Text

Draft - SRO Written Exam (Folder 2)
	ML051030205
Person / Time
Site:	Beaver Valley
Issue date:	12/27/2004
From:	Hynes C; FirstEnergy Nuclear Operating Co
To:	Conte R; NRC/RGN-I/DRS/OSB
	Conte R
References
	Download: ML051030205 (223)
	v • d • e

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

-. Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 KIA ## 003 K5.02 Importance Rating 2.8 Knowledge of the operational implications of the following concepts as they apply to the RCPS:Effects of RCP coastdown on RCS parameters Proposed Question: Common 1 Which ONE of the following describes a function of the flywheel on the RCPs?

A. Prolongs RCP coastdown time to aid in maintaining loop flow thus maintaining hot channel factors at an acceptable level during certain loss of RCS flow events.

B. Prolongs RCP coastdown time to aid in maintaining loop flow thus maintaining DNBR within acceptable limits during certain loss of flow events.

C. Maintains constant RCP speed, minimizing the potential for spurious RCS low flow reactor trips and maintaining hot channel factors at an acceptable level during power operation.

D. Maintains constant RCP speed, minimizing the potential for spurious RCS low flow reactor trips and maintaining DNBR within limits during power operation.

Proposed Answer: B Explanation (Optional):

A. Incorrect. Flywheel designed to provide inertia to aid DNBR, not specifically for hot channel factors Hot channel factors are affected by control rods.

B. Correct.

C. Incorrect. Flywheel more important for loss of flow, where RCP coastdown time is important for heat removal. Hot channel factors are affected by control rods.

D. Incorrect. RCS flow is a consideration for DNBR, but at rated RCP speed, the flywheel inertia is insignificant in performing the function of maintaining flow.

Technical Reference(s): 20M-1.1 B, 2SQS-6.3 (Attach if not oreviouslv orovided)

I Proposed references to be provided to applicants during examination: NONE NUREG-1021, Revision 9 1 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 2SQS-6.3 Objective 2 (As available)

Question Source: Bank #

Modified Bank # X (Note changes or attach parent)

New Question History: BVPS-2 NRC Exam 2002 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 2 BVPS Unit 2

BVPS-1 and BVPS-2 2005 NRC Examination Modified Test Items 2005 Question 1 Which ONE of the following is the basis for the underfrequency trip of the RCPs?

A. Ensures that the RCP motor windings will not overheat due to the increased 12R losses at reduced operating frequencies.

B. Ensures that the inertia of the RCP flywheel will aid in maintaining loop flow thus maintaining DNBR within acceptable limits.

C. Aids in maintaining grid stability by reducing grid loading demands after the Normal 4KV buses have transferred to the Station System Service Transformers.

D. Ensures that the RCPs are not operated at critical speeds which could result in severe vibrations and catastrophic failure of the RCP or an RCS LOCA.

Answer: B This item was question 2 on the BVPS-2 2002 NRC Exam

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

-- Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 003 K3.02 Importance Rating 3.5 Knowledge of the effect that a loss or malfunction of the RCPS will have on the following. S/G Proposed Question: Common 2 Given the following conditions:

The Unit is at 100% power with all systems in NSA.

2RCSP21 A, Reactor Coolant Pump has tripped on overcurrent due to an apparent shaft seizure.

A reactor trip occurs.

Which ONE of the following describes SG response to the event 3 (THREE) minutes following the trip?

SG 21 A level is...

A. Lower than 21 B and 21 C SG due to SG shrink when the RCP tripped.

B. Higher than 21 B and 21 C SG due to less heat removal from 21 A SG.

C. Higher than 21 B and 21 C SG due to SG swell when the RCP tripped D. Lower than 21 B and 21C SG due to the rise in Tcold on the idle loop.

Proposed Answer: B Explanation (Optional):

A. Incorrect. Effects of shrink on SG level are minimal.

B. Correct. Less heat input means less evaporation of SG contents, therefore, same feed, higher level.

C. Incorrect. Effects of SG swell are minimal, but in this case, there is no SG swell.

D. Incorrect. Delta T on the idle loop will go to 0, but Tcold will be at no-load temperature.

Technical Ref erenee(s) : Simulator, T&AA (Attach if not previously provided)

NUREG-1021, Revision 9 3 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: None Learning Objective: 2SQS-6.3 Objective 6 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Cornments:

NUREG-1021, Revision 9 4 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

.... ExaminationOutline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 004 A4.12 Importance Rating 3.8 Ability to manually operate andor monitor in the control room: Boration/dilution batch control Proposed Question: Common 3 Given the following:

The Unit is at 90% power.

All systems are in their at-power, NSA configurations.

Tavg is rising due to a xenon transient.

You are directed to adjust RCS temperature using the Reactor Makeup Control System Which ONE of the following is the mode of makeup control required and the corresponding valve lineup?

A. Borate:

2CHS'FCV113A, Boric Acid Flow Control Valve - OPEN 2CHSFCV114A ,Primary Water Flow Control Valve - CLOSED 2CHS*FCV1138, Makeup Stop Valve To Charging Pump Suction - OPEN 2CHStFCV114B, Makeup Stop Valve To VCT - CLOSED B. Borate:

2CHS'FCVl13A, Boric Acid Flow Control Valve - OPEN 2CHS*FCV114A ,Primary Water Flow Control Valve - CLOSED 2CHSFCV1138, Makeup Stop Valve To Charging Pump Suction - CLOSED 2CHSFCV1148, Makeup Stop Valve To VCT - OPEN C. Dilute:

2CHStFCV113A, Boric Acid Flow Control Valve - OPEN 2CHS'FCVl14A ,Primary Water Flow Control Valve - OPEN 2CHStFCV113B, Makeup Stop Valve To Charging Pump Suction - OPEN 2CHS'FCVll4B, Makeup Stop Valve To VCT - CLOSED D. Dilute:

2CHS'FCVll3A, Boric Acid Flow Control Valve - CLOSED 2CHS*FCVl14A ,Primary Water Flow Control Valve - OPEN 2CHS*FCV113B, Makeup Stop Valve To Charging Pump Suction - CLOSED 2CHStFCV114B, Makeup Stop Valve To VCT - OPEN Proposed Answer: A NUREG-1021. Revision 9 5 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Explanation (Optional):

A. Correct. Boration is required for Tavg rising. Valve lineup is correct.

B. Incorrect. Although boration is required, FCVll3B and F C V l l 4 B are listed in the incorrect positions.

C . Incorrect. Dilution is not required, and FCVl14A is in the incorrect position.

D. Incorrect. Dilution is not required, and each valve is in opposite of its correct position Technical Reference(s): 20M-7.4K (Attach if not previously provided)

Proposed references to be provided to applicants during examination: None Learning Objective: 2SQS-7.1 Objective 2 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

Facility Bank - Not previous NRC NUREG-1021, Revision 9 6 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA ## 005 A4.04 Importance Rating 3.1 Ability to manually operate and/or monitor in the control room Controls and indication for closed cooling water pumps Proposed Question: Common 4 Given the following conditions:

The Unit is in Mode 4.

RCS cooldown is in progress on RHS Train B.

[2CCP*P21A], Component Cooling Water Pump is running.

[2CCP*P21B], Component Cooling Water Pump is racked out.

[2CCP*P21C], Component Cooling Water Pump is in standby connected to the 2DF bus The following annunciators alarm in the Control Room:

[A6-1HI, PRI COMP COOLING WATER SYSTEM TROUBLE

[A6-1G], PRI COMP COOLING PUMP AUTO START/AUTO STOP The crew determines that the cause is a high CCP system demand, with NO other failures present.

Assuming all equipment operates as required and NO operator action, which ONE of the following describes the CCP pump control indication on Benchboard - B?

A. 2CCP*P21A green and bright white indication. 2CCP*P21C red indication.

6. 2CCP*P21A red indication. 2CCP*P21C green and bright white indication.

C. 2CCP*P21A green and bright white indication. 2CCPP21 C green and bright white indication.

D. 2CCP*P21A red indication. 2CCPP21 C red indication.

NUREG-1021, Revision 9 7 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: D Explanation (Optional):

A. Incorrect. Green and bright white would indicate a pump trip. Indications in stem of question do not provide for a trip, rather, just a low pressure.

B. Incorrect. Green and bright white would indicate a pump trip. Indications in stem of question do not provide for a trip, rather, just a low pressure.

C. Incorrect. Green and bright white would indicate a pump trip. Indications in stem of question do not provide for a trip, rather, just a low pressure.

