.

Tuesday, March 20, 2012 2:44:58 PM 44

2012 NRC RO APE 036 Fuel Handling Incidents/S 036AK3.03 Knowledge of the reasons for the following responses as they apply to the Fuel Handling Incidents: Guidance contained in EOP for fuel handling incident (CFR 41.5,41.10/ 45.6 / 45.13)

Importance Rating: 3.7 4.1 Technical

Reference:

AOP-013, Section 3.2, Step 2, Page 10, Rev 14 References to be provided: None Learning Objective: AOP-013, Fuel handling Accident,AOP3-13 Obj. 3 Question Origin: Bank OIT Development Bank 036 AK3.03 Comments:

Tier/Group: T1G2 Tuesday, March 20, 2012 2:44:58 PM 45

2012 NRC RO 2t2rn2NRcRoo2l Given the following plant conditions:

- The plant is operating at 100%

- At 0800 a 83 gpd tube leak occurs on the SG B

- The crew enters AOP-016, Excessive Primary Plant Leakage Which ONE of the following completes statement below?

Reactor Power is required to be reduced to 50% within (1) hour(s) AND the impact of reducing power is that the SG pressures will (2) resulting in a lower RCS to SG leak rate.

A. (1)one (2) lower By (1)one (2) rise C. (1)three (2) lower D. (1)three (2) rise Tuesday, March 20, 2012 2:44:58 PM 46

2012 NRC RO Plausibility and Answ8r Analysis Reason answer is correct: AOP-016, Attachment 1 assumes the leakage should be initially zero to the current in the last hour, requiring action level 3 reduce power to 50%

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for leak rate greater than 75 gpd and a rate increase of greater than 30 gpd/hr. As steam demand is lowered on the secondary the pressure in the SG increases from 995 psig at 100 power to 1092 psig no-load value. The corresponding rise in SG pressure results in a smaller pressure drop during primary to secondary leakage events which reduces the leakrate.

A. incorrect. Plausible because the correct time to reduce power to 50%, but the response of the steam generator pressure due to a increase in steam demand B. Correct.

C. Incorrect. Plausible because the 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months time limit is the time requirement to place the plant in Mode 3, and the response of the steam generator pressure due to a increase in steam demand.

D. Incorrect. Plausible because the 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months time limit is the time requirement to place the plant in Mode 3, but the response to the power reduction is correct.

Tuesday, March 20, 2012 2:44:59 PM 47

2012 NRC RO APE: 037 -Steam Gererator (S/G)-Tube Leake /3 037AK1 .02 Knowledge of the operational implications of the following concepts as they apply to Steam Generator Tube Leak: Leak rate vs. pressure drop CFR 41.8/ 41.10/45.3)

Importance Rating: 3.5 3.9 Technical

Reference:

AOP-016, Attachment 1, Page 19, Rev. 45, SG Student Text, Page 12, Rev 3 References to be provided: None Learning Objective: AOP-016, Excessive Primary Plant Leakage, AOP3-16 Obj. 2.a & 4.b Question Origin: New Comments:

Tier/Group: T1G2 Tuesday, March 20, 2012 2:44:59 PM 48

2012 NRC RO

22. 2012 NRC RO 022 Given the following plant conditions:

- The plant is operating at 45%

- Condenser vacuum is degrading as indicated below:

Time Zone 1 Pressure Zone 2 Pressure 0900 4.4 Hg absolute 4.8 Hg absolute 0905 4.8 Hg absolute 5.3 Hg absolute 0910 5.4 Hg absolute 5.9 Hg absolute 0915 7.2 Hg absolute 7.8 Hg absolute 0920 7.6 Hg absolute 8.4 Hg absolute What is the EARLIEST time that an automatic Turbine/Reactor trip will be generated?

A. 0905 B 0910 C. 0915 D. 0920 Plausibility and Answer Analysis Reason answer is correct: With the 1st stage pressure below 60% the Low vacuum trip of the main turbine occurs automatically when condenser vacuum is above 5 HgA on condenser zone 1. This condition is first satisfied at 0910 A. Incorrect. Plausible because the value is above the 5 HgA setpoint if detemined the low vacuum trip occurs automatically from zone 2.

B. Correct.

C. Incorrect. Plausible because the value is above the 7.5 HgA setpoint if detemined the low vacuum trip occurs automatically from zone 2, but this occurs when 1st stage pressure is above 60%.

D. Incorrect. Plausible because the value is above the 7.5 HgA setpoint if detemined the low vacuum trip occurs automatically from zone 1, but this occurs when 1st stage pressure is above 60%.

Tuesday, March 20, 2012 2:44:59 PM 49

2012 NRC RO APE: O51 Loss o+CondenserVaeuumi4 -

051 AA2.02 Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum: Conditions requiring reactor and/or turbine trip (CFR: 43.5 / 45.13)

Importance Rating: 3.9 4.1 Technical

Reference:

APP-ALB-018, Page 3, Rev. 13 and AOP-012, Step 2, Page 4, Rev 21 References to be provided: None Learning Objective: AOP-012, Partial Loss of Vacuum, AOP3-12 Obj. 4.a Question Origin: New Comments:

Tier/Group: T1G2 Tuesday, March 20, 2012 2:44:59 PM 50

2012 NRC RO 232o12NRcROO23 -

Given the following plant conditions:

- The plant was operating at 100%

- AOP-004, Remote Shutdown, has been entered due to a fire in the MCB

- Transfer to the ACP is complete Using the below indicators from the ACP, which ONE of the following correctly identifies that natural circulation is occurring?

RCS Loops A and B hot leg temperature indicators: Tl-413.2, Tl-423.2 RCS Loops A and B cold leg temperature indicators: TI-410.2, Tl-420.2 Loops A, B, and C SG pressure indicators: P1-474.2, P1-4842, P1-496.2

1) RCS HL indicators: stable or decreasing

2) RCS HL indicators: increasing

3) SG pressure indicators: stable or decreasing

4) SG pressure indicators: increasing

5) RCS HL indicators: at saturation for SG pressure

6) RCS CL indicators: at saturation for SG pressure A. 2,3,and5 B. 2, 4, and 6 C. 1,4,and5 D 1,3, and 6 Plausibility and Answer Analysis Reason answer is correct: Natural Circulation is established when, Hot leg temperatures are lowering, Steam generator pressures are stable or lowering and Cold leg temperatures are at the saturation temperature to maintain Natural circulation.

A. Incorrect. Plausible because these are the indications initially seen during the creatation of the thermal driving head for natural circulation B. Incorrect. Plausible because these are the indications seen to prior to natural circulation being established.

C. Incorrect. Plausible because these are the indications seen following dryout of a faulted steam generator that has completely depressurized D. Correct.

Tuesday, March 20, 2012 2:44:59 PM 51

2012 NRC RO APE: 068 Control Room Evacuation /8 068AA2.1 1 Ability to determine and interpret the following as they apply to the Control Room Evacuation: Indications of natural circulation (CFR: 43.5 / 45.13)

Importance Rating: 4.3 4.4 Technical

Reference:

EPP-004, Step 17.d RNO, Page 30, Rev 24, AOP-004, Attachment 5, Page 98, 99, Rev 57 References to be provided: None Learning Objective: AOP-004, Remote Shutdown, AOP3-4 Obj. 6 Question Origin: New Comments:

Tier/Group: T1G2 Tuesday, March 20, 2012 2:44:59 PM 52

2012 NRC RO

24. 201 2NRC RO 024 -

Given the following plant conditions:

- Plant is at 100% Reactor Power

- Chemistry reports RCS activity is increasing, and the latest sample is 1.4 microcuries per gram DOSE EQUIVALENT 1-131

- ALB-026 2-1, Gross Failed Fuel Detector Trouble is received Which ONE of the following lists (1) the type of radiation monitor the Gross Failed Fuel Detector is AND (2) what actions lAW AOP-032, High RCS Activity, will be used to reduce RCS activity levels?

Ak (1) a process radiation monitor (2) place the cation demineralizer in service B. (1) a process radiation monitor (2) maximize letdown through both mixed-bed demineralizers C. (1) an area radiation monitor (2) place cation demineralizer in service D. (1) an area radiation monitor (2) maximize letdown through both mixed-bed demineralizers Tuesday, March 20, 2012 2:44:59 PM 53

2012 NRC RO Plausibility and Answer Analysis Reason answer is correct: A process radiation monitor (RM-1 RR-741 1, Gross Failed Fuel Detector) is connected to Loop 2 and 3 hot legs and is used to detect. ALB-026-2-1, Gross Failed Fuel Det Trouble, IF alarm is due to high neutron activity then refer to AOP-032, High RCS Activity, lAW AOP-032 if a cation demin is not in service then place one in service.

A. Correct.

B. Incorrect. The first part is correct. The second part is plausible since mixed bed demineralizers are normally utilized during operation, but they are utilized for removal of particles, not reduction of activity (they do not remove Cesium like the Cation bed demin does). If the mixed bed demineralizer was effective in removing activity, maximizing flow would result in maximum purification and reduction of activity C. Incorrect. The first part is plausible because all of the monitors listed in AOP-032, High RCS Activity, Table 1 as entiy condition radiation montors reading higher than normal radiation levels are area radiation monitors. Any or all of these monitors will start seeing higher than normal radiation levels. But these monitors would not be the first monitors to indicate changes in RCS activity levels. The GFFD process monitor would be. The second part of the answer is correct.

D. Incorrect. The first part is plausible because all of the monitors listed in AOP-032, High RCS Activity, Table 1 as entiy condition radiation montors reading higher than normal radiation levels are area radiation monitors. Any or all of these monitors will start seeing higher than normal radiation levels. But these monitors would not be the first monitors to indicate changes in RCS activity levels. The GFFD process monitor would be. The second part is plausible since mixed bed demineralizers are normally utilized during operation, but they are utilized for removal of particles, not reduction of activity (they do not remove Cesium like the Cation bed demin does). If the mixed bed demineralizer was effective in removing activity, maximizing flow would result in maximum purification and reduction of activity Tuesday, March 20, 2012 2:44:59 PM 54

2012 NRC RO APE: High Reor Coo[ant Activity I 076AK2.01 Knowledge of the interrelations between the High Reactor Coolant Activity and the following: Process radiation monitors (CFR 41.7/45.7)

Importance Rating: 2.6 3.0 Technical

Reference:

GFFD Student Text, Page 1, Rev 2, AOP-032, Entry Condtions and actions for RCS specific activity> 1.0 uCi/Gm DEI-131, Pages 3 and 7, Rev 18 References to be provided: None Learning Objective: Gross Failed Fuel Detector Obj. 3.a and 4.c Question Origin: Comments:

Tier/Group: T1G2 Tuesday, March 20, 2012 2:44:59 PM 55

2012 NRC RO 25.2o12NRcRoo25 Given the following plant conditions:

- The plant was operating at 100%

- The plant has experienced a LOCA

- An automatic Reactor Trip and SI have occurred

- The crew has transitioned from PATH-i to EPP-009, Post LOCA Cooldown and Depressurization.

With the above conditions, which ONE of the following describes how voiding can be identified in the RCS?

A. Rapidly decreasing RCS subcooling B. Decreasing safety injection flow C. Increasing RCS pressure Dv Rapidly increasing Pressurizer level Plausibility and Answer Analysis Reason answer is correct: A rapid rise in Pressurize level is indication that voiding of the Vessel Head region has occurred as the rapid expansion of the bulk fluid from liquid to steam forces the fluid into the surge volume of the Pressurizer.

A. Incorrect. Plausible because subcooling is expected to be reduced during depressuization of the RCS and would indica ted saturation conditions exsist to promote void growth B. Incorrect. Plausible because the RCS pressure is lowering and SI flow is expected to be increase during depressuization of the RCS and lowering SI flow would indica ted saturation conditions exsist to promote void growth C. Incorrect. Plausible because he RCS pressure is lowering and to be reduced during depressuization of the RCS and increasing pressure would indicated saturation conditions exsist to promote void growth D. Correct.

Tuesday, March 20, 2012 2:44:59 PM 56

2012 NRC P0 EG3 LOCA Cooldown and Depressurization /4 WEO3EA1 .2 Ability to operate and / or monitor the following as they apply to the (LOCA Cooldown and Depressurization): Operating behavior characteristics of the facility.

(CFR: 41.7/45.5/ 45.6)

Importance Rating: 3.7 3.9 Technical

Reference:

EOP-EPP-009, Note 1, Page 18, Rev #18 References to be provided: None Learning Objective: EPP-009, Post LOCA cooldown and depressurization, EOP3-5 Obj. 3.b Question Origin: Bank CIT Development INTG 289 Comments:

Tier/Group: T1G2 Tuesday, March 20, 2012 2:44:59 PM 57

2012 NRC RO

-2&. 2012 NRC RO 026 - - -

Given the following plant conditions:

- The crew is implementing EOP-FRP-P.1, Response to Imminent Pressurized Thermal Shock

- RCS subcooling does not support SI termination but it does support starting an RCP Which ONE of the following describes why it is desirable to re-start an RCP under these conditions?

A Promote mixing of the Safety Injection water and RCS B. Supply additional heat input into the RCS C. Establish PRZ Spray control D. Promote heat transfer from the SGs to the RCS Plausibility and Answer Analysis Reason answer is correct: Per the WOG Background document to decrease the likelihood of a PTS condition the start of an RCP should be attempted in order to mix cold SI water with warm RCS water.

A. Correct.

B. Incorrect. Plausible because the start of a RCP will provide pump heat which reduces the low temperature concern of a PTS condition.

C. Incorrect. Plausible because the preferred method of RCS pressure control is the use of PRZ Spray which requires an RCP running D. Incorrect. Plausible because if SG where at a higher pressure and temperature than the RCS it will be a heat source not a heat sink and the more effective heat transfer method is the force circulation of the RCS vice natural circulation.

Tuesday, March 20, 2012 2:44:59 PM 58

2012 NRC RO E08 Pressurized Thermal Shock /4 WEO8EK3.3 Knowledge of the reasons for the following responses as they apply to the (Pressurized Thermal Shock): Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.

(CFR: 41.5 /41.10, 45.6, 45.13)

Importance Rating: 3.7 3.8 Technical

Reference:

FRP-P.1 Background document. Step 6 basis, Page 28, HP-Rev.2 References to be provided: None Learning Objective: FRP-P, lntergrity Status Tree, EOP3-14 Obj. 4.d Question Origin: Bank OIT Development Bank INTG 445 Comments:

Tier/Group: T1G2 Tuesday, March 20, 2012 2:44:59 PM 59

2012 NRC P0 27 2Q2 NRC R0027 Given the following plant conditions:

- LT-71 62B, Containment Wide Range Level has increased to 207 inches and continues to rise

- The crew is implementing FRP-J.2, Response to Containment Flooding Which ONE of the following correctly completes the below statement describing why the Containment sump is sampled at this point?