D. Correct. Both pumps run; 21 C after auto starting.

Technical Reference(s): 2SQS-15.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-15.1 Objective 22 (As available)

Question Source: Bank ##

Modified Bank ## (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 8 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 005 K3.01 Importance Rating 3.9 Knowledge of the effect that a loss or malfunction of the RHRS will have on the following RCS Proposed Question: Common 5 Given the following conditions:

The plant is in Mode 4, cooling down for refueling.

RHS Pump [2RHS*P21A], and heat exchanger are in service.

The auto setpoint on [2RHS*FCV605A], RHR Heat Exchanger Bypass Flow Control Valve, drifts HIGH.

Which ONE of the following describes the effect, if any, on the RCS cooldown rate?

The RCS cooldown rate..

A. rises, due to the increased flow through the RHR heat exchanger B. lowers, due to the decreased total flow through the RHR system C. lowers! due to the decreased flow through the RHR heat exchanger D. rises, due to the increased total flow through the RHR system.

Proposed Answer: C Explanation (Optional):

A. Incorrect. Cooldown rate will not rise. If setpoint drifts high, more total flow will result in less RHR heat exchanger flow.

B. Incorrect. Rate does lower, but total flow increases, not decreases.

C. Correct. More bypass flow with a higher setpoint for total flow.

D. Incorrect. Temperature may rise, but the rate will slow down. Correct reason.

Technical Reference(s): 2SQS-10.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE NUREG-1021, Revision 9 9 BVPS Unit 2

~~ ~ ~

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 2SQS-10.1 Objective 7 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Com prehens ion or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 10 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 006 A2.12 Importance Rating 4.0 Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS: and (b) based on those predictions. use prwedures to correct, control, or mitigate the consequences of those malfunctions or operations. Conditions requiring actualion cif ECCS Proposed Question: Common 6 Given the following conditions:

A reactor trip has occurred.

The crew has transitioned to ES-0.1, Reactor Trip Response.

The following conditions develop:

RCS pressure is 1950 psig and lowering slowly.

[2CHS*P21A], Charging Pump is RUNNING.

[2CHS*P21B], Charging Pump is in STANDBY.

Charging flow is offscale HIGH.

Letdown is isolated.

RCS temperature is 542°F and slowly lowering.

0 PRZR level is 4% and lowering.

Which ONE of the following actions is required?

A. Initiate SI and continue in ES-0.1 B. Initiate SI and return to E-0, Reactor Trip Or Safety Injection.

C. Start HHSl pumps as required to maintain PRZR level and continue in ES-0.1.

D. Start HHSl pumps as required to maintain PRZR level and return to E-0.

Proposed Answer: B Explanation (Optional):

NUREG-1021, Revision 9 11 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet A. Incorrect. While the action is correct, the crew will not remain in ES-0.1.

B. Correct. PRZR level is below the minimum left hand page requiring SI actuation.

C. Incorrect. Only start HHSl as needed if the crew is in a reduction or termination of SI sequence. Since it has not initiated, this action would be inappropriate.

D. Incorrect. Procedure transition is correct, but the action is incorrect.

Technical Reference(s): ES-0.1 Foldout (Left Hand (Attach if not previously provided)

Page)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-53.2, Objective 4 (As available)

Question Source: Bank #

Modified Bank # X (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

Robinson 2004 NRC Exam NUREG-1021. Revision 9 12 BVPS Unit 2

BVPS-1 and BVPS-2 2005 NRC Examination Modified Test Items 2005 Question 6 L

See Attached LXR question file

dJa m QUESTIONS REPORT for RETAKE SRO REV 2 sm

1. 006 A? I ? 001 @Vtt=& 6 Given the following conditions:

L A reactor trip has occurred. The crew has transitioned to EPP-4, Reactor Trip Response.

The following conditions exist:

RCS pressure is 1950 psig and decreasing slowly.

All Available Charging pumps are available.

Letdown is isolated.

Pressurizer level is 12% and decreasing at a rate of 4%/min.

Which ONE (1) of the following actions is required?

A. Initiate SI and continue in EPP-4.

Bt, Initiate SI and return to PATH-I.

C. Start CSlPs as required to maintain pressurizer level and continue in EPP-4.

D. Start CSlPs as required to maintain pressurizer level and return to PATH-I.

A-Incorrect. Would return to PATH-I where SI actions are contained.

L B-Correct per foldout, cannot maintain >I 0%, initiate SI C-Incorrect. Would perform after an SI flow reduction as part of reinitiation criteria, but not in EPP-4 D-Incorrect. Would perform after an SI flow reduction as part of reinitiation criteria.

Wednesday, January 05,2005 5:16:54 AM 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 KIA # 007 A4.01 Importance Rating 2.7 Ability to manually operate andor monitor in the control room' PRT spray supply valve Proposed Question: Common 7 Given the following conditions:

A load rejection has occurred.

0 PRZR PORV operation has resulted in high pressure and temperature in the PRZR relief tank.

0 PRT pressure is 13 psig.

0 The PORV has reseated.

Which ONE of the following describes the operation of [2RCS-MOV516], PRT Spray Valve, and

[ZRCS-AOV519], PRT Primary Water Isolation Valve in response to the high PRT pressure?

A. PRT spray valve and PRT primary water supply isolation valve automatically open B. PRT spray valve and the PRT primary water supply isolation valve must both be manually opened.

C. Check open PRT spray valve. PRT primary water supply isolation valve must be manually opened.

D. PRT spray valve must be manually opened. Check open PRT primary water supply isolation valve.

Proposed Answer: B Explanation (Optional):

A. Incorrect. Both valves are manual.

6. Correct.

C. Incorrect. Correct for BVPS-1.

D. Incorrect. Opposite of BVPS-1 actions.

Technical Reference(s): 1OM-6.4.AAY (Attach if not previously provided)

NUREG-1021, Revision 9 13 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-6.4 Objective 10 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 14 BVPS Unit 2

~

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA ## 008 A2.02 Importance Rating 3.2 Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions use procedures to correct control or mitigate the consequences of those malfunctions or operations Hiyh/low surge tank level Proposed Question: Common 8 The Unit is at 80% power with all systems in NSA when the following alarms are received 0 [A6-1HI, PRI Comp Cooling Water System Trouble 0 [A4-5C], Radiation Monitoring Level HIGH.

CCP Surge Tank level is 70% and rising slowly Which ONE of the following actions is required?

A. Trip the reactor, enter E-0, Reactor Trip Or Safety Injection, and trip all RCPs B. Check Containment and Auxiliary Building sump levels for source of leakage and attempt to isolate.

C. Close any RCP thermal barrier isolation valve that indicates less than 50 gpm CCP discharge flow.

D. Close 2CHS-AOV200A, B, & C, Letdown Orifice Isolation Valves to determine if the leak is in the CVCS letdown non-regenerative heat exchanger.

Proposed Answer: D Explanation (Optional):

A. Incorrect. No reactor trip is required. CCP surge tank level is not offscale.

B. Incorrect. Action is required for out-leakage from CCP.

C. Incorrect. This is a normal flowrate. Valve would be closed if flow was > 50 gpm.

D. Correct. Leak isolation of higher pressure systems would include the non-regenerative heat exchanger.

Technical Reference(s): AOP-2.15.1 (Attach if not previously provided)

NUREG-1021, Revision 9 15 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination:

Learning Objective: 2SQS-53C.1 Objective 5 (As available)

Question Source: Bank ##

Modified Bank ## (Note changes or attach parent)

New X Question History: Last NRC Exam Quest ion Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 16 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 010 K5.01 Importance Rating 3.5 Knowledge of the operational implications of the following concepts as the apply to the PZR PCS: Determination of condition of fluid in PZR. using steam tables Proposed Quest ion: Common 9 Given the following conditions:

A plant heatup is in progress per 20M-50.4.M, Station Startup from Mode 5 to Mode 3.

RCS pressure is 335 psig with [2CHS-PCV145], NRHX Discharge Pressure Control Valve in AUTO.

PRZR temperature is 380°F and rising at 1 O F per minute.

0 The PRZR is SOLID; a bubble is being drawn.

Which ONE of the following is the approximate time before a bubble is formed in the PRZR?

A. Less than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. 1 hourto 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months C. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months D. 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Proposed Answer: A Explanation (Optional):

A. Correct. 335 psig is 350 psia, saturation temperature is 431 O F . At 1"F per minute, it will take 51 minutes to draw a bubble.

B. Incorrect. Allows for interpretation mistakes and symmetry of choices.

C. Incorrect. Allows for interpretation mistakes and symmetry of choices.

D. Incorrect. Allows for interpretation mistakes and symmetry of choices.

Technical Reference(s): Steam Tables (Attach if not previously provided) 20M-6.4.P NUREG-1021, Revision 9 17 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: Steam Tables Learning Objective: 2SQS-6.4 Objective 9 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 18 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group ## 1 WA ## 012 K6.06 Importance Rating 2.7 Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Sensors and detectors Proposed Question: Common 10 Given the following conditions:

0 The Unit was operating at 68% power.

0 An automatic reactor trip occurred.

0 The cause of the trip was low flow in RCS Loop 21 A.

0 The cause of the trip was determined to be an instrument failure.

Which ONE of the following input failures caused the reactor trip?

A. The loop high pressure side flow input failed high.

B. The loop high pressure side flow input failed low.

C. One loop low pressure side flow input failed high.

D. One loop low pressure side flow input failed low.

Proposed Answer: B Explanation (Optional):

A. Incorrect. High side input will indicate high DP and high flow.

B. Correct. Each flow transmitter takes input from 1 high side tap and 3 low side taps. If the high side tap fails low, then all 3 DPs indicate low, satisfying the 2/3 logic for 1 loop low flow trip.

C. Incorrect. Low side tap failing high causes a 1 out of 3 low flow trip. 2 out of 3 are required for a reactor trip to occur.

D. Incorrect. Low side failing low would cause a high DP and high flow indication.

Technical Reference(s): 20M-6 Figure 6-1 & 6-3 (Attach if not previously provided) 20M-6.4.IF NUREG-1021, Revision 9 19 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-1.1 Objective 8 and 11 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

BVPS-1 2002 NRC exam Q24 NUREG-1021, Revision 9 20 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 01 3 A4.01 Importance Rating 4.5 Ability to manually operate andor monitor in the control room ESFAS-initiated equipment which fails to actuate Proposed Question: Common 11 Given the following conditions:

0 The Unit was operating at 100% power.

A PRZR PORV failed open.

0 The reactor tripped on low PRZR pressure.

0 PRZR pressure stabilized at 1700 psig.

Plant status is as follows:

0 All control rods are fully inserted.

0 Normally running charging pump is in service.

- 0 Standby charging pump is NOT running, 0 NO LHSl pumps are running.

0 CIA is NOT actuated.

0 CIB is NOT actuated.

0 Main steam lines are NOT isolated.

0 FWlS is NOT actuated.

Which ONE of the following describes the required manual operator actions?

Manually initiate both trains of A. Safety Injection.

B. Safety Injection and CIB.

C. Safety Injection, CIB, and Main Steam Line Isolation.

D. Safety Injection, CIB, Main Steam Line Isolation, and CIA.

d NUREG-1021, Revision 9 21 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: A Explanation (Optional):

A. Correct. When PRZR pressure drops below 1845 psig, SIS should have actuated, which would result in Safety Injection, CIA, and Feedwater Isolation. Manual actuation of SI should start the non-running HHSl and LHSl pumps as well as actuate CIA and the Feedwater Isolation.

B. Incorrect. CIB is not actuated on low PRZR pressure.

C. Incorrect. CIB and MSL Isolation are not actuated on low PRZR pressure.

D. Incorrect. CIB and MSL Isolation are not actuated on low PRZR pressure. CIA will actuate when SI is initiated.

Technical Reference(s): E-0 (Attach if not previously provided)

Att A-0.11 Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-1.1 Objective 10 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

BVPS-1 2002 NRC exam Q8 NUREG-1021, Revision 9 22 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 022 K4.01 Importance Rating 2.5 Knowledge of CCS design feature(s) andor interlock(s) which provide for the lollowing Cooling of containment penetrations Proposed Question: Common 12 Containment penetration cooling coils are normally supplied by...

A. Chilled Water Train A.

B. Chilled Water Train B.

C. AComponent Cooling Water header D. 6 Component Cooling Water header Proposed Answer: C Explanation (Optional):

A. Incorrect. Other plant cooling coils and AC units are supplied from chilled water, but not penet ration coo Ie rs .

B. Incorrect. Other plant cooling coils and AC units are supplied from chilled water, but not penetration coolers.

C. Correct.

D. Incorrect. Backup supply if Train Ais unavailable.

Technical Reference(s): 2SQS-15.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-15.1 Objective 2 (As available)

Question Source: Bank ##

Modified Bank # (Note changes or attach parent)

New X NUREG-1021, Revision 9 23 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Quest ion History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 24 BVPS Unit 2

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ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

...- Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 022 K1.02 Importance Rating 3.7 Knowledge of the physical connections and/or cause-effect relationships between the CCS and the following systems SEChemote monitoring systems Proposed Question: Common 13 Given the following conditions:

A reactor trip has occurred.

Safety Injection actuates on low PRZR pressure.

All equipment started and is operating as designed.

RCS pressure is 340 psig and lowering.

CTMT pressure is 18 psig and rising.

Prior to the event, [2HVR*201A and 201B], Containment Air Recirculation Fans were running.

[2HVR*201C], Containment Air Recirculation Fan was in standby aligned to 480V Bus 2P.

Which ONE of the following describes the status of the containment air recirculation fans?

(Assuming NO operator actions.)

A. All containment air recirculation fans are running B. All containment air recirculation fans are tripped and CANNOT be started C. 2HVR*201A and 2HVR*201 B, Containment Air Recirculation Fans can be manually started 2HVR*201C is tripped and cannot be started.

D. 2HVR*201A, 201 B and 201 C, Containment Air Recirculation Fans can be manually started.

Proposed Answer: B Explanation (Optional):

A. Incorrect. The fans trip on an SI.

B. Correct.

C. Incorrect. All fans trip. None will be manually started until after SI is reset D. Incorrect. All fans trip, cannot be manually started until SI is reset.

NUREG-1021, Revision 9 25 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 2SQS-44.C.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-44.C.1 Objective 10 (As available)

Question Source: Bank ##

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 26 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

_- Examination Outline Cross-reference: Level RO SRO Tier # 2 Group ## 1 WA # 026 G2.1.23 Importance Rating 3.9 Conduct of Operations: Ability to perform specific system and integrated plant procedures during all modes of plant operation Proposed Question: Common 14 Given the following conditions:

A LOCA has occurred.

The crew is performing the actions of E-1, Loss Of Reactor Or Secondary Coolant SI, CIA, and CIB are reset.

The crew is evaluating whether Containment Spray should be stopped.

Containment pressure is (-) 3 psig.

Which ONE of the following describes the action required for Containment Spray?

A. STOP ONE (1) train of Quench Spray. When containment pressure reaches (-) 4 psig, STOP the other train.

6. STOP BOTH trains of Quench Spray. Cycle 2SWS*MOV105A and 6, Recirc Spray HX Cooling Water Disch Valves as necessary to maintain (-) 2 to (-) 4 psig.

C. Allow BOTH trains of Quench Spray to run until containment pressure is reduced to (-) 4 psig. Cycle 2SWS*MOV105A and B, Recirc Spray HX Cooling Water Disch Valves as necessary to maintain (-) 2 to (-) 4 psig.

D. STOP Quench Spray Chem injection pumps. Leave the Quench Spray Pumps running until containment pressure reaches (-) 4 psig.

Proposed Answer: B Explanation (Optional):

NUREG-1021, Revision 9 27 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet A. Incorrect. In E-1, both Quench Spray pumps are stopped when pressure is (-) 2 psig.

... B. Correct.

C. Incorrect. The (-) 4 psig number correlates to cycling the Recirc Spray HX valves to maintain CNMT pressure following the stop of Quench Spray.

D. Incorrect. The first step in stopping Quench Spray is to stop the injection pumps, but for this step, Quench Spray pumps are also stopped.

Technical Reference(s): E-1 Step 10 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-53.3 Objective 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 28 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group ## 1 WA ## 039 K3.05 Importance Rating 36 Knowledge of the effect that a loss or malfunction of the MRSS will have on the following: RCS Proposed Question: Common 15 Given the following conditions:

A Unit startup is in progress following a mid-cycle outage.

The reactor is critical at 1 x 10.8amps on the Intermediate Range Nls.

A condenser steam dump valve fails partially open.

Assuming NO action by the crew, which one of the following describes the IMMEDIATE effect on the plant?

A. Power INCREASES; RCS Temperature INCREASES B. Power INCREASES; RCS Temperature DECREASES C. Power DECREASES; RCS Temperature INCREASES D. Power DECREASES; RCS Temperature DECREASES Proposed Answer: B Ex pIanat i on (0pt ional):

A. Incorrect. More steam demand will cause temperature to decrease.

6. Correct. Negative MTC. (Middle of Life) If temperature decreases, power increases.

C. Incorrect. Power increases due to negative MTC. Temperature decreases due to increased heat removal.

D. Incorrect. If MTC was positive, this would be the initial effect, but MTC is only positive at BOL with a high boron concentration.