To determine if...

A. the Containment Spray Additive Tank should be isolated.

B the water is suitable for transfer to tanks outside Containment.

C. Emergency Service Water to Containment should be isolated.

D. the Containment sump contains enough boron to prevent a post-LOCA reactivity transient which could result in a loss of subcriticality.

Plausibility and Answer Analysis Reason answer is correct: Per the WOG Background document in an attempt to decrease the level in the containment sump the watershould be sampled for activity to see if the water can be transferred to tanks outside of the containment.

A. Incorrect. Plausible because Containment Spray Additive Tank is design to isolate on low level to prevent air binding of the containment spray pumps in the tank is not isolated.

B. Correct.

C. Incorrect. Plausible because in FRP-J. 1, Response to High Containment Pressure, ESW return is sampled for activity to determine if isolation of the ESW to fan cooler trains is required.

D. Incorrect. Plausible because one of the water sources to containment is ESW which is an unbora ted water source and has the potential to result in dilution of the boron that is collecting in the containment sump following the injection phase of SI.

Tuesday, March 20, 2012 2:44:59 PM 60

2012 NRC RO EI&Containrnent Flooding /5 WE15EG2.l .7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

(CFR: 41.5/43.5/45.12/45.13)

Importance Rating: 4.4 4.7 Technical

Reference:

WOG ERG Background Document for FR-Z.2 (Containment Flooding FRP-J.2), Step 2, Page 8, Rev 2 References to be provided: None Learning Objective: FRP-J, Containment Status Tree, EOP3-13 Obj. 1 .b Question Origin: NEW Comments:

Tier/Group: T1G2 Tuesday, March 20, 2012 2:44:59 PM 61

2012 NRC RO 28.2ol2NRcRoo2g -

Given the following plant conditions:

- The plant is operating at 15% power with Steam Dumps being transferred to Tavg control

- ALB-009 5-1, PRESSURIZER HIGH-LOW PRESS, alarms Two minutes later, RCS Pressure is 2150 psig and is decreasing.

- The RO attempts to shut 1 RC-1 03 (PCV-444D: PRZ Spray Loop B) but it will not respnd Which ONE of the following describes the actions required for this condition lAW AOP-019, Malfunction of RCS Pressure Control?

A. Trip the Reactor then secure ONLY the RCP B to stop the pressure decrease B. Trip the Reactor then secure BOTH the RCP A and B to stop the pressure decrease C Stop the RCP B and if RCS pressure continues to decreases to < 2000 psig then Trip the Reactor D. Stop BOTH the RCP A and B and if RCS pressure continues to decreases to

<2000 psig then Trip the Reactor Tuesday, March 20, 2012 2:44:59 PM 62

2012 NRC RO Pusibility and Answer AIys -

Reason answer is correct: With Reactor power BELOW P-8 the operator will stop the RCP A (RCP associated with the failed Spray Valve PCV-444D: Loop B) and if pressure continues to decrease to below 2000 psig if in Mode 1 or 2 Trip the Reactor and Go To EOP Path-i.

A. Incorrect: Plausible because this action is performed if Reactor power is> P-8 but reactor power is> P-7 but < P-8. The second part of the answer is correct, ONLY the RCP A would be secured to stop the pressure decrease IA W AOP-0 19.

B. Incorrect: Plausible because this action is performed if Reactor power is> P-8 but reactor power is> P-7 but < P-8. The second part of the answer is plausible because AOP-019 would have the operator secure additional RCPs IF PRZ pressure continues to drop in an uncontrolled manner but would have to be BELOW 2000 psig. No indications of being below 2000 psig are given.

C. Correct:

D. Incorrect: Plausible because the candidate may consider that spray flow from the RCP B will continue to cause RCS pressure to decrease but AOP-019 initially directs securing ONLY the RCP associated with the failed Spray Valve. IF IF PRZ pressure continues to drop in an uncontrolled manner AND falls BELOW 2000 PSIG THEN: the operator would Trip the Reactor and Stop additional RCPs.

Tuesday, March 20, 2012 2:44:59 PM 63

2012 NRC RO 003 Reactor cooant Pump System (RCPS) 003A1 .06 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCPS controls including: PZR spray flow (CFR: 41.5 / 45.5)

Importance Rating: 2.9 3.1 Technical

Reference:

AOP-01 9 Rev 22 References to be provided: None Learning Objective: AOP-01 9, Malfunction of Reactor Coolant System Pressure Control, AOP3-19 Obj. 3.b Question Origin: Modified, OIT Development Bank, 027 AA2.06 Comments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:44:59 PM 64

2012 NRC P0

29. 2012-NRC RO.-029 -

Given the following plant conditions:

- The plant is operating at 100%

- CSIP A has been out of service for maintenance for the past 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

- At 0800, the CSIP B trips due to a motor fault

- CSIP C is not available Based on the conditions above, lAW Technical Specifications, the crew must initiate action to shutdown the plant (1) , with the plant reaching Mode 3 no later than (2)

A. (1)byO900 (2) 1400 B (1)byO900 (2) 1500 C. (1)immediately (2) 1400 D. (1)immediately (2) 1500 Plausibility and Answer Analysis Reason answer is correct: T.S. 3.5.2, ECCS Subsystems Tavg greater than or equal to 350°F requires two operable trains of ECCS for this condition. Action are provided for only the loss of one train and therefore T.S. 3.0.3, Limiting Condition For Operation Not Met is applied. One hour is allowed to initiate action to place unit in a Mode in which the specification doesnt apply in addition to the time alloted to place the unit in the non appicable Mode A. Incorrect. Plausible because the 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to place the unit in Hot Standby (Mode 3) is applied from the time of discovery and the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action to initiate actions per T.S. 3.0.3 is applied correctly B. Correct.

C. Incorrect. Plausible because the 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to place the unit in Hot Standby (Mode 3) is applied from the time of discovery, but the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action to initiate actions per T.S. 3.0.3 is not applied D. Incorrect. Plausible because the 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to place the unit in Hot Standby (Mode 3) is applied from the expiration of the T.S. 3.0.3 initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action to initiate actions to shutdown the unit, but the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action to initiate actions per T.S. 3.0.3 is not applied Tuesday, March 20, 2012 2:44:59 PM 65

2012 NRC RO 004 Chemical and Volume Contro[ System (CVCS) 004G2.2.39 Knowledge of less than or equal to one hour Technical Specification action statements for systems.

(CFR: 41.7/41.10/43.2/45.13)

Importance Rating: 3.9 4.5 Technical

Reference:

T.S. 3.0.3 and 3.5.2 References to be provided: None Learning Objective: Technical Specifications, TS2-0 Obj. 3.a Question Origin: Bank CIT Exam Bank TS2-0 (RO3A) 5 Comments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:44:59 PM 66

2012 NRC RO 3O2&i2NRCROO3o Given the following plant conditions:

- PATH-2 is in effect due to a SGTR

- The RCS has been depressurized, and SI flow is terminated

- After normal minif low is realigned, PATH-2 directs the crew to transfer CSIP suction to the VCT (Level is 38%)

If the RO takes the RWST to CSIP valves to shut prior to opening the VCT outlets, what will be the impact?

The RWST supply valves will A shut causing a loss of suction to the running CSIP.

B. not shut since the VCT outlets are closed.

C. shut once the VCT outlets automatically open.

D. not shut since the alternate miniflow isolations are open.

Plausibility and Answer Analysis Reason answer is correct: The CSIP suction isolation valves from the RWST automatically open when a SI signal is present. The CVCS system interlock between the RWST and VCT isolation valves only prevents the VCT from being isolated without the respective RWST isolation valve being open first. With SI reset the auto open signal is removed and in this condition both RWST suction isolation valves can be shut and remain shut which will result in the lost of the CSIP suction path.

A. Correct.

B. Incorrect. Plausible because the system is interlocked to prevent the VCT outlet from closing with the RWST suction valve closed at the same time C. Incorrect. Plausible because the system is interlocked to prevent the VCT outlet from closing with the RWST suction valve closed at the same time, but the RWST suction valves receive an auto open signal from SI D. Incorrect. Plausible because the system is interlocked to prevent the alternate mini-flow valves from being open with the CSIP suction from the RHR system open to prevent water from the Containment sump from being sent to the RWST when the system is in Emergency Recirculation mode.

Tuesday, March 20, 2012 2:44:59 PM 67

2012 NRC RO 004 Chemical and Volume Control System (CVCS 004K4.O7Knowledge of CVCS design feature(s) and/or interlock(s) which provide for the following: Water supplies (CFR: 41.7)

Importance Rating: 3.0 3.3 Technical

Reference:

CVCS Student Text, page 41, Rev 11, Drawing 2166-B-401-0242 and 0244, Rev 19 References to be provided: None Learning Objective: Chemical and Volume Control System, Obj. 8.h Question Origin: Bank CIT Development Bank, EOP-3.2-R3 Comments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:44:59 PM 68

2012 NRC RO 31 2012 NRC ROO31 Given the following plant conditions:

- The plant was operating at 100%

Time 0515 LOCA occurs and the operators enter PATH-i 0525 RHR Pump B tripped on overcurrent 0550 Cold Leg Recirc is established lAW EPP-01 0, Transfer To Cold Leg Reci rculation 0555 CSIP B was secured due to a gear drive failure and resultant oil fire 0600 RHR Pump A tripped on overcurrent lAW EPP-012, Loss Of Emergency Coolant Recirculation, which ONE of the following (1) represents the time used to calculate minimum SI flow required AND (2) the reason for calculating this minimum SI Flow?

A. (1)0515 (2) to ensure the existence of an adequate vessel inventory such that core cooling is ensured.

B (1) 0515 (2) to match decay heat in order to further decrease SI pump flow and delay RWST depletion.

C. (1)0550 (2) to ensure the existence of an adequate vessel inventory such that core cooling is ensured.

D. (1)0550 (2) to match decay heat in order to further decrease SI pump flow and delay RWST depletion.

Tuesday, March 20, 2012 2:44:59 PM 69

2012 NRC RO Plausibility and Answer Analysis Reason answer is correct: lAW EQP-EPP-012 Attachment 1 is based on the time after the Reactor to determine the minimum SI flow, per the ECA 1.1 background document the minimum SI flow established to delay RWST depletion.

A. Incorrect. Plausible because the minimum Si flow is determines based on the time after the Reactor tripped lAWAttachment 1, but the reason given from the background document is for the RVLIS SI termination criteria.

B. Correct.

C. Incorrect. Plausible if the candidate determines the minimum SI flow is based on the time after the Emergency recirculation is established AND the reason given from the background document is for the RVLIS SI termination criteria.

D. Incorrect. Plausible if the candidateconsidered determines the minimum SI flow is

based on the time after the Emergency recirculation is establlshed, but the reason given from the background document is correct for the minimum SI flow required.

Tuesday, March 20, 2012 2:45:00 PM 70

2012 NRC P0 005 Residua[ Heat Removal System (RHRS) -

005K3.05 Knowledge of the effect that a loss or malfunction of the RHRS will have on the following: ECCS (CFR: 41.7 / 45.6)

Importance Rating: 3.7 3.8 Technical

Reference:

EOP-EPP-01 2, Attachment 1, Page 61, Rev 27 References to be provided: None Learning Objective: EPP-01 0, 011, 012 & 013, Safety Injection Recirculation, Loss of Recirc and LOCA outside containment, EOP2-3 Obj 3.i Question Origin: New Comments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:00 PM 71

2012 NRC RO 32 2012 NRC RO032 -

Given the following plant conditions:

- RHR A train is in service for Shutdown Cooling.

- The Instrument Air supply line to 1 RH-30, RHR HEAT XCHG A OUT FLOW CONTROL valve becomes severed and is completely detached.

- 1 RH-30, has a demand of 50%

Which ONE of the following describes the effect on the RHR system?

A. RHR pump A will reach runout conditions.

B. RHR pump A will operate at shutoff head.

C. RHR Heat Exchanger A outlet temperature rises.

D RHR Heat Exchanger A outlet temperature lowers.

Plausibility and Answer Analysis Reason answer is correct: Air to flow control valve failing Valve fails open. Therefore, more flow through heat exchanger, but total flow is maintained by the bypass valve, which will throttle closed when HX outlet flow rises.

A. Inorrect. Plausible because the Hx outlet valve fails open during a loss of air, but the valve travel is physically limited to prevent reaching pump runout conditions.

B. Incorrect. Plausible because the Hx bypass valve falls shut during a loss of air, but the outlet valve will fail out to provide a flow path for the discharge of the pump.

C. Incorrect. Plausible because this is the response of the system if the Hx bypass valve failed to the open position and the Hx outlet valve failed to the shut position during a loss of air

0. Correct.

Tuesday, March 20, 2012 2:45:00 PM 72

2012 NRC RO 005 Residual Heat Remova[ System (RHRS) 005K6.03 Knowledge of the effect of a loss or malfunction on the following will have on the RHRS: RHR heat exchanger (CFR: 41.7 / 45.7)

Importance Rating: 2.5 2.6 Technical

Reference:

AOP-017-BD, page 28 Step 3.3.4, Rev 10; RHR Student Text, page 30, Rev 7 References to be provided: None Learning Objective: AOP-017, Loss of Instrument Air, AOP3-17 Obj. 2.b Question Origin: Bank OIT Development 005 K6.03 Comments: 2006 NRC RO exam Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:00 PM 73

2012 NRC RO

33. 2OI2NRC ROO33- - - - -

Given the following plant conditions:

- EPP-009, Post LOCA Cooldown and Depressurization, is in progress

- RCS temperature is 500°F with a cooldown rate of 25°F per hour in progress

- RCS pressure is 1600 psig

- Containment pressure is 2 psig

- One RCP is running

- The crew is preparing to stop one CSIP and align the normal charging flowpath Which ONE of the following describes (1) the reason RCS subcooling lowers when the crew stops one CSIP AND (2) the RCS subcooling value that requires action to realign the BIT?

A. (1) RCS temperature rise (2) 40°F B. (1) RCS temperature rise (2) 10°F C. (1) RCS pressure reduction (2) 40°F D (1) RCS pressure reduction (2) 10°F Tuesday, March 20, 2012 2:45:00 PM 74

2012 NRC RO Plausibility and Answer Analysis Reason answer is correct: Per the EPP-009, SI reinitiation foldout critieria with normal containment parameters( <3 psig) the fold actions to realign SI are taken when subcooling cannot be maintained above 10°F and per the WOG background documents for EPP-009 the RCS pressure and Pressurizer level decrease which results in lower subcooling of the RCS.

A. Incorrect. Plausible because the SI foldout criteria subcooling value is correct for adverse containment conditions and subcooling lowers as the RCS temperature is closer to the saturation temperature for the RCS pressure at a given time, but a temperature rise is not the cause of this condition.