Technical Reference(s): GFE - Reactor Operational (Attach if not previously provided)

NUREG-1021, Revision 9 29 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Physics Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-21.1 Objective 11 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2002 NRC Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021. Revision 9 30 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 KIA # 039 K1.08 Importance Rating 2.7 Knowledge of the physical connections and/or causeeffect relationships between the MRSS and the following systems MFW Proposed Question: Common 16 Given the following conditions:

0 The Unit is at 100% power.

0 The following annunciators are in alarm:

o [A6-9E], Steam Generator 21A Level Deviation From Setpoint o [A6-9H], Loop A Steam Flow Greater Than Feedwater Flow The BOP determines that [2FWS-FCV478], SG 21 A Feed Regulating Valve is opening Which ONE of the following describes the event taking place?

A. A controlling feedwater flow transmitter has failed high.

6. A controlling steam pressure transmitter has failed high.

C. A controlling steam flow transmitter has failed low.

D. A SG level transmitter has failed high.

Proposed Answer: B Explanation (Optional):

A. Incorrect. For this failure, the FRV would close.

B. Correct. Steam pressure compensates steam flow and will fail flow in the same direction.

Feedwater will attempt to compensate, the FRV will open and SG level will rise.

C. Incorrect. If steam flow fails low, then the FRV controller responds by closing the FRV and SG level decreases.

D. Incorrect. If a SG level transmitter fails high, then the FRV would compensate by closing.

NUREG-1021, Revision 9 31 BVPS Unit 2

~~~~

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 20M-24.4.IF (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-24.1 Objective 16 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 32 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Quest ion Worksheet Examinat i on OutIine Cross-reference: Level RO SRO Tier ## 2 Group ## 1 KIA # 059 A3.02 Importance Rating 2.9 Ability to monitor automatic operation of the MFW. including: Programmed levels of the S/G Proposed Question: Common 17 With SG level on program which ONE of the following is the expected behavior for SG level during a power increase from OYOto 100% power7 A. Level ramps from 33% at 0% RTP to 44% at 20% RTP, then holds at 441.6.

B. Level is constant at 33% throughout the power ascension.

C. Level will hold at 33% until 20% power, then rises to 44% at 100% RTP D. Level is constant at 44% throughout the power ascension.

Proposed Answer: A Explanation (Optional):

A. Incorrect. Similar to former program prior to SG level program modification change B. Incorrect. Wrong level program.

C. Incorrect. SG program prior to SG level program modification change.

D. Correct.

Technical Reference(s): 2SQS-24.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQSD-24.1 Objective 13 (As available)

Question Source: Bank #

Modified Bank # X (Note changes or attach parent)

New Question History: Last NRC Exam NUREG-1021, Revision 9 33 BVPS Unit 2

~~~

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

Valid because it is a recent system modification.

NUREG-1021, Revision 9 34 BVPS Unit 2

BVPS-1 and BVPS-2 2005 NRC Examination Modified Test Items 2005 Question 17 L, The unit power is rising from 0% to 100% power. With SG level on program which of the following is the expected behavior for SG level?

A. Level ramps from 33% at 0% RTP to 44% at 20% RTP then holds at 44%.

B. Level ramps from 33% at 0% to 44% at 100% RTP.

C. Level will hold at 33% until 20% power then rises to 44% at 100% RTP.

D. Level ramps holds at 33% until 10% RTP then rises to 44% at 100% RTP Answer: A Item taken from BVPS-1 Written Test Item Bank c

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 059 K4.16 Importance Rating 3.1 Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following Automatic trips for MFW pumps Proposed Question: Common 18 Which ONE of the following will automatically trip [2FWS-P21A], SG Main Feed Pump?

A. 2 out of 3 Lo-Lo Level in any SG B. Reactor Trip coincident with Low Tavg C. Low lube oil pressure of 4 psig D. 2FWS-MOVl50A, SG Main Feed Pump Discharge Valve shut Proposed Answer: C Explanation (Optional):

A. Incorrect. Results in a reactor trip and automatic start of the AFW pumps.

B. Incorrect. Results in a partial FWI, but does not include M f W pump trip.

C. Correct.

D. Incorrect. Discharge valve shut is a start interlock for the pump.

Technical Reference(s): 2SQS-24.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-24.1 Objective 13 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam NUREG-1021, Revision 9 35 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 36 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 061 K1.07 Importance Rating 3.6 Knowledge of the physical connections andor cause-effect relationships between the AFW and the following systems Emergency wd!er source Proposed Question: Common 19 Which ONE of the following describes the suction sources for the Auxiliary Feedwater System?

A. Normal suction aligned to 2FWE-TK210, PDWST. Suction can be aligned to 2WTD-TK23, Demin Water Storage Tank if the PDWST is unavailable.

6 . Normal suction aligned to 2WTD-TK23, Demin Water Storage Tank. Suction can be aligned to 2FWE-TK210, PDWST if the Demin Water Storage Tank is unavailable.

C. Normal suction aligned to 2FWE-TK210, PDWST. Suction can be aligned to the Service Water System if the PDWST is unavailable.

D. Normal suction aligned to 2WTD-TK23, Demin Water Storage Tank. Suction can be aligned to the Service Water System if the Demin Water Storage Tank is unavailable.

Proposed Answer: C Explanation (Optional):

A. Incorrect. TK23 can makeup to TK210, but the suction cannot be aligned to it.

6 . Incorrect. Opposite of distractor A. AFW suction cannot be aligned to TK23.

C. Correct.

D. Incorrect. Wrong normal source of supply.

Technical Reference(s): 2SQS-24.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-24.1 Objective 2 (As available)

Question Source: Bank #

NUREG-1021, Revision 9 37 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 38 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier ## 2 Group ## 1 WA ## 061 A3.02 Importance Rating 4.0 Ability to monitor automatic operation of the A F W , including RCS cooldown during AFW operations Proposed Question: Common 20 The plant is in Mode 3 following a reactor trip. A plant cooldown of 50°F/hr. is underway Assuming SG level is held constant, which ONE of the following describes the trend of auxiliary feedwater flow requirements as the plant cools down to Mode 5?

A. More AFW flow is required to maintain SG level due to the increased density of the SG water as it cools.

B. AFW flow requirements are constant as long as the cooldown rate remains constant C. Less A M flow is required to maintain SG level because heat input to the SG's decrease as the cooldown continues.

D. AFW flow requirements are constant as long as SG level remains constant Proposed Answer: C Explanation (Optional):

A. Incorrect. Density will increase, but the effect is minimal compared to decay heat change B. Incorrect. Even though the cooldown rate is constant, less heat is being removed as temperature goes down.

C. Correct.

D. Incorrect. It takes less feedwater to maintain level constant as the RCS cooldown continues. Otherwise, AFW pumps would be adequate for full power operation.

Technical Reference(s): Thermo (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-24.1 Obiective 5 (As available)

NUREG-1021, Revision 9 39 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank ##

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 40 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 062 K2.01 Importance Rating 3.3 Knowledge of Bus Power Supplies to the following Major System Loads Proposed Question: Common 21 Which ONE of the following describes the 4KV busses that supply power to [l RC-P-1A] and

[lRC-P-1C], Reactor Coolant Pumps, respectively?

A. Bus 2 A and Bus 2C B. Bus 2B and Bus 2C C. Bus 2C and Bus 2A D. Bus 2C and Bus 2 8 Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. Bus 26 supplies RCP 21 6.

C. Incorrect. Opposite from actual.

D. Incorrect. Both busses are wrong.

Technical Reference(s): 2SQS-6.3 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-6.3 Objective 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam NUREG-1021, Revision 9 41 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 42 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 063 K3.01 Importance Rating 3.7 Knowiedge of the effect that a loss or malfunction of the dc electrical system will have on the following ED/G Proposed Question: Common 22 How is an emergency diesel generator in standby affected by a loss of all 125VDC power?

A. It can be locally started, and could still generate power after manual field flash.

B. It can start automatically, but cannot generate electricity due to loss of field flash.

C. It can start automatically, and could still generate power after manual field flash.

D. It can be locally started, but cannot generate electricity due to loss of field flash.

Proposed Answer: D Explanation (Optional):

A. incorrect. Cannot generate power if DC is not available for field flash.

B. Incorrect. Auto start circuitry is disabled.

C. Incorrect. Auto start circuitry is disabled.

D. Correct.

Technical Reference(s): 2SQS-36.2 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-36.2 Objective 3 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam NUREG-1021, Revision 9 43 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 44 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Quest ion Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group ## 1 KIA # 064 K4.02 Importance Rating 3.9 Knowledge of ED/G system design feature(s) and/or inter-lock(s) which provide for the following Trips for ED/G while operating (normal or emergency)

Proposed Question: Common 23 Given the following conditions.

A loss of offsite power has occurred.

0 While performing the actions of E-0, the RO manually initiated a Safety Injection 0 Approximately 5 minutes later, 2-1 EDG tripped.

Which ONE of the following was the cause of the EDG trip?

A. Loss of Field B. Reverse Power C. Ground Overcurrent D. Differential Overcurrent Proposed Answer: D Explanation (Optional):

A. Incorrect. Only active when the EDG is paralleled.

6. Incorrect. Only active when the EDG is paralleled.

C. Incorrect. Only active when the EDG is paralleled.

D. Correct. Differential and overspeed trips remain active when the EDG is supplying the bus in UNIT mode.

Technical Reference(s): 2SQS-36.2 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-36.2 Objective 13 (As available)

NUREG-1021, Revision 9 45 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 46 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 064 A3.05 Importance Rating 2.8 Ability to monitor automatic operation of the ED/G system, including Operation of the governor control of frequency and voltage control in parallel operation Proposed Question: Common 24 Given the following conditions:

The Unit is at 100% power.

20ST-36.2, Emergency Diesel Generator [2EGS*EG2-2] Monthly Test is in progress.

2-2 EDG is paralleled to the grid, carrying approximately 50% load.

A grid disturbance causes frequency to drop very slightly. Grid voltage remains constant.

Which ONE of the following describes the response of 2-2 EDG?

A. KW output rises

6. KW output lowers.

C. KW output and KVAR output rises.

D. KW output and KVAR output lowers Proposed Answer: A Explanation (Optional):

A. Correct. If frequency drops, the EDG will attempt to increase speed, which will pick up real load.

B. Incorrect. KW output will rise when the EDG tries to raise grid frequency.

C. Incorrect. KVAR output will remain essentially constant if grid voltage is constant. If it did change, it would change in the opposite direction of KW.

D. Incorrect. KW output will rise.

Technical Reference(s): Electrical Theory Manual (Attach if not previously provided)

NUREG-1021, Revision 9 47 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-36.2 Objective 12 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 48 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 073 A2.02 Importance Rating 2.7 Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions use procedures to correct, control. or mitigate the consequences of those malfunctions or operations Detector failure Proposed Question: Common 25 A liquid waste release is in progress to cooling tower blowdown from [2SGC-TK23A]. SG Blowdown Test Tank when the following annunciator alarms:

0 [A4-5A], Radiation Monitoring System Trouble The BOP determines that [ZSGC-RQI1001, Liquid Waste Effluent Radiation Monitor has failed Which ONE of the following is the required action?

A. The release may continue provided grab samples are taken within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and determined to remain within limits.

B. The release may continue provided two (2) independent samples are independently determined to be within limits and two (2) technically qualified personnel verify the valve lineup.

C. The release must be terminated. It shall not be restarted until detector [2SGC-RQIlOO]

is operable.

D. The release must be terminated. It shall not be restarted until two (2) samples are independently analyzed and two (2) technically qualified personnel verify valve lineups.

Proposed Answer: D Explanation (Optional):

A. Incorrect. With a failed monitor, the release must be stopped until compensatory actions have been put in place.

B. Incorrect. Action is correct but not for ongoing release.

C. Incorrect. Action is correct but RQll 00 does not have to be operable if compensatory measures are taken.

D. Correct.

NUREG-1021, Revision 9 49 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): ODCM (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-17.1 Objective 11 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2002 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 x Comments:

BVPS-2 2002 NRC NUREG-1021, Revision 9 50 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 KIA # 076 K2.01 Importance Rating 2.7 Knowledge of bus power supplies to the following: Service water Proposed Question: Common 26 Given the following conditions:

[2SWS-P21A], Service Water Pump is running.

[2SWS-P21B], Service Water Pump is racked out.

[2SWS-P21C], Service Water Pump is running in place of 2SWS-P21 B Subsequently, a loss of offsite power occurs.

Which ONE of the following describes the Service Water pumps that will be in operation when the EDG's have completed their loading sequence?

A. 2SWS*P21A ONLY B. 2SWSP21 C ONLY C. 2SWS"P21A and 2SWS*P21C ONLY D. NO Service Water Pumps will be running.

Proposed Answer: C Explanation (Optional):

A. Incorrect. The swing pump, 21 C will also start if connected to 2DF bus.

B. Incorrect. As long as both pumps are connected to different busses, they will both start C. Correct. As long as both pumps are on different busses, they will both start.

D. Incorrect. Loss of power only, nothing preventing both pumps from starting.

Technical Reference(s): 2SQS-30.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-30.1 Objective 15 (As available)

NUREG-1021, Revision 9 51 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

BVPS-1 Bank NUREG-1021, Revision 9 52 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

-.. Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 KIA # 078 K3.02 Importance Rating 3.4 Knowledge of the effect that a loss or malfunction of the IAS will have on the following Systems having pneumatic valves and controls Proposed Question: Common 27 Which ONE of the following CVCS valves fails OPEN on a loss of instrument air?

A. 2CHS-FCVl14B, Boric Acid Dilute Injection to VCT B. 2CHS-FCVl13B, Boric Acid Blender Discharge to Injection Pumps C. 2CHS-PCV145, NRHX Discharge Pressure Control Valve D. 2CHS-PCV116A, VCT Pressure Control Valve Proposed Answer: C Exp Ianat ion (0ptional) :

A. Incorrect. Fails closed.

B. Incorrect. Fails closed.

C . Correct.

D. Incorrect. Fails closed.

Technical Reference(s): AOP-2.34.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-34.1 Objective 11 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X NUREG-1021, Revision 9 53 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 54 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 103 A3.01 Importance Rating 3.9 Ability to monitor automatic operation of the containment system, including Containment isolation Proposed Question: Common 28 A reactor trip and safety injection has occurred. The following conditions currently exist:

0 RCS pressure is 1700 psig.

0 Tavg is 545°F.

0 Containment pressure is 1 psig.

0 All SG pressures are 1000 psia.

0 All SG NR levels are 5% and slowly rising.

Which ONE of the following, if any, additional ESF actuations have occurred?

A. CIA

8. MSLl C. CIAandCIB D. No additional ESF actuations have occurred Proposed Answer: A Explanation (Optional):

A. Correct. No conditions shown, but SI will cause CIA also.

6 . Incorrect. Containment pressure too low, main steam pressure is too high C. Incorrect. Containment pressure is too low.

D. Incorrect. CIA will occur due to the SI signal.

Technical Reference(s): 2SQS-11.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE NUREG-1021, Revision 9 55 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 2SQSD-11.1 Objective 16 (As available)

Question Source: Bank #

Modified Bank ## (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 56 BVPS Unit 2

_______ ~ ~ ~ _ _ _ _ _ ~~~~

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Out h e Cross-reference: Level RO SRO Tier # 2 Group # 2 WA # 001 K2.01 Importance Rating 3.5 Knowledge of bus power supplies to the following One-line diagram of power supply to M/G sets Proposed Question: Common 29 What is the correct sequence of components that supply power from the the 480 VAC substations to the control rod drive mechanisms (CRDMs)?

(RDMGs = Rod Drive Motor Generator Sets)

A. 480V Bus A, RDMGs, Power Cabinets, Trip Breakers

6. 480V Bus B, Power Cabinets, Trip Breakers, RDMGs C. 480V Bus A, Trip Breakers, RDMGs, Power Cabinets D. 480V Bus B, RDMGs, Trip Breakers, Power Cabinets Proposed Answer: D Explanation (Optional):

A. Incorrect. Sequence is wrong.

B. Incorrect. Sequence is wrong.

C. Incorrect. Sequence is wrong.

D. Correct.

Technical Reference(s): 3SQS-1.3 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-1.3 Objective 3 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

NUREG-1021. Revision 9 57 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

BVPS-1/2 Bank Reference ID 1586 NUREG-I 021, Revision 3 58 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination OutIine Cross-refe rence: Level RO SRO Tier # 2 Group ## 2 KIA # 002 K4.05 Importance Rating 3.0 Knoivlcdye of RCS design features and/or interlocks which provide for the following Detection of RCS leakage Proposed Question: Common 30 Which ONE of the following describes ONLY the equipment required by Technical Specifications to be OPERABLE for detection of small amounts of RCS leakage?