B. Incorrect. Plausible because the SI foldout criteria subcooling value is correct for normal containment conditions and subcooling lowers as the RCS temperature is closer to the saturation temperature for the RCS pressure at a given time, but a temperature rise is not the cause of this condition.

C. Incorrect. Plausible because the SI foldout criteria subcooling value is correct for adverse containment conditions and subcooling lowers as the RCS pressure lowers the saturation temperature for the RCS pressure lowers as well.

D. Correct.

Tuesday, March 20, 2012 2:45:00 PM 75

2012 NRC RO 006 Emergency Core Cooling System (ECCS) 006A1 .16 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: RCS temperature, including superheat, saturation, and subcooled (C FR: 41.5 / 45.5)

Importance Rating: 4.1 4.2 Technical

Reference:

EOP-EPP-009 and GD, Step: SI Rein foldout and, Page 21-22, Rev 18 References to be provided: None Learning Objective: EPP-009, Post LOCA cooldown and depressurization, EOP3-5 Obj. 4 Question Origin: Bank CIT Development 006 Al .16 Comments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:00 PM 76

2012 NRC RO 34 2012 NRC R 0-34 - -

Given the following plant conditions:

- A Large Break LOCA occurred 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago

- EPP-01 0, Transfer to Cold Leg Recirculation has been completed

- CSIP B has just tripped Which ONE of the following completes the statement below?

After CSIP B trips the flow rate through Fl-940, Alternate Header Flow will (1) and flow rate through Fl-943, Normal Header Flow will (2)

A. (1)remainatzeroflow (2) decrease to approximately half the previous value B. (1) decrease to approximately half the previous value (2) remain at zero flow C. (1) decrease to zero (2) remain constant D (1) remain constant (2) decrease to zero Plausibility and Answer Analysis Reason answer is correct: EPP-0 10 splits the recirc injection flow path into two headers by closing CSIP discharge cross connect valves. Loss of one pump will result in loss of flow on only that header. The A train CSIP supplies the alternate header through FI-940 while the B train CSIP supplies the normal header through Fl-943.

A. Incorrect. Plausible if the applicant does not understand the injection flowpath following completion of EPP-0 10. Flow reduction is plausible if both pumps are operating in parallel and one is secured.

B. Incorrect. Plausible if the applicant does not understand the injection flowpath following completion of EPP-0 10. Flow reduction is plausible if both pumps are operating in parallel and one is secured.

C. Incorrect. Plausible if the applicant understands that the header is split but believes A train supplies the normal header and B train supplies the alternate header.

D. Correct.

Tuesday, March 20, 2012 2:45:00 PM 77

2012 NRC RO 006 Emergency Core Cooling System (ECCS>

006K6.03 Knowledge of the effect of a loss or malfunction on the following will have on the ECCS: Safety Injection Pumps (CFR: 41.7 / 45.7)

Importance Rating: 3.6 3.9 Technical

Reference:

EPP-010, Steps 5 and 6, Pages 12 and 14, Rev 26 References to be provided: None Learning Objective: EPP-009, Post LOCA cooldown and depressurization, EOP3-5 Obj. 5.b Question Origin: Bank OIT Development 006 K6.13 Comments: Modified a 2009B NRC Exam RO question by changing which CSIP has tripped. By changing the A CSIP trip to the B CSIP trip the correct answer was changed from D toC.

Tier/Group: T2G 1

1. Giver the fccaing pfant conditions:

- A Large Break LOCA occurred 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago EPPJ1 Transfer to Cod Leg Re rculaton has been compeed

- The A OSIP has just frpped Which ONE of the c loteng correi1y identifies the flow rates AFTER the A CSIP trip ccurrs?

The flow rate through F-4O, Alternate Header Row will e1) - and flow rats through Fl-c43, Normal Header F-ow will i2 A. 1) remain at zero flow

2) decrease to appro.imat&y halt the previous value B. ) decrease to appruxsnately halt the previous value remain at zero flow i) decrease to zero (2 remain constant remain constant

2) decrease to zero Tuesday, March 20, 2012 2:45:00 PM 78

2012 NRC RO 35.2o12NRcRoo3s -

Given the following plant conditions:

- The plant was initially at 100% power

- CNMT Cooling is in the Max Cooling Mode with BOTH ESW Pumps in service The following occur:

- A spurious Safety Injection occurs

- One train of SI fails to reset from the control room

- Multiple Pressurizer PORV lifts occur during the recovery

- PRT pressure is 110 psig and slowly increasing Which ONE of the following identifies (1) the condition of the PRT AND (2) the current conditions in the Containment?

A (1) Not functioning properly (2) Containment Sump level constant; Containment temperature increasing B. (1) Not functioning properly (2) Containment Sump level increasing;Containment temperature constant C. (1) Functioning as designed (2) Containment Sump level constant;Containment temperature increasing D. (1) Functioning as designed (2) Containment Sump level increasing;Containment temperature constant Tuesday, March 20, 2012 2:45:00 PM 79

2012 NRC RO Plausibility and Answer Analysis Reason answer is correct: PRT rupture discs have not actuated at the designed pressure of 100 psi, thus energy and radioactive liquid released through the PORVs is still contained within the PRT. Therefore sump level will be constant for the given conditions. CNMT temperature is rising due to loss of fan coolers on the SI signal A. Correct.

B. Incorrect. First part is correct as noted above but plausible if applicant misunderstands that once ruptured, PRT pressure will drop to approximately Containment pressure based on the large size of the disc compared to the in-flow from periodic PORV cycling. Nominally the rupture disc should relieve at 100 psi, but for the conditions given the rupture discs have not yet blown. Second part is incorrect C. Incorrect. First part is incorrect but plausible if applicant misunderstands that, Nominally the rupture disc should relieve at 100 psi. Second part is correct for the given conditions, CNMT temperature is rising due to loss of fan coolers on the SI signal, but CNMT sump level will remain constant until the rupture discs actuate.

D. Incorrect. First part is incorrect but plausible if applicant misunderstands that, Nominally the rupture disc should relieve at 100 psi. Second part is incorrect but plausible since the candidate may assume the rupture disc functioned as designed, but CNMT temperature will rise due to loss of fan coolers on the SI signal Tuesday, March 20, 2012 2:45:00 PM 80

2012 NRC RO

- 007 Pressurizer Relief TanklQueneh Tank System (PRTS) 007K3.01 Knowledge of the effect that a loss or malfunction of the PRTS will have on the following: Containment (CFR: 41.7/45.6)

Importance Rating: 3.3 3.6 Technical

Reference:

Pressuizer Student text, page 4, rev 5 References to be provided: None Learning Objective: Pressurizer Pressure Control Obj. 2.e Question Origin: New Comments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:00 PM 81

2012 NRC RO 362.o12NRcRto36 -

Given the following plant conditions:

- The plant is operating at 100%

- CCW Surge Tank High-Low Level alarm energized

- CCW Surge Tank Level LI-670A.1 (Train A) reads 60 percent

- CCW Surge Tank Level Ll-676A.1 (Train B) reads 35 percent

- CCW Pump A Discharge Temp Tl-671 reads 95°F

- COW Header A Pressure P1-649 SA reads 96 psig

- COW Header B Pressure P 1-650 SB reads 48 psig

- COW Hx A Outlet Header Flow FI-652.1 reads 10,500 gpm Which ONE of the following actions would automatically occur as a result of these indications?

A CCW Pump B will start B. CCW Holdup Tank Transfer Pump will trip C. CCW Surge Tank Make Up, 1 DW-1 5 will open D. CCW Return Isolation from the RCP Thermal Barrier, 1CC-252 will shut Plausibility and Answer Analysis Reason answer is correct: Each CCW pump is designed to automatically start when its associated header pressure sensor drops below 52 psig.

A. Correct.

B. Incorrect. Plausible beacuse the CCW Holdup Tank Transfer Pump will trip automatically for a high level in the CCW Surge Tank C. Incorrect. Plausible because it is the normal make up source for the CCW surge tank but is incorrect because the make up valve is manually aligned from the MCB by the board operator as necessary D. Incorrect. Plausible if a high flow condition occurs in the RCP Thermal barrier return header the return line will automatically isolate. This high flow condition is sensed independent of the total system flow.

Tuesday, March 20, 2012 2:45:00 PM 82

2012 NRC RO

- 008 Component Cooling Water System (CCWS) -

008A3.10 Ability to monitor automatic operation of the CCWS, including: CCW pump instruments and their respective sensors, including flow, pressure, oil level, and discharge temperature (CFR: 41.7/45.5)

Importance Rating: 2.9 3.0 Technical

Reference:

ALB-APP-005, Rev 20, Window 6-1, and 8-2 References to be provided: None Learning Objective: Component Cooling Water Obj. Ta Question Origin: NEW Comments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:00 PM 83

2012 NRC RO a7.2ol2NRcRoo37 Given the following plant conditions:

- The plant is operating at 100%

- A Large Break LOCA occurs

- PATH-i is in progress Which ONE of the following completes the statement below?

1CC-i 47, COW FROM RHR HEAT EXCHANGER A-SA will be opened (1) AND 1CC-99, CCW HEAT EXCHANGER A TO NON-ESSENTIAL SUPPLY and 100-128, CCW NON-ESSENTIAL RETURN TO HEADER A will be shut (2)

A. (1) manually (2) automatically B. (1) automatically (2) manually C (1) manually (2) manually D. (1) automatically (2) automatically Plausibility and Answer Analysis Reason answer is correct: CCW to the RHR Hx is normally isolated and is required to be manually aligned to supply cooling to the Hx. The non essential header isolations are normally open and must be manually shut to split the header into individual trains. These actions are direct by Path-i guide step 55.

A. Incorrect. Plausible because the CCW to the RHR Hx is manually aligned and the CCW system is isolated automatically on both Phase A and B containment isolation signal.

B. Incorrect. Plausible because the CCW to the thermal barrier is automatically opened when transferring control to the ACP, manual isolation of the non essential will be required.

C. Correct.

D. Incorrect. Plausible because the CCW to the thermal barrier is automatically opened when transferring control to the ACP and the CCW system is isolated automatically on both Phase A and B containment isolation signal.

Tuesday, March 20, 2012 2:45:00 PM 84

2012 NRC RO 008 Component Cooling Watei System (CCWS) 008A4.01 Ability to manually operate and/or monitor in the control room: CCW indications and controls (CFR: 41.7/45.5)

Importance Rating: 3.3 3.1 Technical

Reference:

PATH-i Guide, page 57, step 55, Rev 33 References to be provided: None Learning Objective: Component Cooling Water Obj. 9 Question Origin: New Comments: Original K/A was 008A4.1 1 but was replaced on 11/3/2011 by Richard Baldwin at Archie Luckys request.

(Unable to write a question to the original K/A, HNPs CCW system did not have this type of valve).

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:00 PM 85

2012 NRC RO 38.2o12NRcRcw3 Given the following plant conditions:

- The unit is in Mode 3 at normal operating pressure

- Pressurizer (PRZ) Pressure Control is in AUTO

- PRZ Pressure Channel PT-445 fails high

- PRZ Pressure Channel indications are:

- P1-444: 2050 psig

- P1-445: 2500 psig

- P1-455: 2050 psig

- P1-456: 1950 psig

- P1-457: 2050 psig Assuming NO operator actions, which ONE of the following describes the expected conditions of the PRZ PORVs and spray valves?

A. PORV 1 RC-1 14 (PCV-444B) CLOSED -

PORVs 1 RC-1 16 (PCV-445B) and 1 RC-1 18 (PCV-445A) OPEN Spray Valves PCV-444C and PCV-444D OPEN -

B. PORV 1 RC-1 14 (PCV-444B) OPEN -

PORV5 1 RC-1 16 (PCV-445B) and 1 RC-1 18 (PCV-445A) CLOSED Spray Valves PCV-444C and PCV-444D OPEN -

C PORV 1 RC-1 14 (PCV-444B) CLOSED-PORV 1 RC-1 16 (PCV-445B) and 1 RC-1 18 (PCV-445A) OPEN Spray Valves PCV-444C and PCV-444D CLOSED-D. PORV 1 RC-1 14 (PCV-444B) OPEN -

PORV5 1 RC-1 16 (PCV-445B) and 1 RC-1 18 (PCV-445A) CLOSED Spray Valves PCV-444C and PCV-444D CLOSED-Tuesday, March 20, 2012 2:45:00 PM 86

2012 NRC RO Plausibility and Answer Analysis - - -

Reason answer is correct: PT-445 controls only PORVs 116 and 118. The PORVs will open and remain open until 2/3 of the protection channels 455/456/457 decrease below the P-i 1 setpoint of 2000 psig. Spray valves are controlled by channel 444.

A. Incorrect. Plausible since PORVs 116 and 118 will open until actual pressure drops below 2000 psig, but the spray valves are controlled by the other channel and will not open.

B. Incorrect. Plausible since this would be the response of the system if the failed channel was 444, but with 445 failed, none of these components are affected.

C. Correct.

D. Incorrect. Plausible since the spray valves will remain closed, but 445 controls PORVs ll6and 118, not 114 010 Pressurizer Pressure Control System (PZR PCS) 01 0K6.Oi Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: Pressure detection systems (CFR: 41.7 / 45.7)

Importance Rating: 2.7 3.1 Technical

Reference:

AOP-019 page 18, att 1, rev 22 References to be provided: None Learning Objective: AOP-Oi 9, Malfunction of Reactor Coolant System Pressure Control, AOP3-19 Obj. 3.b Question Origin: Bank CIT Exam Bank, AOP-019 (05) 003 Corn m ents:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:00 PM 87

2012 NRC RO

39. 2(112 NRC RD 039 - -

Given the following plant conditions:

- The plant was operating at 100%

- Offsite power was lost resulting in a Reactor Trip Which ONE of the following set of operator actions or plant conditions are required to close (reset) the Reactor Trip breakers?

1) Turbine autostop trip header must be repressurized

2) RCP Bus voltage must be restored to greater than 5148v

3) ALL steam generator levels must be restored to greater than 25%

4) High flux rate trip bistables must be reset on the Power Range Nuclear Instrument channels A. 1,2 B. 1,3 C. 2,4 D 3,4 Plausibility and Answer Analysis Reason answer is correct: Both trips will be active based on the initial conditions, but are not blocked automatically and are therefore required to be reset with the trip condition clear in order to close the Rx Trip Breakers A. Incorrect. Plausible because both trips will be active based on the initial conditions, but will be blocked automatically below 10% power by P-7 and are therefore not required to be reset in order to close the Rx Trip Breakers B. Incorrect. Plausible because both trips will be active based on the initial conditions, but Turbine trip/Reactor Trip will be blocked automatically below 10%

power by P-7 and is therefore not required to be repressurized in order to close the Rx Trip Breakers C. Incorrect. Plausible because both trips will be active based on the initial conditions, but RCP undeivoltage Reactor Trip will be blocked automatically below 10% power by P-7 and is therefore not restored above the trip setpoint in order to close the Rx Trip Breakers D. Correct.