A. Containment Dew Point Monitor and Gaseous Activity Radiation Monitor B. Containment Particulate Activity Radiation Monitor and Containment Sump Monitor C. Containment Sump Monitor and Containment Temperature Monitoring D. Containment Temperature Monitoring and Containment Dew Point Monitor Proposed Answer: B Explanation (Optional):

A. Incorrect. Dew point monitor is helpful, but not required.

B. Correct.

C. Incorrect. Containment temperature monitor is helpful, but not required.

D Incorrect. Containment temperature and dewpoint will indicate leakage, but not required by TS.

Technical Reference(s): Tech Spec and Bases (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: NIA (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam NUREG-1021. Revision 9 59 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Quest ion Worksheet Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 x Comments:

NUREG-1021, Revision 9 60 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 WA # 011 K3.01 Importance Rating 3.2 Knowledge of the effect that a loss or malfunction of the PZR LCS will have on the following CVCS Proposed Question: Common 31 Given the following conditions:

The Unit is at 100% power with all system in NSA.

The controlling PRZR level transmitter [2RCS-LT459] fails at the programmed level that corresponds to full plant load.

Assume NO operator action is taken Which ONE of the following describes the effect on charging flow and PRZR level when plant power is REDUCED to 1O%?

A. Charging flow remains constant and actual PRZR level remains constant. PRZR heaters will energize to compensate for reduced Tavg.

B. Charging flow decreases and actual PRZR level decreases. On low PRZR level, letdown will isolate and the PRZR heaters will turn off.

C. Actual PRZR level increases and charging flow increases. The backup heaters will energize as level rises due to the apparent in-surge.

D. Actual PRZR level decreases and charging flow increases. When actual level increases back to program level, charging flow will back down to maintain level.

NUREG-1021, Revision 9 61 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: B Explanation (Optional):

A. Incorrect.

6. Correct. Charging flow will decrease because Tavg is decreasing and it will appear that actual level is too high due to the failed transmitter. (Indicated level will be 54"/0 when actual will start to decrease). LT-460 will show the actual pressurizer level which will be decreasing. When level decreases to 14% letdown will isolate and heaters will cut off.

C. Incorrect.

D. Incorrect.

Technical Reference(s): 2SQS-7.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-7.1 Objective 19 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

Robinson 2002 NRC exam NUREG-1021, Revision 9 62 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

-... Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 WA # 041 A1.O1 Importance Rating 2.9 Ability lo predict and/or monitor changes in parameters (to prevent exceeding design limits) associated wtth operating the SDS controls including Tave verification above low-low setpoint Proposed Question Common 32 The Unit was operating at 100% power when a reactor trip occurred due to a LOCA All Safety Injection systems failed to operate and FR-C 1, Response To Inadequate Core Cooling has been entered Given the following:

The Unit Supervisor has directed the depressurization of all intact SGs to 200 psig using the condenser steam dump valves.

All main steam trip valves are open and the condenser is available.

[2MSS*PK464], Steam Dump Controller is in MANUAL.

The Steam Dump Control Mode Selector Switch is in the STM PRESS position and SG depressurization is underway.

PRZR pressure is < 1950 psig and the Block Steamline SI Switches have been placed in the BLOCK position.

As the SG depressurization progresses, the steam dump valves automatically shut.

Which ONE of the following caused the steam dump valves to automatically shut?

A. Steam generator pressure has reached 500 psig.

6. Steam header pressure has dropped below the setpoint on 2MSS*PK464.

C. Tavgis below 541 OF and no action has been taken to defeat the Tavg Interlock.

D. Main steamline isolation due to exceeding the high steam pressure rate setpoint Proposed Answer: C

.-- Explanation (Optional):

NUREG-1021. Revision 9 63 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet A. Incorrect. Block Steamline SI Switches have been placed in the Block position. The Main Steamline Isolation due to low steam line pressure rate is inactive.

6. incorrect. 2MSS*PK464 is in manual. Pressure setpoint has no effect.

C. Correct. As Tavg approaches 541 OF, the TavgInterlock must be defeated by holding both steam dump control bypass interlock selector switches to the DEFEAT TAVG NTLK position until the status light 213 Lo-Lo Tavgis LIT. This action was not performed.

D. Incorrect. Block Steamline SI Switches have been placed in the Block position. The Main Steamline Isolation due to exceeding the high steam pressure rate setpoint is inactive.

Technical Reference(s): 20M-53A.FR-C.l (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-21 .l, Objective 11 (As available)

Question Source: Bank ## X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2002 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Cornments:

2002 NRC exam NUREG-1021, Revision 9 64 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 WA # 033 G2.1.27 Importance Rating 2.8 Conduct of Operations. Knowledge of system purpose and or function Proposed Question: Common 33 Which ONE of the following describes a design feature of the Spent Fuel Pool Cooling and Purification System?

A. Maintains Keff < 0.95 with unborated water during all fuel handling activities.

B. Ensures that any pipe break in the system will maintain sufficient shielding over irradiated fuel bundles.

C. Maintains water temperature below 200°F for all postulated events.

D. Provides sufficient storage for all irradiated fuel assemblies for the life of the plant.

Proposed Answer: B Explanation (Optional):

A. Incorrect. Boration is required for core offload to the SFP.

B. Correct.

C. Incorrect. If allowed to heat up with a full core offloaded, SFP would reach boiling if without cooling.

D. Incorrect. Available storage is limited to 18 refuelings.

Technical Reference(s): 2SQS-20.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-20.1 Objective 1 (As available)

NUREG-1021, Revision 9 65 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 66 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 WA # 034 K6.02 Importance Rating 2.6 Knowledge ol the effect of a loss or malfunction on the following will have on the Fuel Handling System Radiation monitoring systems Proposed Question: Common 34 Given the following conditions:

The Unit has been in Mode 6 for seven (7) days.

0 Fuel movement is in progress.

0 Containment Purge System is operating.

[2HVR*RQ104AII Containment Purge and Exhaust Radiation Monitor fails a channel check and is declared INOPERABLE.

Which ONE of the following describes how, if at all, fuel movement is affected?

A. No effect. Refueling may continue.

8. Refueling may continue as long as 2RMR*RQ303A and 6 , Containment Atmosphere Process Monitors are operable.

C. Suspend fuel movement until the Containment Purge System is isolated, and then resume refueling activities.

D. Refueling may continue as long as 2HVR-RQ104BI Containment Purge And Exhaust Radiation Monitor remains operable.

Proposed Answer: A Explanation (Optional):

A. Correct. As long as > 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months shutdown, monitors are not required by TS.

8. Incorrect. No requirement for RQ303NB to replace RQ104A, and there is no input to purge isolation.

C . Incorrect. If CNMT purge monitors were required, this would be an alternative action to perform.

D. Incorrect. If they were required, they would both be required.

Technical Reference(s): 20M-44C.1 (Attach if not previously provided) d NUREG-1021, Revision 9 67 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-44C.1, Objective 14 (As available)

Question Source: Bank #

Modified Bank ## (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 x Comments:

NUREG-1 021, Revision 9 68 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 WA ## 045 K1.18 Importance Rating 3.6 Knowledge of the physical connections and/or causeeffect relationships between the MT/G system and the fdlow!ng s y s t e m s RPS Proposed Question: Common 35 While operating at 100% power, an OTAT runback occurs.

Which of the following describes the response of the main turbine/generator? Assume the initiating condition does not clear.

A. The load reference is runback, the runback timer will cycle on/off, on for 1.5 seconds, then off for 30 seconds, until generator load is zero.

B. The load reference is runback, the runback timer will cycle on/off, on for 1.5 seconds, then off for 30 seconds, until generator load is reduced to 20%.

C. Load is reduced at the rate of 200% per minute until load is reduced to 20Y0,with no further automatic action.

D. Load is reduced at the rate of 200% per minute until load is reduced to O%, with no further automatic action.

Proposed Answer: A Exp Ianat io n (0ptio nal) :

A. Correct.

6 . Incorrect. There is no limit to 20°/o if the initiating condition remains active.

C. Incorrect. Load is reduced at a rate of 200% per minute, but only in 1.5 second pulses, and would not stop at 20% power.

D. Incorrect. Load is reduced at a rate of 200% per minute, but only in 1.5 second pulses.

Technical Reference(s): 2SQS-35.3 (Attach if not previously provided)

~ ~~~ ~ ~

Proposed references to be provided to applicants during examination, NONE Learning Objective 2SQS-35.3 Objective 2 (As available)

NUREG-1021, Revision 9 69 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

BVPS-1 Ref ID 1SQS-26.1-12-01 NUREG-1021, Revision 9 70 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 WA # 068 A3.02 Importance Rating 3.6 Ability to monitor automatic operation of the Liquid Radwaste System including Automatic isolation Proposed Question: Common 36 Given the following:

The Unit is operating at 100% power with all systems in NSA.