Tuesday, March 20, 2012 2:45:00 PM 88

2012 NRC RO 012 Reactox Protection System 01 2A4.06 Ability to manually operate and/or monitor in the control room: Reactor Trip Breakers (CFR: 41.7/45.5 to 45.8)

Importance Rating: 4.3 4.3 Technical

Reference:

RPS Student Text, Page 24, 27, 31, 33, Rev 6 References to be provided: None Learning Objective: Reactor Protection System Obj. 6.e Question Origin: Bank, LORNRC Bank, A09 008 Comments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:00 PM 89

2012 NRC RO

40. 2LH 2 NRC R O4 Given the following plant conditions:

- The plant is operating at 100%

- Containment Pressure Channel IV pressure indication was oscillating and has been removed from service lAW OWP-ESF, Engineered Safety Feature Actuation.

Which ONE of the following identifies the logic associated with the HI-i and HI-3 Containment Pressure actuations after the Channel IV is removed from service?

HI-i SI Actuation Hl-3 CNMT Spray Actuation A 1/2 2/3 B. 1/2 1/3 C. 1/3 2/3 D. 1/3 1/3 Plausibility and Answer Analysis Reason answer is correct: HI-i is normally a 2/3 logic (at 3 psig in the Containment) but changes to 1/2 when one of the logic channels are tripped. For HI-3, 2/4 logic at 10 psig in the Containment, the channel is bypassed.

A. Correct.

B. Incorrect. Plausible if both bis tables are tripped.

C. Incorrect. Plausible if the logic for both are 2/4 and only HI-i is tripped.

D. Incorrect. Plausible if the logic for both are 2/4 and both are tripped.

Tuesday, March 20, 2012 2:45:00 PM 90

2012 NRC RO 013 Engineered Safety Features ActuatiQr System (ESFAS) 013K5.02 Knowledge of the operational implications of the following concepts as they apply to the ESFAS: Safety system logic and reliability (C FR: 41.5 / 45.7)

Importance Rating: 2.9 3.3 Technical

Reference:

OWP-ESF page 4,8 rev 21 References to be provided: None Learning Objective: Engineered Safety Features Actuation System Obj. 1 0.b Question Origin: Bank OIT Development 013 K5.02 Comments: 2007 Audit Exam Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:00 PM 91

2012 NRC RO 41.2012NRCRQU41 -- -

Given the following plant conditions:

- The plant was operating at 100%

- A Small Break LOCA has occurred

- Containment pressure is 3.8 psig and increasing

- Containment temperature is 137°F and increasing Which ONE of the following completes the statement below?

The expected Containment Cooling Fan alignment will be ONE fan in each Containment Fan Cooler Unit running in (1) speed with the post-accident dampers (2)

A (1)SLOW (2) OPEN B. (1)SLOW (2) SHUT C. (1)HIGH (2) SHUT D. (1)HIGH (2) OPEN Plausibility and Answer Analysis Reason answer is correct: Upon receipt of a SI signal each containment fan cooler will start in slow speed and the post accident damper will automatically open if either of the associated fans are running in slow speed A. Correct B. Incorrect. Plausible because the containment cooling fans will be running in slow speed, but post accident dampers will not be shut.

C. Incorrect. Plausible because the containment cooling fans will normally be running in High speed with the post accident dampers shut.

D. Incorrect. Plausible because the post accident dampers will open, but the containment cooling fans will be running in slow speed.

Tuesday, March 20, 2012 2:45:01 PM 92

2012 NRC RO 022 Containment Cooling System (CCS) 022A4.O3Ability to manually operate and/or monitor in the control room: Dampers in the CCS (CFR: 41.7 / 45.5 to 45.8)

Importance Rating: 3.2 3.2 Technical

Reference:

CCS Student Text Procedure, Page 16, Rev 4 References to be provided: None Learning Objective: Containment Cooling System Obj. 8.c Question Origin: Bank OIT Exam Bank, CCS (08C) 002 Comments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:01 PM 93

2012 NRC RO 42 2012. NRf R0 042 Given the following plant conditions:

- The plant was operating at 100% when a LOCA and Loss of Offsite Power occur

- EDG B tripped when started

- The crew is currently in EPP-012, Loss of Emergency Coolant Recirculation

- Containment pressure is 14 psig and rising

- RWST level is 34% and lowering Which ONE of the following describes when Containment Spray can be secured lAW EPP-01 2?

Reference Provided A. ONLY after the RWST level is < 3%

B. A Containment Spray pump can be secured now C With RWST level > 23.4% and Containment pressure < 10 psig D. ONLY when directed by operations staff after Containment pressure is reduced to < 10 psig Tuesday, March 20, 2012 2:45:01 PM 94

2012 NRC PC Plausibility and Answar Analysis Reason answer is correct: With a LOCA and Loss of Offsite Power AND the B EDG tripped ONLY the A Emergency bus will be powered. With Containment pressure at 14 psig a Containment Spray actuation signal would have been generated and ONLY the A Containment Spray pump and two (2) fan cooler units would be in operation. The Containment Spray requirements per EPP-012 step 7 with RWST level > 23.4% and Containment pressure

<10 psig is zero (0) pumps in operation with no requirement for the number of fan cooler units running.

A. Incorrect. Plausible because the requirements for RWST level <3% are 0 Containment Spray pumps running but the pump can be secured prior to reaching 3% in the RWST. Additionally, the foldout of EPP-012 states that IF RWST level decreases to 3% THEN secure all pumps taking suction only from the RWST. With RWST level at 34% the Containment Spray pump Ais currently taking a suction ONLY from the RWST but when RWST level goes below 23.4% an auto swap over to the Containment Recirc Sump will occur and the suction will be from the sump rather than the RWST.

B. Incorrect. Plausible because only 1 Containment Spray pump is required to be in operation with the RWST level at 34% and Containment Pressure of 14 psig. But, current plant conditions has ONLY one Containment Spray pump in operation. With a loss of offsite power AND the B EDG tripped the B Containment Spray pump does not have power and is NOT in operation.

C. Correct.

0. Incorrect. Plausible because PATH-i Attachment 9 provides guidance to the plant operations staff for placing Containment Spray in standby but this direction is when Containment pressure is <8 psig and has ran for a minimum of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Per the table in EPP-0 12 Containment Spray pump requirements are zero pumps in operation but the number of operating pumps is determined by the operating MCR crew and does not have to have plant operations staff approval to secure the operating pumps.

Tuesday, March 20, 2012 2:45:01 PM 95

2012 NRC RO

- 026 Containrnen Spiay System (CSS 026A2.08 Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Safe securing of containment spray when it can be done)

(CFR: 41.5/43.5/45.3/ 45.13)

Importance Rating: 3.2 3.7 Technical

Reference:

EPP-012, Step 7, Page 6, Rev 27 References to be provided: EPP-012 page 6 Learning Objective: Containment Spray System Obj. 7 Question Origin: New Corn ments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:01 PM 96

2012 NRC RO

- 43 2012 NRC. RO C143 Given the following plant conditions:

- The plant was operating at 100%

- A Main Steam line break has occurred inside Containment

- SPDS is displaying RED on the INTEGRITY Critical Safety Function (CSF)

Which ONE of the following completes the statement below?

The parameters used by SPDS to determine the INTEGRITY CSF are the (1)

Tcold AND the (2) RCS Pressure.

A. (1) lowest (2) lowest B. (1)highest (2) highest C (1) lowest (2) highest D. (1) highest (2) lowest Plausibility and Answer Analysis Reason answer is correct: The ERFIS program determines the Intergity CSFST endpoint using the following computer inputs:

TRC9441, RCL A Cold Leg DECR Last Hr Temp TRC9442, RCL B Cold Leg DECR Last Hr Temp TRC9443, RCL C Cold Leg DECR Last Hr Temp PRC9000, RCS Cold Overpressure Limit PRC9455H, RCS Highest Pressure TRC9440, RCS Lowest Cold Leg Temp A. Incorrect. Plausible because the lowest Tcold is correct, but the lowest RCS pressure is used to determine the setpoht for LTOPS.

B. Incorrect. Plausible because the highest RCS pressure is correct, but the 5 highest core exit thermocouple are used to calculate subcooling.

C. Correct.

D. Incorrect. Plausible because the parameters monitored are reversed.

Tuesday, March 20, 2012 2:45:01 PM 97

2012 NRC RO 039-Main an1 Reheat Steam System (MRSS) 039G2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

(CFR: 41.7 / 43.5/45.12)

Importance Rating: 4.0 4.6 Technical

Reference:

HNP-D-001 5, page 97, Rev 6 References to be provided: None Learning Objective: FRP-P, Integrity Status Tree, EOP3-14 Obj. 4.a Question Origin: NEW Comments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:01 PM 98

2012 NRC RO

44. 2L11 2 NRC-RO 044 - -

Given the following plant conditions:

- The plant is operating at 85% power

- A Loss of Main Feedwater Pump B has occurred

- The crew enters AOP-0i0, Feedwater Malfunctions Which ONE of the following describes (1) the plant response AND (2) the action required lAW AOP-010?.

A (1) Automatic turbine runback is initiated (2) Isolate Steam Generator Blowdown B. (1) Automatic turbine runback is initiated (2) Trip the Reactor and go to PATH-i C. (1) Automatic turbine runback is NOT initiated (2) Isolate Steam Generator Blowdown D. (1) Automatic turbine runback is NOT initiated (2) Trip the Reactor and go to PATH-i Plausibility and Answer Analysis Reason answer is correct: Trip of the MFP B causes the Turbine to runback to <60% to reduce steam flow to within the feed flow capacity of one MFP. AOP-01 0 direct the operator to shut the blowdown FCV to reduce the inventory loss until the runback is complete A. Correct.

B. Incorrect. Plausible because a turbine runback will occur automatically and the power level is just below the value that would require the candidate to trip the reactor and go to PATH-i IAWAQP-0i0.

C. Incorrect. Plausible because the AOP-0i0 action for this power level is to shut the blowdown FC and if both Heater Drain pump where to trip then no runback would occur because 85% is below the power level (90%) for which a turbine runback would be caused by a trip of the last running HDP.

D. Incorrect. PlausThie because a turbine runback would not occur if both Heater Drain pump were to trip because 85% is below the power level (90%) in which that runback is active and if the above 90% initial power actions were taken for being initially above 80% then the candidate would trip the reactor and go to PATH -1.

Tuesday, March 20, 2012 2:45:01 PM 99

2012 NRC RO 059 Main Feeciwater (MEW) System 059K4.02 Knowledge of MEW design feature(s) and/or interlock(s) which provide for the following: Automatic turbine/reactor trip runback (CFR: 41.7)

Importance Rating: 3.3 3.5 Technical

Reference:

AOP-01 0, Section 3.0, Step 3, Page 4, Rev 33 References to be provided: None Learning Objective: Digital Electrohydraulic Control System Obj. 8.a Question Origin: Bank Comments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:01 PM 100

2012 NRC RO 45 2q12 NRC RO O4 Given the following plant conditions:

- The plant is operating at 100%

- Annunciator ALB-14-7-4, SG A, B, C BACK LEAKAGE HIGH TEMP has alarmed and has been verified as valid by local pyrometer readings indicating > 212°F Under these conditions why would establishing AFW flow to the Steam Generators be an undesirable action?

Rapid introduction of feed flow.

A. combined with steam void collapse could cause AFW Pump run out conditions.

B. creates a higher AT across AFW system valves, resulting in thermal binding.

C. is the initiator for accelerated water induced erosion of AFW piping.

D and the resulting steam void collapse causes water hammer in AFW piping.

Plausibility and Answer Analysis Reason answer is correct: Per the AOP-01 0 basis document if steam has entered the horizontal portions of the AFW system piping the introduction of cold AFW water could create bubble collapse water hammer of a damaging magnitude.

A. Incorrect. Plausible because the collapsing of steam bubbles will result in a surge in the pump flow, but the discharge pressure control valve is designed to prevent the pump from reaching runout conditions B. Incorrect. Plausible because the backleakage from the steam generators will result in higher temperatures, but the AFW system has alarms to alert the operator before the system becomes susceptible thermal binding of the systems valves.

C. Incorrect. Plausible because flow accelerated corrosion is possible on carbon steel piping under these conditions, but the the short term concern is the potential of water hammer.

D. Correct.

Tuesday, March 20, 2012 2:45:01 PM 101

2012 NRC RO 061- Auxiiiary [Emergency Feedwater (AFW.) System 061 K5.05 Knowledge of the operational implications of the following concepts as the apply to the AFW :Feed line voiding and water hammer (CFR: 41.5 / 45.7)

Importance Rating: 2.7 3.2 Technical

Reference:

AOP-01 0 BD, 1.0 Discussion on SG Backleakage, Page 7, Attachment 9, Step 1 .b, Page 39, Rev. 15 References to be provided: None Learning Objective: AOP-01 0, Feedwater System Malfunctions, AOP3-1 0 Obj. 2.a.2 Question Origin: Bank OIT Exam AOP-010 (03) 1 Comments: None Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:01 PM 102

2012 NRC RO 4 2012 NRC RO 046 - -

Given the following plant conditions:

- The plant is operating at 100%

- Recovery from a Loss of Instrument Bus 1DP-1A-S1 is in progress

- The crew has de-energized the associated Process Instrumentation Cabinet in preparation for energizing Instrument Bus 1 DP-1 A-Si

- The crew is evaluating bistable status prior to energizing the bus Which ONE of the following describes the reason for checking bistable status?

A. When the Instrument Bus is energized, a reactor trip may occur due to the associated Process Instrumentation Cabinet being de-energized, if another bistable of the same parameter is tripped.

B When the Process Instrumentation Cabinet is energized after the Instrument Bus, energize to actuate bistables may experience a momentary inadvertent trip.

Checking other bistables ensures an ESF actuation will not occur.

C. Bistables are checked to ensure that each parameter for Process or Protection goes to its required state when the Instrument Bus and Process Instrumentation Cabinet is energized.

D. Bistables are checked to ensure that all lights are out, verifying that the Process Instrumentation Cabinet normal and alternate supply breakers are open prior to reenergizing the Instrument Bus.

Plausibility and Answer Analysis Reason answer is correct: Directly from procedure, check bistables to ensure inadvertent actuation does not occur A. Inorrect. Because the concern is energize to actuate bistables. Deenergize to actuate bistables would have caused a trip already.

B. Correct.

C. Incorrect. Bistables are checked for required state, but not prior to energizing a PlC.

D. Incorrect. Bistables are checked by looking at the lights but this does not verify the alternate supply breakers are open. This is done by checking the breakers prior to reenergizing the Instrument Bus.

Tuesday, March 20, 2012 2:45:01 PM 103

2012 NRC RO

062 AC E[eGtrical Disribn 062A1 .03 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the AC distribution system controls including:

Effect on instrumentation and controls of switching power supplies (CFR: 41.5 / 45.5)

Importance Rating: 2.5 2.8 Technical

Reference:

OP-156.02, Section 8.7, Step 8.7.2.1, Rev 97 References to be provided: None Learning Objective: LPAOP3-24 Obj 6 Question Origin: Bank OIT Development 062 Al .03 2 Comments: 2008 NRC RO Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:01 PM 104

2012 NRC RO 47;2o12NRcRo47 Given the following plant conditions:

- The plant is operating at 50%

- Aux Bus 1 D deenergizes and is locked out Which ONE of the following loads will be energized following this event?

(Assume no operator action)

A. Normal service water Pump 1A B. Containment fan coil Unit AF-I-37 1 A C Service water booster Pump 1A-SA D. Pressurizer backup heater Group A Plausibility and Answer Analysis Reason answer is correct: Service water Booster pump 1A-SA is supplied from the 1A Emergency Bus and will be started by the sequencer once power is restored from the EDG.

A. Incorrect. Plausible because NSW Pump 1A is powered by the 6.9KVAux Bus 1D, but it will not have power available until the 1D Bus is re-energized B. Incorrect. Plausible because Containment fan coil Unit AH-37 1A is powered by the 480 VA ux Bus 1 Dl, which is supplied by 6.9 KV A ux Bus 1 D ,and it will not have power available until the 1D Bus is re-energized C. Correct.

D. Incorrect. Plausible because the Pressurizer backup heater Group A is powered by the 48OVAux Bus 11, which is supplied by the 6.9 KV Emergency Bus 1A-SA, but it will not have power restored by the sequencer once the 6.9 KV bus power is restored from the EDG.

Tuesday, March 20, 2012 2:45:01 PM 105

2012 NRC RO 062 A;C. Electrical Distribution 062K2.01 Knowledge of bus power supplies to the following: Major system loads (CFR: 41.7)

Importance Rating: 3.3 3.4 Technical

Reference:

OP-i 39, Attachment 1, Page 96, Rev 91 References to be provided: None Learning Objective: Service Water System Obj. 6.d Question Origin: Bank CIT Exam Bank, Comments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:01 PM 106

2012 NRC RO 4& 20 12-NRC RO O4 -*-* -

Which of the below annunciators would reflect an automatic start of the Emergency DC Lube Oil pump?

A. ALB-01 8 (7-1), Loss of DC Power to the Emerg Brg Oil Pump B ALB-020 (5-4A), Turb Emer Oil Pump Run/Trbl.

C. ALB-018 (2-4), Turbine Trip Brg Oil Low Press.

D. ALB-020 (1-4A), Brg Oil Pre Trip Low Press.

Plausibility and Answer Analysis Reason answer is correct: The alarm setpoint is 10.5 psig and corresponds to the pressure which will automatically start the DC Emergency Bearing Oil Pump A. Incorrect. Plausible because the alarm received is associated with the DC Emergency Bearing Oil Pump, but is not an indication that the should have started.

B. Correct.

C. Incorrect. Plausible because the alarm received is associated with the Bearing Oil system, but is an indication that the did not start when it should have started.

D. Incorrect. Plausible because the alarm received is associated with the Bearing Oil system, but is an indication that the did not start when it should have started.

Tuesday, March 20, 2012 2:45:01 PM 107

2012 NRC RO 06a DC Liectrical Distribution -

063A3.01 Ability to monitor automatic operation of the DC electrical system, including:

Meters, annunciators, dials, recorders, and indicating lights (CFR: 41.7/ 45.5)

Importance Rating: 2.7 3.1 Technical

Reference:

APP-ALB-020, Window 5-4A, Page 39, Rev 33 References to be provided: None Learning Objective: Main Turbine Lube Oil Obj. 6.c Question Origin: Bank, OIT Development MT-3.1-x Comments: 2008 RO Audit Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:01 PM 108

2012 NRC RO

- 49 2012 NRC RO 049 - -

Given the following plant conditions:

- OST-1823, 1A-SA Emergency Diesel Generator Operability Test 18 Month Interval, is being performed.

- EDG A is running carrying Bus 1A-SA in lsochronuos mode.

- ESW A Pump trips and 1 SW-39, Normal SW Supply to Header A, will not OPEN.

Which ONE of the following completes the statments below?

The EDG A (1) control switch must be used to secure the Diesel AND when the control switch is released the Diesel will (2)

A. (1) EMERGENCY STOP (2) Automatically restart due to undervoltage (86UV)

B (1) EMERGENCY STOP (2) not restart until the EDG trip signals are reset C. (1) STOP (2) Automatically restart due to undervoltage (86UV)

D. (1)STOP (2) not restart until the EDG trip signals are reset Plausibility and Answer Analysis Reason answer is correct: Because ESW is lost to an operating EDG the Emergency Stop control switch must be used to prevent the auto start of the EDG on a 86UV to the 6.9 KV Emergency Bus 1 A-SA. Following the use of this control switch the emergency trips must be reset to allow the undervoltage conditions on the 1A-SA bus to automatically start the EDG.

A. Incorrect. Plausible because the Emergency stop control switch is the correct switch but the automatic starts are blocked until the emergency trips are reset.

B. Correct.

C. Incorrect. Plausible because this is the expected response for the use of the Normal stop switch, but the lost ESW to the EDG requires the use of the emergency stop control switch.

D. Incorrect. Plausible because this is the correct response for the use of the Emergency stop switch, but the use of the Normal stop switch will only stop the EDG while the control switch is in the stop position.

Tuesday, March 20, 2012 2:45:01 PM 109

2012 NRC PC 064 Emergency Dies Generators (EDIG) -

064A2.14 Ability to (a) predict the impacts of the following malfunctions or operations on the EDIG system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effects (verification) of stopping ED/G under load on isolated bus (CFR: 41.5/43.5/45.3/45.13)

Importance Rating: 2.7 2.9 Technical

Reference:

AOP-022, Section 3.0, Step 2, Page 4, Rev 34 AOP-025, Section 3.1, Step 3.a RNO, Step 46, Page 7, Page 19, Rev 30 References to be provided: None Learning Objective: Diesel Engine and Support Systems Obj. 8.a & 9 Question Origin: New Comments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:01 PM 110

2012 NRC RO 50 2O12NRCROO-50 Given the following plant conditions:

- The plant is operating at 100%

Which ONE of the following will DIRECTLY initiate an emergency start of the A Emergency Diesel Generator?

A BKR 1 05-SA, Emergency Bus A-SA to Aux Bus D Tie opening B. 86UV undervoltage lockout on Aux Bus D activating C. BKR 101, SUT XFMR A to Aux Bus D opening concurrent with a generator lockout D. Safeguards Sequencer A starting Plausibility and Answer Analysis Reason answer is correct: Emergency starts of the EDG are initiated by the 52Sb contacts in the breaker 1 05-SA, Emergency Bus A-SA to Aux Bus D Tie which close whenever the breaker is opened.

A. Correct.

B. Incorrect. Plausible because an 86 UV relay is an Emergency start signal if it is from the 6.9 KV Emergency Bus 1A-SA, but the 86 UV relay for the 6.9 KVAux Bus 1D will not directly start the EDG.

C. Incorrect. Plausible because this condition will send a trip signal to the tie breaker 105 which will result in a EDG start signal for breaker 105 opening, but it will not send a signal directly to the EDG.

D. Incorrect. Plausible because the safegaurd sequencerA will send a start signal to the EDG, but the signal is processed via slave relay k601 not directly from the master relay in the SI System.

Tuesday, March 20, 2012 2:45:01 PM 111

2012 NRC RO 064 Emergnc.y Die1 GneratQr (EDIG) -

064K1 .01 Knowledge of the physical connections and/or cause effect relationships between the ED/G system and the following systems: AC distribution system (CFR: 41.2 to 41.9/45.7 to 45.8)

Importance Rating: 4.1 4.4 Technical

Reference:

DG Student Text Procedure, Page 57, Rev 7 References to be provided: None Learning Objective: Diesel Engine and Support Systems Obj. 8.b Question Origin: Bank OIT Exam Bank, DE (08B) 002 Comments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:01 PM 112

2012 NRC RO 5.t2OI2NRCROO-51 -

Given the following plant conditions:

- The plant is operating at 100%

- Annunciator ALB-01 0, 3-4, WPB Effluent Rad Monitor Trouble is recieved

- RM-1 1 indicates REM*1WV3546, WPB Stack 5 PIG Monitor is in HIGH alarm Which ONE of the following valves will automatically shut?

A. 3LHS-296, Treated LHS Tk Disch Isol Valve.

B 3WG-229, WG Decay Tanks E & F to Plant Vent Vlv.

C. 3FD-421, WMT Disch Isol VIv.

D. 3SWT-149, Sample Tk Environmental Disch Isol Vlv.

Plausibility and Answer Analysis Reason answer is correct: A Process radiation monitor will isolate the discharge path for the associated flowpath automatically when it is in the High alarm condition.

REM*1WV3546 is associated with the Waste process build release path to the Plant vent and will isolate the E and F waste gas decay tanks by shutting 3WG-229.

A. Incorrect. Plausible because annunciator ALB-O1O, 3-4, WPB Effluent Rad Monitor Trouble will come in for the High alarm on REM*1 WL-3540, which will shut 3LHS-296 B. Correct.

C. Incorrect. Plausible because annunciator ALB-O1O, 3-4, WPB Effluent Rad Monitor Trouble will come in for the High alarm on REM-2 1 WL-354 1, which will shut 3FD-42 1 D. Incorrect. Plausible because annunciator ALB-O1O, 3-4, WPB Effluent Rad Monitor Trouble will come in for the High alarm on REM-21 WS-3542, which will shut 3SWT-149 Tuesday, March 20, 2012 2:45:01 PM 113

2012 NRC RO 073 Process Radiation Monitoring (PRM System -

073K1 .01 Knowledge of the physical connections and/or cause effect relationships between the PRM system and the following systems: Those systems served by PRM5 (CFR: 41.2 to 41.9/ 45.7 to 45.8)

Importance Rating: 3.6 3.9 Technical

Reference:

AOP-005-BD, 1.0 Discussion, Page 3, Rev 8, APP-ALB-010 Window 3-4, Page 17, Rev 25 References to be provided: None Learning Objective: AOP-005, Radiation Monitors, AOP3-5 Obj. 4 Question Origin: Bank CIT Development 073 Ki .01 V Comments: 2008 Audit RO Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:01 PM 114

2012 NRC RO 52.2ol2NRcRo-o52 -

Given the following plant conditions:

- The plant is operating at 100%

- An overcurrent fault causes 1 B35-SB to be deenergized How will the supply and return cross-tie valves between NSW and ESW be configured following an automatic start of the ESW pump B?

A. BOTH 1 SW-40, Normal SW Supply to Header B AND 1 SW-274, Header B Return to Normal Header will shut.

B NEITHER 1 SW-40, Normal SW Supply to Header B NOR 1 SW-274, Header B Return to Normal Header will shut.

C. 1 SW-40, Normal SW Supply to Header B will shut; 1 SW-274, Header B Return to Normal Header will NOT shut.

D. 1 SW-40, Normal SW Supply to Header B will NOT shut; 1 SW-274, Header B Return to Normal Header will shut.

Plausibility and Answer Analysis Reason answer is correct: Both 1 SW-40 and 1 SW-274 are powered from 480V MCC 1 B35-SB, with power lost to both valves they will not realign automatically and remain in the open position.

A. Incorrect. Plausible because the service water system is designed with isolation valves powered from the opposite safety train to ensure isolation capabilty from the NSW system is preserved following the loss of one train.

Candidate must know the power supply for each valve to correctly answer the question.

B. Correct.

C. Incorrect. Plausible because the service water system is designed with isolation valves powered from the opposite safety train to ensure isolation capabilty from the NSW system is preserved following the loss of one train.

Candidate must know the power supply for each valve to correctly answer the question.

D. Incorrect. Plausible because the service water system is designed with isolation valves powered from the opposite safety train to ensure isolation capabilty from the NSW system is preserved foiowmg the loss of one train.

Candidate must know the power supply for each valve to correctly answer the question.

Tuesday, March 20, 2012 2:45:02 PM 115

2012 NRC RO 0-76 Service Water System (SWS) 076K2.01 Knowledge of bus power supplies to the following: Service water (CFR: 41.7)

Importance Rating: 2.7 2.7 Technical

Reference:

OP-i 39, Attachment 1, Page 98, Rev 91 References to be provided: None Learning Objective: Service Water System Obj. 6.f Question Origin: Bank OIT Exam Bank, ESWS (06F) 002 Comments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:02 PM 116

2012 NRC RO 53 2012 NRC RO 053 - - -

Given the following plant conditions:

- The plant is operating at 100% power

- The Control Room receives ALB-2-8-1, INSTRUMENT AIR LOW PRESSURE alarm

- Air header pressure is lowering as indicated on the MCB meters.

Which ONE of the following is an expected plant response for this situation?

A The Service Air Header Isolation Valve, 1 SA-506 automatically shut at 90 psig B. The RCS letdown system automatically isolates at 85 psig C. The Feedwater Flow Control valves automatically shut at 75 psig D. The Feedwater pump discharge valves automatically isolate at 60 psig Plausibility and Answer Analysis Reason answer is correct: lAW AOP-017 a service air isolation occurs at 90 psig and Service Air Header Isolation Valve 1 SA-506 auto shuts A. Correct.

B. Incorrect. Plausible since th RCS letdown system is affected at 85 psig but it does not automatically isolate. The letdown valves begin to fail to mid-position at this pressure.

C. Incorrect. Plausible since the FW flow control valves auto shut at 60 psig. 75 psig IA pressure is associated with when the low air header pressure alarms on the MCB for Instrument and Seivice Air.

D. Incorrect. Plausible since the Feedwater pump discharge isolation valves receive a close signal as part of a Feedwater isolation signal along with the FW flow control valves, but this signal is separate from the automatic shut signal for low IA pressure to the FW flow control valves.

Tuesday, March 20, 2012 2:45:02 PM 117

2012 NRC RO 078 thstrument Air System (LAS -

078A3.01 Ability to monitor automatic operation of the lAS, including: Air pressure (CFR: 41.7 / 45.5)

Importance Rating: 3.1 3.2 Technical

Reference:

AOP-01 7, Attachment 7, Page 57, Rev. 32 References to be provided: None Learning Objective: AOP-01 7, Loss of Instrument Air, AOP3-1 7 Obj. 2 & 4 Question Origin: OIT Exam Bank AOP-017 (04) 1 Comments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:02 PM 118

2012 NRC RO

54. 21)12 NRC RD 054 -

Given the following plant conditions:

- The plant is operating at 100%

- Compressor lB is running in Lead

- Compressor 1 A is the Lag unit

- Compressor 1 C is the Standby unit

- A service air pipe ruptures resulting in lowering Instrument Air header pressure Which ONE of the following statements describes the response of the Instrument Air System following the reduction in header pressure?