A liquid waste discharge is in progress to the Unit 2 cooling tower basin.

A HIGH radiation alarm occurs on [2SGC-RQlOO], Liquid Waste Process Monitor.

Which ONE of the following describes the action that will occur?

A. Manually close 2SGC-HCV100, High Radiation Valve terminating the release.

B. Verify 2SGC-HCV1 00, High Radiation Valve closes automatically immediately terminating the release.

C. Manually open 2SGC-HCVl OO, High Radiation Valve diverting the release to the Unit 1 boron recovery test tank.

D. Verify 2SGC-HCV100, High Radiation Valve opens automatically immediately diverting the release to the Unit 1 boron recovery test tank.

Proposed Answer: 6 Explanation (Optional):

A. Incorrect. The valve closes automatically.

B. Correct.

C. Incorrect. Opening HCVlOO will not divert to U1 boron recovery system.

D. Incorrect. Opening HCV100 will not divert to U1 boron recovery system.

Technical Reference(s): 2SQS-17.1 (Attach if not previously provided)

--- Proposed references to be provided to applicants during examination: NONE NUREG-1021, Revision 9 71 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

- Learning Objective: 2SQS-17.1 Objective 6 (As available)

Question Source: Bank # X Modified Bank ## (Note changes or attach parent)

New Question History: Last NRC Exam 2002 NRC Quest ion Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

BVPS-1 Q77 2002 NRC NUREG-1021, Revision 9 72 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 WA # 071 A1.06 Importance Rating 2.5 Ability to predict andor monitor changes in pararneters(t0 prevent exceeding design limits) associated with operating the Waste Gas Disposal System controls including Ventilation system Proposed Question: Common 37 A gaseous waste release is in progress in accordance with 1/20M-19.4A.B, Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent.

For the current ventilation dilution flow, which ONE of the following actions would INCREASE the radioactive release rate of the discharge in progress?

A. Opening TV-1GW-103A2, Gaseous Waste Decay Tank Bleed Valve prior to opening FCV-1GW-105, Decay Tank Bleed Control Valve.

B. Stopping 1GW-F-1A, GW Disposal Blower when the release is in progress C. Closing TV-1GW-103A2, Gaseous Waste Decay Tank Bleed Valve prior to closing FCV-1GW-105, Decay Tank Bleed Control Valve.

D. Opening FCV-1GW-105, Decay Tank Bleed Control Valve from 75% to 100% while the discharge is in progress.

Proposed Answer: D Explanation (Optional):

A. Incorrect. Normal procedure direction.

6 . Incorrect. Action will slow decrease the flow rate.

C. Incorrect. Either valve closed first will isolate the flow path.

D. Correct. Increases bleed flow to the vent system.

Technical Reference(s): 1/20M-19.4A.B (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning 0bjective: 2SQS-19.1 Objective 3 (As available)

NUREG-1021, Revision 9 73 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 74 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 WA # ~

075 K1.02 Importance Rating 2.9 Knowledge of the physical connections and/or causeeffect relationships between the circulating water system and the following systems Liquid radwaste discharge Proposed Question: Common 38 A precaution contained in 20M-25.4.L, Discharging Steam Generator Blowdown Evaporator Test Tank [2SGC-TK23A(B)] Contents To Cooling Tower Blowdown states that two tanks containing radioactive liquid can NOT be discharged at the same time.

Which ONE of the following describes the reason for this precaution?

A. The discharge permit for discharging the contents of a liquid waste tank is based upon a dilution rate which includes the cooling tower blowdown rate of both units.

B. Pipe size restrictions in the effluent line could result in an overpressure condition if more than 1 waste tank pump is in operation.

C. The limit prevents excessive wear on the foot valve in the discharge structure due to high flow rates.

D. The common discharge point is only provided with a limited amount of dilution flow from the Unit 2 Cooling Tower Blowdown.

Proposed Answer: A E x planation (0pt ional):

A. Correct.

B. Incorrect. There are no pipe size restrictions, as either Unit can discharge to its own or the other units cooling tower blowdown.

C. Incorrect. Insignificant flow compared to blowdown.

D. Incorrect. No common discharge point actually exists. The piping is tied so that either Unit can discharge to either cooling tower blowdown.

Technical Reference(s): 20M-25.4.L (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE NUREG-1021, Revision 9 75 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 2SQS-17.1 Objective 11 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2002 NRC Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

2002 BVPS-1 Q80 NUREG-1021, Revision 9 76 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier ## 1 Group # 1 KIA # 007 EAl.09 Importance Rating 3.2 Ability to operate and monitor the following as they apply to a reactor trip CVCS Proposed Question: Common 39 Given the following conditions:

0 A reactor trip has occurred.

0 Due to a steam dump failure, PRZR level dropped to 10%.

0 PRZR level has recovered to 22%.

0 The crew is performing the actions of ES-0.1, Reactor Trip Response.

0 The RO is restoring letdown after re-energizing PRZR heaters.

Which ONE of the following is the FIRST action taken when restoring letdown in accordance with ES-0.1, Reactor Trip Response?

A. OPEN 2CHS*LCV460A, B.

B. OPEN 2CHS*PCV145 in MANUAL.

C. Ensure 2CHS-AOV204 is CLOSED.

D. OPEN 2CHS-AOV200A, B, C.

Proposed Answer: B Explanation (Optional):

A. Incorrect. Valves should already be closed.

B. Correct.

C. Incorrect. Valve should be open as long as no CIA exists.

D. Incorrect. Valves should be closed and will not be reopened until after PCV145 Technical Reference(s): ES-0.1 Step 7.C RNO (Attach if not previously provided)

NUREG-1021, Revision 9 77 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-53.3 Objective 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-I 021, Revision 9 70 BVPS Unit 2

~

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA # 008 AA2.20 Importance Rating 3.4 Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident The effect of an open PORV on code safety based on observation of plant parameters Proposed Question: Common 40 With the Unit operating at 100% power, the reactor trips on low PRZR pressure

[2RCS-P1472], Pressurizer Relief Tank Pressure indicates 35 psig. The crew suspects that a PORV opened inadvertently and is now stuck partially open.

Which ONE of the following confirming indications could be expected if a PORV is stuck partially open?

A. PORV relief line temperature stabilized at 281 O F . PRZR safety relief line temperatures slowly rising.

6. PORV relief line temperature stabilized at 250°F. PRZR safety relief line temperatures slowly rising.

C. PORV relief line temperature stabilized at 281 O F . PRZR safety relief line temperatures indicate ambient temperature and stable.

D. PORV relief line temperature stabilized at 250°F. PRZR safety relief line temperatures indicate ambient temperature and stable.

NUREG-1021, Revision 9 79 BVPS Unit 2

~~ ~~~~

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: A Explanation (Optional):

A. Correct. 281 "F is the saturation temperature corresponding to 50 psia.

B. Incorrect. 255°F is approximately the saturation temperature corresponding to 35 psia (35 psig PRT pressure = 50 psia). Safety relief line temperatures would be rising because they share a common discharge line to the PRT with the PORV's.

C. Incorrect. 281 OF is the saturation temperature corresponding to 50 psia. However, safety relief line temperatures would be rising because they share a common discharge line to the PRT with the PORV's.

D. Incorrect. 255°F is approximately the saturation temperature corresponding to 35 psia (35 psig PRT pressure = 50 psia); Also, safety relief line temperatures would be rising because they share a common discharge line to the PRT with the PORV's.

Technical Reference(s): Steam Tables (Attach if not previously provided) 20M6.4 Annunciator Response Proposed references to be provided to applicants during examination: Steam Tables Learning Objective: 2SQS-6.4 Objectives 19/20 (As available)

Question Source: Bank ##

Modified Bank # X (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

Provide Candidates with Steam Tables. Modified values to require interpretation of steam tables with similar, but different values, from last year BVPS-1 NRC exam NUREG-1021, Revision 9 80 BVPS Unit 2

BVPS-1 and BVPS-2 2005 NRC Examination Modified Test Items 2005 Question 40 L With the plant operating at 100% power, the reactor trips on low PRZR pressure.

Pressurizer Relief Tank Pressure indicates 15 psig on PI-I RC-472. The crew suspects that a PORV opened inadvertently and is now stuck partially open.

Which one of the following confirming indications could be expected if a PORV is stuck partially open?