A. At 96 psig Compressor 1 A receives an autostart signal from the CAS Control Panel Sequencer.

B. At 95 psig Compressor 1A will autostart from the internal pressure switch, run for 15 minutes and if unloaded then shutdown C. At 98 psig the CAS Control Panel Sequencer will shift to the 1A running as Lead, with 1 B as Lag and the 1 C in Standby.

D At 101 psig system air header pressure, Compressor 1C will autostart; Compressor 1 B will continue to run.

Plausibility and Answer Analysis Reason answer is correct: With the CAS Control Panel in seqence 2 it will sequence the lead (1 B) and lag (1A) compressors to maintain normal system pressure 100 to 115 psig. If the lead and lag compressors are not able to maintain system header pressure the 1C compressor will start at 101 psig system header pressure.

A. Incorrect. Plausible becasue 96 psig is the correct pressure for the 1A compressor to automatically start when isolated from the CAS Control panel.

B. Incorrect. Plausible because 95 psig is the correct pressure for the lB compressor to automatically start when isolated from the CAS Control panel C. Incorrect. Plausible because 98 psig is the pressure that the CAS Control panel will load the lead compressor, but it does not shift the lead compressor at this pressure.

D. Correct.

Tuesday, March 20, 2012 2:45:02 PM 119

2012 NRC RO 078 Instrument Air system (lAS) 078K3.03 Knowledge of the effect that a loss or malfunction of the lAS will have on the following: Cross-tied units (C FR: 41.7/45.6)

Importance Rating: 3.0 3.4 Technical

Reference:

OP-i 51.01, Section 4.0, Step 4.0.6, Page 7, Rev 66 References to be provided: None Learning Objective: AOP-01 7, Loss of Instrument Air, AOP3-1 7 Obj. 2 Question Origin: Bank OlT Exam ISA (02F) 4 Comments: After a discussion with Rick Baldwin on 11-15-2011 we agreed that the question could ask about cross-tied air compressors and NOT Cross-tied units. This clarification was needed because this K/A was written for multiple unit facilities.

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:02 PM 120

2012 NRC RO

- 55 2012 NRC RO 055 Which ONE of the following components forces air within Containment between the Reactor Vessel and the concrete wall on which the Reactor Vessel is supported?

A. Reactor Support Cooling Fans, S-4 A-SA B. Containment Fan Coil Units, AH-2 A-SA C Primary Shield Cooling Fans, S-2 A-SA D. Containment Fan Coolers, AH-37 1A Plausibility and Answer Analysis Reason answer is correct: Primary Shield Cooling is to supply cool air from the concrete air shaft to the clearance between the reactor vessel and primary shield wall A. Incorrect. Plausible because Reactor Supports Cooling is to supply cooling air to the reactor vessel supports and to the reactor coolant leg nozzles to reduce thermal expansion.

B. Incorrect. Plausible because Containment Fan Coil Units are design to provide area cooling support to the RCPs C. Correct.

D. Incorrect. Plausible because Containment Fan Coolers is to provide cooling to Containment for normal operation and accident conditions. During normal operations the Containment Fan Coolers will maintain Containment temperatures below Technical Specification limits Tuesday, March 20, 2012 2:45:02 PM 121

2012 NRC RO 1-03 ContainmentSystem- -

1 03K1 .03 Knowledge of the physical connections and/or causeeffect relationships between the containment system and the following systems: Shield building vent system (CFR: 41.2 to 41.9/ 45.7 to 45.8)

Importance Rating: 3.1 3.5 Technical

Reference:

CCS Student Text, Page 3, Rev 4 References to be provided: None Learning Objective: Containment Cooling System Obj. 1 .c Question Origin: Bank OIT Development Bank, CCSTQ2-0 Comments:

Tier/Group: T2G1 Tuesday, March 20, 2012 2:45:02 PM 122

2012 NRC P0

- 2012 NRC RO 0.56 Given the following plant conditions:

- The plant was operating at 100%

- A Large Break LOCA occurred one hour ago

- Only one Train of ECCS equipment is available Which ONE of the following is the reason the source range count rate is indicating higher than normal?

A. The source range detectors are not accurate indicators under adverse Containment conditions.

B Attenuation of neutrons in the downcomer has been reduced by voiding.

C. Attenuation of neutrons in the core has been reduced by voiding.

D. RHR suction has swapped to the Containment Recirc Sump which contains a lower boron concentration than the ECCS injection.

Plausibility and Answer Analysis Reason answer is correct: Detector will be more responsive to voiding in downcomer than to voiding in core, downcomer is more likely to be subcooled and as the downcomer begins to void the SR will become more responsive to the neutrons that are leaking out of the core through the voided downcomer region.

A. Incorrect. Plausible because the Wide range flux monitors are designed for accident conditions and monitoring of a larger range of flux conditions that are expected to be seen following a major accident.

B. Correct.

C. Incorrect. Plausible because as vessel level is reduced attenuation of neutrons in the core is reduced, but the effect on the SR Nis will be minimial due to shielding of the core in the central region.

D. Incorrect. Plausible because some boron is expected to remain in the core as the bulk RCS fluid flashes to steam and the boron comes out of solution and is plated on the RCS fuel bundles.

Tuesday, March 20, 2012 2:45:02 PM 123

2012 NRC RO 002 Reactor CoolantSystem (RCS) 002K1 .12 Knowledge of the physical connections and/or cause-effect relationships between the RCS and the following systems: NIS (CFR: 41.2 to 41.9/45.7 to 45.8)

Importance Rating: 3.5 3.6 Technical

Reference:

Westinghouse Owners Group, Mitigating Core Damage, Module 3, Lesson 1 References to be provided: None Learning Objective: LPMCD4-6, Midigating Core Damage, Obj b.2 Question Origin: New Comments:

Tier/Group: T2G2 Tuesday, March 20, 2012 2:45:02 PM 124

2012 NRC RO 57.wIzNRcRclos7 -

Given the following plant conditions:

- The plant is operating at 100%

- Breaker 102, Unit Aux Xfmr A To Aux Bus D, is opened to isolate an electrical fault caused by a fire.

Which ONE of the following loads will de-energize AND automatically re-energize?

A. NSW Pump A B. NSW Pump B C CSIP A D. CSIPB Plausibility and Answer Analysis Reason answer is correct: Bus 1D is the normal supply to 69 KV Bus 1A-SA. The charging pump is de-energized while the EDG comes up to speed and powers the bus.

The Charging pump will be started automatically by the sequencer.

A. Incorrect. Plausible because seavice water is required for safe shutdown and NSW pump A is a 1D loads, however service water will be supplied by ESW in this situation.

B. Incorrect. Plausible because B NSW pump is a 1E load C. Correct.

D. Incorrect. Plausible because losing Bus 1E will result in this effect Tuesday, March 20, 2012 2:45:02 PM 125

2012 NRC RO 01 t Pressurizer Level Cntro System (PZR LC 011 K2.0i Knowledge of bus power supplies to the following: Charging pumps (CFR: 41.7)

Importance Rating: 3.1 3.2 Technical

Reference:

OP-i 07, Attachment 1, Page 73, Rev 90 References to be provided: None Learning Objective: AOP-01 5, Loss of One Emergency AC Bus, AOP3-25 Obj.4&5.c Question Origin: Bank OIT Development 011 K2.01 Comments:

Tier/Group: T2G2 Tuesday, March 20, 2012 2:45:02 PM 126

2012 NRC RO 5.2O12NRCROO58 -

Given the following plant conditions:

- A plant Reactor startup is in progress

- Shutdown Bank C has been fully withdrawn

- The OAC is in the process of withdrawing Shutdown Bank A, when a DRPI Data A and Data B failure occur on one of the Shutdown Bank C control rods.

Which ONE of the following pairs of annunciators on APP-ALB-01 3 alarmed from this condition?

WINDOW ALARM TITLE

1) 6-1 RPI URGENT ALARM

2) 6-2 RPI NON-URGENT ALARM

3) 7-4 ONE ROD AT BOTTOM

4) 8-5 COMPUTER ALARM ROD DEV/SEQ NIS PWR RANGE TILTS A. 1AND3 B 1AND4 C. 2AND3 D. 2AND4 Plausibility and Answer Analysis Reason answer is correct: DRPI will generate a RPI Urgent Alarm when a failure of both Data A and Data B occurs. ERFIS receives information from DRPI to determine whether any one control rod within a group is> 12 steps from the group average. Since there is NO information for ERFIS to compare due to the Data A and Data B failure for the one control rod, ERFIS will generate a Computer Alarm Rod Deviation.

A. Inorrect. Plausible since the API Urgent Alarm will come in AND a One Rod At Bottom annuciator would have alarmed IF the Shutdown banks were withdrawn AND Control Bank A was withdrawn to> 12 steps. Since the Shutdown banks are NOT withdrawn and Shutdown Bank C is < 12 steps the alarm is overridden.

B. Correct.

C. Incorrect. Plausible since DRPI will generate a API Non-Urgent alarm when EITHER Data A OR Data B fail. But since both have failed a API Urgent alarm would annunciate.

D. Incorrect. Plausible since DRPI will generate a RPI Non-Urgent alarm when EITHER Data A OR Data B fail. The second part of the answer is correct.

Since there is NO information for ERFIS to compare due to the Data A and Data B failure for the one control rod, ERFIS will generate a Computer Alarm Rod Deviation.

Tuesday, March 20, 2012 2:45:02 PM 127

2012 NRC RO 014 Rod Pos4tiori 1ndioatior System (RPlS 014K3.02 Knowledge of the effect that a loss or malfunction of the RPIS will have on the following: Plant computer (CFR: 41.7/45.6)

Importance Rating: 2.5 2.8 Technical

Reference:

APP-ALB-01 3 Window 6-1, 8-5, Page 26 & 37, Rev 30 References to be provided: None Learning Objective: Digital Rod Position Indication System Obj. 4 & 6 Question Origin: New Comments: None Tier/Group: T2G2 Tuesday, March 20, 2012 2:45:02 PM 128

2012 NRC RO

59. 2012 NRC RO O9 Given the following plant conditions:

- The crew is performing EPP-004, Reactor Trip Response

- Natural circulation verification is in progress

- Core Exit Thermocouples G2 and K5 have failed due to open circuits Which ONE of the following completes the statement below?

With open circuit failures, the input from these thermocouples to the Inadequate Core Cooling Monitor (ICCM) will be (1) AND the subcooling margin will be (2)

A. (1)failed low; (2) manually calculated by an operator.

B. (1)failed high; (2) manually calculated by an operator.

C (1) failed low; (2) automatically calculated by ICCM.

D. (1)failed high; (2) automatically calculated by ICCM.

Plausibility and Answer Analysis Reason answer is correct: An open circiut will result in a failed low input and will not be used by ICCM (Only the 5 highest CET temperature and lowest RCS pressure).

A. Incorrect. Plausible since candidate must know the method used to calculate subcooling, because ICCM automatically averages the 5 highest GET determines ICCM will not use the value.

B. Incorrect. Plausible since candidate must know thermocouples fall low on an open, not high and ICCM will not use the value, because it automatically averages the 5 highest CET C. Correct.

D. Incorrect. Plausible since candidate must know thermocouples fall low on an open, not high.

Tuesday, March 20, 2012 2:45:02 PM 129

2012 NRC RO 01.7 InCore Temperature. Monitor System (ITM) 017A3.OlAbility to monitor automatic operation of the ITM system including: Indications of normal, natural, and interrupted circulation of RCS (CFR: 417 / 45.5)

Importance Rating: 3.6 3.8 Technical

Reference:

ICCM Student Text, Page 10, Rev 6, EOP-Users-Guide Page 31, Step 6.2, Rev 36 References to be provided: None Learning Objective: EOP Users Guide, EOP3-19 Obj. 4.a Question Origin: Bank CIT Development 017 K6.01 Comments:

Tier/Group: T2G2 Tuesday, March 20, 2012 2:45:02 PM 130

2012 NRC RO 20-12 NRC RO-060 Given the following plant conditions:

- The plant is operating at 100% power

- ARR Fan S-lA is in operation in Containment

- The following alarm is received:

ALB-28-1-4, CNMT BLDG ARR CHAR FILTER TROUBLE

- ARR Fan S-lA switch indication is OFF and ARR Fan S-lB switch indication is ON Which ONE of the following (1) describes the cause of the condition AND (2) the procedure reference to correct this event?

A. (1) High charcoal filter AP (2) FPP-002, Fire Emergency B. (1) High charcoal filter zP (2) AOP-036, Safe Shutdown Following A Fire C (1) High charcoal filter temperature (2) FPP-002, Fire Emergency D. (1) High charcoal filter temperature (2) AOP-036, Safe Shutdown Following A Fire Tuesday, March 20, 2012 2:45:02 PM 131

2012 NRC RO Plausibility and Answer Analysis Reason answer is correct: ARR charcoal filter trouble annunicator alarms when the temperature sensor exceeds 180°F with a reflash at 280°F. The high temperature causes the runnning fan to trip on the pre-high temperature alarm (at 180°F). The standby fan unit starts 12 seconds after the in-service fan unit trips. The question stem states that the BOP reviewed the APP and one could assume that this will take more than 12 seconds to pull the APP, read the APP and review the fan indications which would be enough time to allow the auto start of the standby fan.

A. Incorrect. Plausible because the annunciator is a charcoal filter alarm.

B. Incorrect. Plausible because the standby fan is running. The standby fan auto starts in 12 seconds if the operational fan trips but this is not a correct answer because if the fan were to have tripped on overload window 1-5 CNMT BLDG ARR FANS Si LOWFLOW- O/L would have alarmed.

C. Correct.

D. Incorrect. Plausible because the standby fan is running. The standby fan would auto start in 12 seconds if low flow were sensed (<8000 CFM) but this did not occur because annunciator window 1-5 CNMT BLDG ARR FANS Si LOW FLOW O/L is not in alarm.

Tuesday, March 20, 2012 2:45:02 PM 132

2012 NRC RO 027 Containment 1oIine Removal System 027A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the CIRS; and (b) based on those predictions, use Procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High temperature in the filter system (CFR: 41.5/43.5 / 45.3/ 45.13)

Importance Rating: 3.0 3.3 Technical

Reference:

APP-ALB-028-1-4, Page 5, Rev 15 References to be provided: None Learning Objective: Plant Procedures- Fire protection, PP2-15 Obj. 1 Question Origin: New Comments:

Tier/Group: T2G2 Tuesday, March 20, 2012 2:45:02 PM 133

2012 NRC RO 6L212NRcRoo61 Which ONE of the following completes the statements below?

Containment Pre-entry Purge Makeup Fan, AH-81B will trip when Containment pressure increases to (1) INWG.

CNMT Vacuum Relief, 1CB-6 receives an open signal at (2) INWG.

A. (1)-.250 (2) -2.0 B. (1)-.250 (2) -2.25 C. (1)-.225 (2) -2.0 D (1)-.225 (2) -2.25 Plausibility and Answer Analysis Reason answer is correct: The vacuum relief valves open to relieve containment vacuum when the actuation setpoint of -2.25 inches w.g. is reached.

A. Incorrect. Plausible because the first part of the answer is slightly lower than the acutal setpoint and the second part is the setpoint at which 1CB-2 would auto close at.

B. Incorrect. Plausible because the first part of the answer is slightly lower than the acutal the setpoint C. Incorrect. Plausible the first part of the answer is slightly lower than the actual setpoint but the second half of the answer is correct.

13. Correct.

Tuesday, March 20, 2012 2:45:02 PM 1 34

2012 NRC RO 029 Containment Purge Systam (CPS -

029K4.02 Knowledge of design feature(s) and/or interlock(s) which provide for the following: Negative pressure in containment (CFR: 41.7)

Importance Rating: 2.9 3.1 Technical

Reference:

CVS Student Text, Page, 25 and 28, Rev. 4, OP-168, Page 13, Rev 32 References to be provided: None Learning Objective: Containment Ventilation System Obj. 4 Question Origin: Bank OIT Development 029 K4.02 2 Comments:

Tier/Group: T2G2 Tuesday, March 20, 2012 2:45:02 PM 135

2012 NRC RO 62.2012NRcR0062 - *- . -

Given the following conditions:

- The plant is operating at 100% power

- The suction pipe from Spent Fuel Pool B to the Spent Fuel Pool Cooling Pump completely severs.

Which ONE of the following completes the statements below?

Level in the Spent Fuel Pool will decrease and stabilize at (1) feet above the fuel assemblies.

Spent Fuel Pool area radiation monitor RM-1 FR-3566A-SA is in HIGH alarm and monitor RM-1 FR-3567B-SB is in ALERT. This condition will cause (2) train(s) of Fuel Handling Ventilation Emergency Exhaust to automatically start.

A (1)18 (2) A B. (1)18 (2) both A and B C. (1)23 (2) A D. (1)23 (2) both A and B Tuesday, March 20, 2012 2:45:02 PM 136

2012 NRC RO PlausibllityandAnswerAnalysis Reason answer is correct: An anti siphon hole in the suction pipe prevents the Spent Fuel Pool from draining any lower than 5 feet below the normal level of 23 above the fuel. Any one of a trains ARMs in HIGH alarm in the FHB will start 1 train of FHB emergency exhaust.

Since only the A Train is in HIGH alarm the A train will auto start.

A. Correct.

B. Incorrect. Plausible because 18 feet is the correct level the Fuel Pool will drain down and only one Rad monitor from either train will shutdown both Normal Supply fan A and B C. Incorrect. Plausible because 23 feet is the correct level the Fuel Pool is required to be maintained above the Fuel by Tech Specs and the A train Exhaust fan will auto start D. Incorrect. Plausible because 23 feet is the correct level the Fuel Pool is required to be maintained above the Fuel by Tech Specs and only one Rad monitor from either train will shutdown both Normal Supply fan A and B Tuesday, March 20, 2012 2:45:02 PM 137

2012 NRC RO 033 Spent Fuel Pool Cooling System (SFPCS) 033A1 .02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Spent Fuel Pool Cooling System operating the controls including: Radiation monitoring systems (CFR: 41.5/45.5)

Importance Rating: 2.8 3.3 Technical

Reference:

FPC Student Text, Page 3, Rev 6, OP-170, section 8.1, Page 23, Rev 23, AOP-005-BD, 1.0 Discussion, Page 3, Rev 8 References to be provided: None Learning Objective: AOP-005, Radiation Monitors, AOP3-5 Obj. 3 Fuel Pool Cooling Obj. 7.a Question Origin: New Comments: None Tier/Group: T2G2 Tuesday, March 20, 2012 2:45:02 PM 138

2012 NRC RO

63. 201-2 NRC RO-063 -

Given the following plant conditions:

- The plant is operating at 7% Reactor Power

- SG level control is FRBPVs in automatic

- AFW pumps are all secured Which of the following completes the statement below?

If LT-496, SG C level channel 3, fails low, SG C level will INITIALLY increase to (1) AND a (2) will occur.

(Assume NO operator action)

A (1)78%

(2) MFWI B. (1)78%

(2) MSLI C. (1)73%

(2) MFWI D. (1)73%

(2) MSLI Plausibility and Answer Analysis Reason answer is correct: The SGWLC system will attempt to raise the failed SG level until a valid High-High level is reached on the SG C. When 2 of 4 SG levels channels are above 78%

on 1 SG P-14 trips the MFP and isolates FW.

A. Correct.

B. Incorrect. Plausible because P- 14 is activated at 78% level, to prevent overfilling the MSLs but the MSLI is not actuated from this signal C. Incorrect. Plausible because 73% is the operations recommend trip limit established during manual control of SG level, if P- 14 was actuated then a MFWI would result D. Incorrect. Plausible because 73% is the operations recommend trip limit established during manual control of SG level, the P- 14 is designed to prevent overfilling the MSLs but the MSLI is not actuated from this signal Tuesday, March 20, 2012 2:45:02 PM 139

2012 NRC RO 0-35 Steam Generator System (S/GS) 035K6.03 Knowledge of the effect of a loss or malfunction on the following will have on the S/GS: S/G level detector (CFR: 41.7/ 45.7)

Importance Rating: 2.6 3.0 Technical

Reference:

APP-ALB-014, Window 6-3B, Page 38, Rev 21 References to be provided: None Learning Objective: Steam Generator Water Level Control Obj. 4 & 6 Question Origin: Bank OIT Development, 035K6.03 Comments: 2002 Audit RO Tier/Group: T2G2 Tuesday, March 20, 2012 2:45:02 PM 140

2012 NRC RO

64. 2012 NRC R() 064 -

Given the following plant conditions:

- The plant is operating at 100%

- Treated L&HS Tank A contains radioactive liquid that is required to be released.

lAW OP-120.10.04, the Treated L&HS Tank A should be discharged to the (1) because the Disharge Permit is based on (2) , lowering the release activity level below the allowable concentrations for radiation exposure to the public.

A. (1) Waste Neutralization Settling basin (2) maintaining a minimum dilution water flow rate B. (1) Waste Neutralization Settling basin (2) maximizing the decay time for radioactive liquid C (1) Cooling Tower Blowdown line (2) maintaining a minimum dilution water flow rate D. (1) Cooling Tower Blowdown line (2) maximizing the decay time for radioactive liquid Plausibility and Answer Analysis Reason answer is correct: lAW OP-120.10.04 step 27, the Treated L&HS tank discharge valves should be placed in the Cooling Tower 3LHS-301 position. The caution prior to this step states that the Discharge Permit is based on the dilution waer from the Cooling Tower Blowdown.

A. Incorrect. Plausible because discharge to the Waste Nuetralization basin allows longer time for waste products to decay, but would also cause a buildup of contamination.

B. Incorrect. Plausible because discharge to the Waste Nuetralization basin allows longer time for waste products to decay, but would also cause a buildup of contamination.

C. Correct.

D. Incorrect. Plausible because discharge is correctly aligned to the cooling tower blowdown line, but the discharge permit is based on a minimum dilution flow from the coo/mg tower.

Tuesday, March 20, 2012 2:45:03 PM 141

2012 NRC RO 068 Liquid Radwaste System (LRS) 068K5.04 Knowledge of the operational implication of the following concepts as they apply to the Liquid Radwaste System: Biological hazards of radiation and the resulting goal of ALARA (CFR: 41.5 / 45.7)

Importance Rating: 3.2 3.5 Technical

Reference:

OP-120.10.04, Section 5.2.2, Step 27, Page 23, Rev 33 ODCM, Section 2.1.1, Page 2-3, Rev 6 References to be provided: None Learning Objective: Liquid Waste Processing System Obj. 2.c Question Origin: New Comments:

Tier/Group: T2G2 Tuesday, March 20, 2012 2:45:03 PM 142

2012 NRC RO 652o12NRCR&O65 -

Given the following plant conditions:

- The plant is operating at 100%

- Instrument Air header pressure is 70 psig and lowering slowly Which ONE of the following describes (1) the location where 1 SA-506, Instrument Air from Service Air Isolation Valve, position is indicated, AND (2) the status of the Instrument Air Header Low Pressure alarm?

A. (1)SLB-3 (2) Alarm is NOT lit.

B. (1)AEP-1 (2) Alarm is NOT lit.

C (1)SLB-3 (2) Alarm is lit.

D. (1)AEP-1 (2) Alarm is lit.

Plausibility and Answer Analysis Reason answer is correct: 1SA-506 is indicated on SLB-3 in the MCB, Instrument Air Low Pressure annunciator ALB-002-8-1 alarms when IA pressure decreases to 75 psig.

A. Incorrect. Plausible since the first part is correcl, the second part is plausible if the alarm setpoint was confused for the automatic isolation of the Feedwater Regulating valves at 60 psig.

B. Incorrect. Plausible because AEP- 1 has indications for various Dampers that are supplied by Instrument Air, the second part is plausible if the alarm setpoint was confused for the automatic isolation of the Feedwater Regulating valves at 60 psig.

C. Correct.

D. Incorrect. Plausible because AEP- 1 has indications for various Dampers that are supplied by Instrument Air, the second part is correct.

Tuesday, March 20, 2012 2:45:03 PM 143

2012 NRC RO 079 Station Air System (SAS) - -

079A4.01 Ability to manually operate and/or monitor in the control room: Cross-tie valves with lAS (CFR: 41.7/ 45.5 to 45.8)

Importance Rating: 2.7 2.7 Technical

Reference:

AOP-01 7 Basis Document, Section 3.0 Step 4, Page 11, Rev 10 and ALB-002-8-1, Page 38, Rev. 43 References to be provided: None Learning Objective: AOP-01 7, Loss of Instrument Air, AOP3-1 7 Obj. 2.a Question Origin: Bank OIT Exam Development, 079K1 .01 Comments: 2009A NRC RO Tier/Group: T2G2 Tuesday, March 20, 2012 2:45:03 PM 144

2012 NRC RO

-66. 2012 NRC RO 066 - - -- -

Which ONE of the following would require suspension of CORE ALTERATIONS?

A. Train A Fuel Handling Building Emergency Exhaust unit is OPERABLE and in operation; Train B has just been declared INOPERABLE.

B Direct communication is lost between the Control Room and personnel at the refueling station in Containment.

C. Reactor Cavity water level is 23 feet 3 inches above the vessel flange with only one RHR loop operable and in operation.

D. The Containment equipment hatch can be closed with only 8 bolts.

Plausibility and Answer Analysis Reason answer is correct:PLP-1 14 Att. 2 Section 3.0 Direct communications shall be maintained between the control room and personnel at the refueling station in con tainment.

These are all Tech Spec immediate actions for a certain event. They cause LCO actions to be completed immediately but not all apply to core alterations or are already in an alignment that is allowed.

A. Incorrect. Alterations involving movement of fuel within the storage pool or crane operation with loads over the storage pool are not allowed but Core Alterations are not affected. (TS 3.9.12)

B. Correct.

C. Incorrect. TS 3.9.8.1 At least one residual heat removal (RHR) loop shall be OPERABLE and in operation in MODE 6 with irradiated fuel in the vessel when the water level above the top of the reactor vessel flange is greater than or equal to 23 feet D. Incorrect. TS 3.9.4.this meets the requirement and will not require suspension because the equipment door is cabable of being closed and only needs to be held in place by a minimum of four bolts.

Tuesday, March 20, 2012 2:45:03 PM 145

2012 NRC RO 2.1 Conduct of Opefations - -

G2.1 .36 Knowledge of procedures and limitations involved in core alterations.

(CFR: 41.10/43.6 / 45.7)

Importance Rating: 3.0 4.1 Technical

Reference:

PLP-1 14 Relocated Technical Specifications, Attachment 2, Page 9, Rev 21 References to be provided: None Learning Objective: Technical Specifications, TS2.0 Obj. 2 Question Origin: CIT Development Bank G2.1 .36 001 Comments:

Tier/Group: T3 Tuesday, March 20, 2012 2:45:03 PM 146

2012 NRC RO

67. 2012 NRC RO-O67 - -. -

Given the following plant conditions:

- The plant is operating at 90%

- VCT level is 38%

- VCT Level Transmitter, LT-i 12 fails HIGH Which ONE of the following completes the statement below?

(Assume NO operator action)

Actual VCT level on LI-i 15 would initially (1) AND 1CS-120 (LCV-1 15A),

Letdown VCT/Hold Up Tank will (2)

A (1) lower (2) reposition to the RHT B. (i)lower (2) remain aligned to the VCT C. (1) remain unchanged (2) reposition to the RHT D. (1) remain unchanged (2) remain aligned to the VCT Plausibility and Answer Analysis Reason answer is correct: Due to the failure, LID would be diverted and auto makeup to the VCT would occur. The VCT level would continue to drop until level reaches 20% on Ll-115.

A. Correct.

B. Incorrect. At 5% on LT- 112 AND 115 the CSIP suctions would auto swap to the RWST thus making this answer choice incorrect. This swapover would close the VCT outlets, which would cause the VCT level to stabilize at approximately 5%. Plausible because the applicant must know that it takes a 2/2 coincidence to initiate the auto swapover.

C. Incorrect. Same reasons as B above. Plausible because at 10% the auto swapover signal clears. The applicant may associate the level at which the signal clears with the level at which auto swapover occurs.

D. Incorrect. Same reasons as B above. Plausible because this would be the correct answer if L T- 112 were to fail high.

Tuesday, March 20, 2012 2:45:03 PM 147

2012 NRC RO 2.1 Conduct of- Opecations G2.1 .45 Ability to identify and interpret diverse indications to validate the response of another indication.

(CFR: 41.7/43.5/45.4)

Importance Rating: 4.3 4.3 Technical

Reference:

AOP-003-BD, Step 4, Page 8, Rev 8 References to be provided: None Learning Objective: AOP-003, Malfunction of Reator Makeup Water System, AOP3-3 Obj. 2.a & 4.a Question Origin: New Comments:

Tier/Group: T3 Tuesday, March 20, 2012 2:45:03 PM 148

2012 NRC RO 6& 201-2 NRC RO 068 - -

Given the following plant conditions:

- Mode 6, Refueling is in progress Which ONE of the following lists the Key Safety Functions per OMP-003, Outage Shutdown Risk Management?

A. Subcriticality, Core Cooling, Integrity, Inventory, Containment B Decay Heat Removal, Inventory, Electrical Power, Reactivity Control, Containment C. Residual Heat Removal, Inventory, Cavity Level, Electrical Power, Auxiliary Feed Water D. Decay Heat Removal, Reactivity Control, Integrity, Containment, Residual Heat Removal Plausibility and Answer Analysis Reason answer is correct: Per OMP-003 the key safety functions when shutdown are Decay Heat Removal, Inventory, Electrical Power, Reactivity Control, Containment A. Incorrect. Plausible because the catagories listed are those for the CSFST 5 B. Correct C. Incorrect. Plausible because the categories listed are subcategories of the key safety functions while shutdown.

D. Incorrect. Plausible because the catagories listed are the key safety functions while determining on-line risk Tuesday, March 20, 2012 2:45:03 PM 149

2012 NRC RO 2.2 Equipment Control -

G2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.

(CFR: 41.10/43.5/45.13)

Importance Rating: 2.6 3.9 Technical

Reference:

OMP-003, 5.2.1.13, Page 14, Rev 34 OMA-NGGC-0203, Page 5, Rev 1 References to be provided: None Learning Objective: None Question Origin: Bank LORNRCBNK, pp-i 8.30 R3 Comments:

Tier/Group: T3 Tuesday, March 20, 2012 2:45:03 PM 150

2012 NRC RO

69. 20-12 NRC RO-069 - -- -- -

Given the following plant conditions:

- The plant is operating at the POAH, per GP-005, Power Operations

- Master Pressure controller PK-444A.1 malfunctions resulting in rising RCS pressure Which ONE of the following completes the statement below?

lAW Technical Specifications, the action for exceeding a Reactor Coolant System pressure of (1) requires the crewto (2)

A (1)2735 psig (2) be in HOT STANDBY with the Reactor Coolant System pressure within its limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. (1)2485 psig (2) be in HOT STANDBY with the Reactor Coolant System pressure within its limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months C. (1) 2735 psig (2) reduce the Reactor Coolant System pressure within its limits within 5 minutes D. (1) 2485 psig (2) reduce the Reactor Coolant System pressure within its limits within 5 minutes Plausibility and Answer Analysis Reason answer is correct: lAW T.S. 2.1.2 the RCS pressure shall not exceed 2735 in Modes 1, 2, 3, 4, and 5 except for hydrostatic testing. The action for exceeding this limit in Modes 1 and 2 is to restore below the limit and be in Mode 3 (Hot Standby) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

A. Correct.

B. Incorrect. Plausible because the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action is correct for exceeding the limit but the pressure is the value for the Pressurizer safeties to lift C. Incorrect. Plausible because the pressure is the correct value not to be exceeded, but 5 minute action is correct for exceeding the limit when in Modes 3, 4 and 5.

D. Incorrect. Plausible because the pressure is the value for the Pressurizer safeties to lift, and the 5 minute action is correct for exceeding the limit when in Modes 3, 4 and 5.

Tuesday, March 20, 2012 2:45:03 PM 151

2012 NRC RO 2.2 Equipment Control G2.2.38 Knowledge of conditions and limitations in the facility license.

(CFR: 41.7/41.10/43.1 /45.13)

Importance Rating: 3.6 4.5 Technical

Reference:

Tech Specs, 2.1.2 References to be provided: None Learning Objective: Technical Specifications, TS2.0 Obj. 2 Question Origin: New Comments:

Tier/Group: T3 Tuesday, March 20, 2012 2:45:03 PM 152

2012 NRC RO

- -702o12NRcRocI7o - -

After completing resin transfer of the CVCS cation demineralizer and initial flushing of the lines, radiation levels around the piping have not returned to their expected levels.

Which ONE of the following completes the statement below?

lAW OP 120.04, Spent Resin Storage And Transfer System, the can authorize additional flush times for these lines to enhance ALARA principles.

A. Radwaste Specialist B Control Room Supervisor C. Work Control Center SRO D. Health Physics Supervisor Plausibility and Answer Analysis Reason answer is correct: Per OP-i 20.04 precautionand limitation 5, extended flush times may be approved by the Control Room Suprervisor (Unit SCO) to reduce radiation levels to enhance ALARA principles A. Incorrect. Plausible because the Radwaste Specialist coordinates with radiation protection to ensure radwaste activities maintain site dose ALARA B. Correct.

C. Incorrect. Plausible because the WCC SRO authorizes and signs for the start of work maintenance activities and supeavises WCC activities which normally includes transfering spent resin D. Incorrect. Plausible because the radiation protection department surveys and monitors site dose levels and creates RWP which are approved by the RP Supervisor Tuesday, March 20, 2012 2:45:03 PM 153

2012 NRC RO 2.3 Radiation Control G2.3.12 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.

(CFR: 41.12/45.9/45.10)

Importance Rating: 3.2 3.7 Technical

Reference:

OP1 20.04, P&L # 4.0.5, Page 8, Rev 26 References to be provided: None Learning Objective: None Question Origin: Bank, OlT Development, SWPS 9-0-A5 Comments: None Tier/Group: T3 Tuesday, March 20, 2012 2:45:03 PM 154

2012 NRC P0 7t2o12NRcRo71 - -

Given the following plant conditions:

- The plant is operating at 100% Reactor Power

- ALB-10-4-5, RAD MONITOR SYSTEM TROUBLE has alarmed

- Both REM-Ol LT-3502ASA, CNMT RCS Leak Detection Monitor, AND RM-1CR-3561A-SA, CNMT Vent Isolation are in High Alarm Which ONE of the following set of actions are required lAW annunciator panel procedures and AO P-005, Pad iation Monitoring System?

A Verify Normal Containment Purge isolated; Monitor PRZ level and CNMT conditions B. Verify Normal Containment Purge isolated; Verify equipment alignment lAW OMM-004, Post-Trip/Safeguards Actuation Review C. Verify Containment Ventilation Isolation; Monitor PPZ level and CNMT conditions D. Verify Containment Ventilation Isolation; Verify equipment alignment lAW OMM-004, Post-Trip/Safeguards Actuation Review Tuesday, March 20, 2012 2:45:03 PM 155

2012 NRC RO PlaibilityandAnswerAnalysis Reason answer is correct: A Containment Purge Isolation signal is generated when REM-O1LT-3502ASA is in high alarm. IA WAOP-005 the operator should verify normal containment purge is isolated and then monitor for indications of primary leakage.

A. Correct.

B. Incorrect. Plausible because the first part is correct but the second part is only performed if a Containment Ventilation Isolation has actuated. A Containment Ventilation Isolation has not occurred. It takes 2 of 4 Cnmt RCS Leak Detection Monitors in High Alarm to cause the isolation signal.

Only one of four monitors are in High Alarm.

C. Incorrect. Plausible because the candidate may confuse a Containment Purge Isolation coincidence signal (1/1 leak detection monitors) with a Containment Ventilation Isolation coincidence signal (2/4 Cnmt Vent Isolation monitors). The second part of the answer is correct.

D. Incorrect. Plausible because the candidate may confuse a Containment Purge Isolation coincidence signal (1/1 leak detection monitors) with a Containment Ventilation Isolation coincidence signal (2/4 Cnmt Vent Isolation monitors). The second part would be correct if the Cnmt Vent Isolation signal had occurred.

Tuesday, March 20, 2012 2:45:03 PM 156

2012 NRC RO 23 Radiation Control G2.3.13 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 filters, etc.

(CFR: 41.12/43.4/45.9/45.10)

Importance Rating: 3.4 3.8 Technical

Reference:

AOP-005 Attachment 1, Step 3, Page 9, Rev. 27 References to be provided: None Learning Objective: AOP-005, Radiation Monitors, AOP3-5 Obj. 4.a & 3 Question Origin: Bank CIT Development G2.3.13 002 Comments:

Tier/Group: T3 Tuesday, March 20, 2012 2:45:03 PM 157

2012 NRC RO 72 2012 NRC R0072 - -

Which ONE of the following identifies (1) the 10 CFR 20 annual limit for TEDE AND (2) identifies the Emergency Exposure Limit for lifesaving activities lAW PEP-330, Radiological Consequences?

A. (1)4rem (2) 10 rem B. (1)5rem (2) 10 rem C. (1)4rem (2) 25 rem D (1)5 rem (2) 25 rem Plausibility and Answer Analysis Reason answer is correct: Per PEP-330 Attachment 1, the annual limit for TEDE is 5 REM and the limit for life saving activities is 25 REM A. Incorrect. Plausible because 4 REM is the Progress Energy dose limit per DQS-NGGC-004 for combined utility dose, 10 REM is the PEP-330 limit for protecting valuable property B. Incorrect. Plausible because 5 REM is the correct value for the annual limit for TEDE, 10 REM is the PEP-330 limit for protecting valuable property C. Incorrect. Plausible because 4 REM is the Progress Energy dose limit per DOS-NGGC-004 for combined utility dose, and 25 REM is the correct value for life saving activities D. Correct.

Tuesday, March 20, 2012 2:45:03 PM 1 58

2012 NRC RO 23RadiationControl G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

(CFR: 41.12 /43.4/ 45.10)

Importance Rating: 3.2 3.7 Technical

Reference:

PEP-330, Attachment 1, Page 17, Rev 9 References to be provided: None Learning Objective: Health Physics Administrative Guidelines and Procedures, PP3-7 Obj. 1 .h & 1 .a Question Origin: Bank OIT Development, G2.3.4 1 Comments: None Tier/Group: T3 Tuesday, March 20, 2012 2:45:03 PM 159

2012 NRC RO 73.2nl2NRcRuo73 Given the following plant conditions:

- The plant was operating at 100% Reactor Power

- A loss of Component Cooling Water has occurred.

- The Reactor was tripped lAW AOP-01 4, Loss of Component Cooling Water

- The crew has entered PATH-i Which ONE of the following describes the continued use of AOP-0i 4, Loss of Component Cooling Water?

A. Use of AOP-0i4 is NOT allowed during EOP performance.

B. May ONLY be used concurrently with actions of PATH-i, and ONLY where directed by the procedure.

C May be used concurrently with EOPs ONLY if referencing the AOP does NOT result in delaying accident mitigation.

D. May be used concurrently as necessary under ALL conditions of EOP use.

Plausibility and Answer Analysis Reason answer is correct: Per the EOP Users guide it is acceptable to use and AOP in conjunction with an EOP provided the AOP does not delay the implementation of the EOP mitigating strategy.

A. Incorrect. Plausible because AOP-014 may be used concurrently on an as needed basis, but only if the EOP implementation is not delayed.

B. Incorrect. Plausible because Path-i May direct the use of AOP-014, but other EPPs may direct the use of AOPs, EPP-004 for instance C. Correct.

D. Incorrect. Plausible because AOP-014 would be used if steps performed from the AOP would not result in delays for EPP use, 1tAOP-014 does delay EPP usage it would not be performed Tuesday, March 20, 2012 2:45:03 PM 160

2012 NRC RO Emergency Procedures / Plan G2.4.1 1 Knowledge of abnormal condition procedures.

(CFR: 41.10/43.5 I 45.13)

Importance Rating: 4.0 4.2 Technical

Reference:

EOP Users Guide, Page 10, Rev 34 References to be provided: None Learning Objective: EOP Users Guide, EOP3-19, Obj. 1.b Question Origin: Bank CIT Development G2.4.1 1 001 Comments:

Tier/Group: T3 Tuesday, March 20, 2012 2:45:03 PM 161

2012 NRC RO 74.2 12-NRcROO74 - -

Given the following plant conditions:

- Mode 6, Refueling in progress

- A fire occurred inside Containment.

Per FPP-003, Fire Investigation Report, who is responsible for initiating the Fire Investigation Report and providing it to the Shift Manager?

A. Refueling SRO B. Control Room Supervisor C Site Incident Commander D. Containment Coordinator Plausibility and Answer Analysis Reason answer is correct: Per FPP-003 the Site Incident Commander shall initiate a report following securing from a fire response.

A. Incorrect. Plausible because the plant is in Mode 6 and the refueling SRO is responsible for monitoring activities that effect refueling the vessel B. Incorrect. Plausible because the control room is contacted via the 5555 emergency line to dispatch the fire brigade C. Correct.

0. Incorrect. Plausible because the plant is in Mode 6 and the containment cooridinator is resposible for monitoring containment activities Tuesday, March 20, 2012 2:45:03 PM 162

2012 NRC RO 2.4 Eme-rncy ProGedures! Plan G2.4.25 Knowledge of fire protection procedures.

(CFR: 41.10/43.5/ 45.13)

Importance Rating: 3.3 3.7 Technical

Reference:

FPP-003, Responsibilites, Page 3, Rev 8 References to be provided: None Learning Objective: None Question Origin: OIT Development Bank G2.4.26 002 Comments:

Tier/Group: T3 Tuesday, March 20, 2012 2:45:03 PM 163

2012 NRC RO 75.2o12NRcRoo75 - -

Which ONE of the following is (1) the LOWEST classification that REQUIRES Accountability to be completed AND (2) the LOWEST classification that REQUIRES activation of the Emergency Response Organization?

A. (1)Alert (2) Alert B. (1)Alert (2) Site Area Emergency C (1) Site Area Emergency (2) Alert D. (1) Site Area Emergency (2) Site Area Emergency Plausibility and Answer Analysis Reason answer is correct: Per PEP-230 Attachment 1 if the event classification is an Alert or Higher activate the ERO using the Everbridge system, if the event classification is a Site Area Emergency or General Emergency ensure performance of Accountability per PEP-350 A. Incorrect. Plausible because the lowest event classification is an Alert or higher for the ERO to be activated and an announcement is made for all non ERO personnel to exit the Protected area and report to the Admin Building at this time.

B. Incorrect. Plausible because the lowest event classification that requires ERO activation and the lowest event classification that requires performance of Accountability are reversed.

C. Correct.

0. Incorrect. Plausible because the lowest event classification that requires performance of Accountability is a Site Area Emergency and the requirement for ERO personnel to report to their designated facility is announced for the first time if entered from an Unusual Event or No Event classification.

Tuesday, March 20, 2012 2:45:04 PM 164

2012 NRC RO a4Emergency ProceIuresI Plan G2.4.29 Knowledge of the emergency plan.

(CFR: 41.10/43.5/45.11)

Importance Rating: 3.1 4.4 Technical

Reference:

PEP-230, Attachment 3, Page 35-36, Rev 19 References to be provided: None Learning Objective: Emergency Action levels, EP2-0 Obj. 4.a (weak)

Question Origin: Bank G2.4.29 Comments: New Tier/Group: T3 You have completed the test!

Tuesday, March 20, 2012 2:45:04 PM 165

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