A. PORV relief line temperature stabilized at 213°F. PRZR Safety relief line temperatures indicate 180°F and very slowly rising.

B. PORV relief line temperature stabilized at 250°F. PRZR Safety relief line temperatures indicate 217°F and very slowly rising.

C. PORV relief line temperature stabilized at 213°F. PRZR Safety relief line temperatures indicate 110°F and stable.

D. PORV relief line temperature stabilized at 250°F. PRZR Safety relief line temperatures indicate 110°F and stable.

Answer: B BVPS-1 2002 NRC Exam Question 59

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA ## 015 AK1.01 Importance Rating 4.4 Knowledge of the operational implications of the following concepts as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow) Natural Circulation in a nuclear power plant Proposed Question: Common 41 The Unit is operating at 100 o/o power when a loss of component cooling water results in a reactor trip. Ten minutes after the trip, the following conditions exist:

SG Pressure 21 A 1000 psig and stable 21 B 1005 psig and stable 21 c 995 psig and stable All RCPs are OFF.

0 RCS pressure is 2230 psig and stable.

0 Thot is approximately 575°F in all 3 loops and slowly lowering.

0 Core Exit TCs indicate approximately 580°F.

0 Tcold is approximately 555°F in all 3 loops and stable.

Based on the above indications, what is the condition of the RCS and the preferred method of heat removal for the current plant conditions?

A. Natural circulation exists. The condenser steam dumps are maintaining heat removal B. Natural circulation does NOT exist. Heat removal will be established by opening the condenser steam dumps.

C. Natural circulation exists. SG atmospheric steam dumps are maintaining heat removal D. Natural circulation does NOT exist. Heat removal will be established by opening the SG atmospheric steam dumps.

Proposed Answer: B Explanation (Optional):

NUREG-1021, Revision 9 81 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet A. Incorrect. Natural circulation does not exist because Tcold temperatures are too high and stable.

B. Incorrect. Condenser steam dumps are the preferred method of heat removal in ES-0.2.

C. Incorrect. Natural circulation does not exist because Tcold is too high for SG pressure, and not trending down. No indications that SG ADV's are open for heat removal.

D. Correct. Tcold is above saturation for each SG and not trending down indicating natural circulation does not exist. SG ADV's are not the preferred method of heat removal.

Technical Reference(s): EOP Attachment A. 1-7 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: Steam Tables Learning Objective: 3SQS-53.2 Objective 12 (As available)

Question Source: Bank ##

Modified Bank # X (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

Previous BVPS-1 Audit Examination NUREG-1021, Revision 9 82 BVPS Unit 2

BVPS-1 and BVPS-2 2005 NRC Examination Modified Test Items 2005 Question 41

- The unit is operating at 100 OO/ power when a Loss of Off-Site power causes a reactor trip. Ten minutes after the trip, the following conditions exist:

0 A SG Pressure 1000 psig and stable 0 B SG Pressure 1005 psig and stable 0 C SG Pressure 995 psig and stable All RCPs are Off 0 RCS Pressure is 2230 psig and stable 0 Thot is approximately 575°F in all 3loops and lowering slowly 0 Core Exit TCs indicate approximately 580°F 0 Tcold is approximately 555°F in all 3 loops and stable Based on the above indications, what is the condition of the RCS?

A. Natural Circulation exists. The condenser steam dumps are maintaining heat removal B. Natural Circulation does not exist. Heat removal may be established by opening the condenser steam dumps

- C. Natural Circulation exists. SG PORVs are maintaining heat removal D. Natural Circulation does not exist. Heat removal may be established by opening the SG PORVs Answer: D BVPS-1 2002 Audit Examination Question 52

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group ## 1 KIA ## 022 AA2.04 Importance Rating 2.9 Abilily l o determine and interpret the following as they apply to lhe Loss of Reactor Coolant Pump Makeup How long PZR levcl can be maintained within limits Proposed Question: Common 42 The Unit was at 55% power when all charging flow was lost. The following conditions exist The crew has isolated letdown while attempting to restore charging flow.

The RO reports that PRZR level is lowering at a rate of 1% every five (5) minutes PRZR level was approximately 2% below reference when letdown was isolated.

Assuming charging flow is not restored, approximately how long can PRZR heater operation be maintained?

A. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 6 . 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months C. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months D. 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Proposed Answer: C Explanation (Optional):

A. Incorrect. Value is close and symmetrical.

B. Incorrect. Value is close and symmetrical.

C. Correct. At 55% power, Tavg is approximately 55% of range. PRZR level program will be approximately 55% of scale between 22% and 5496. Pressurizer heater cutout is at 14%.

Therefore, with level lowering at 1Yo every 5 minutes, it will take 128 minutes to reach 14°io.

D. Incorrect. Value is close and symmetrical.

Technical Reference(s): 2SQS-6.4 (Attach if not previously provided)

NUREG-1021, Revision 9 83 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-6.4 Objectives 18/19 (As available)

Question Source: Bank ##

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 84 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA # 025 AA1.08 Importance Rating 2.9 Ability to operate and / or monitor the following as they apply lo the Loss of Residual Heat Removal System RHR cooler inlet and outlet temperature indicators Proposed Question: Common 43 Given the following conditions:

0 The Unit is in Mode 5 .

A loss of RHS cooling has occurred.

The crew is performing actions of AOP-2.10.1, Residual Heat Removal System Loss.

The RO reports that CCP pumps CANNOT be started.

The US directs the RO to monitor RHS system temperature.

Which ONE of the following describes the reason for monitoring RHS temperature at this time?

A. RHS temperature must be logged to determine time to RCS saturation.

6 . RHS temperature must be logged to determine time available to vent RHS pumps.

C. If temperature exceeds 180°F, the RHS pumps must be tripped to prevent seal damage.

D. If temperature exceeds 180°F, the RHS pumps must be tripped to prevent cavitation.

Proposed Answer: C Explanation (Optional):

A. Incorrect. Core exit temperatures, not RHS temperature is logged.

6. Incorrect. Core exit temperatures, not RHS temperature is logged.

C. Correct.

D. Incorrect. When cavitation occurs or RCS reaches saturation, pumps will be tripped.

Technical Reference(s): AOP-2.10.1 Step 9 (Attach if not previously provided)

NUREG-1021, Revision 9 85 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 2SQS-53C.1 Objective 4 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 86 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA # 027 AA2.02 Importance Rating 3.8 Ability to determine and interpret the following as they apply to the Pressurizer Pressure Control Malfunctions Normal values for RCS pressure Proposed Question: Common 44 Given the following conditions:

The Unit is at 100% power with all systems in NSA.

The following annunciator is in alarm:

0 [A4-1D],Pressurizer Control Press HIGH/LOW The RO determines that [2RCS*PT445], PRZR pressure transmitter is failing LOW Assuming NO operator action is taken, which ONE of the following describes the expected indication on 2RCS*P1444?

A. Rises until 2RCS*PCV455C, PRZR PORV Relief Valve OPENS B. Rises until 2RCS*PCV455D and 456 PRZR PORV Relief Valves OPEN.

C. Remains constant at the normal full power value. NO control action occurs.

D. Remains constant due to AUTO control of PRZR Heater Group 2C. All backup heaters TRIP.

Proposed Answer: C Explanation (Optional):

A. Incorrect. If PT445 fails low, the only indication will be the alarm. Heaters and spray valves are controlled from the master controller.

8 . Incorrect. These 2 valves are controlled by PT445, which is failing low.

C. Correct.

D. Incorrect. Backup heaters do not trip and there is no reason for them to trip.

NUREG-1021, Revision 9 87 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Quest ion Worksheet Technical Reference(s): 20M-6.4.IF (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-6.4 Objective 19 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 88 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 KIA # 029 EK3.11 Importance Rating 4.2 Knowledge of the reasons for the following responses as the apply to the ATWS Initiating emergency boration Proposed Question: Common 45 Which ONE of the following describes the reason that emergency boration is initiated in FR-S.l, Response to Nuclear Power Generation - ATWS?

A. After control rod trip and rod insertion functions, boration is the next most direct manner of adding negative reactivity to the core.

B. It is the fastest method of adding negative reactivity in the event that an uncontrolled cooldown results from a turbine trip failure.

C. To provide a method of boron addition at high RCS pressures, helping to avoid unnecessary SI initiation.

D. It is required because the UFSAR accident analysis does not take credit for local operator actions in the event of an ATWS.

Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. The fastest method is to insert rods.

C. Incorrect. Avoiding SI initiation is not a concern for FR-S.1.

D. Incorrect. Whether or not UFSAR takes credit for local actions has no bearing on why boration is initiated.

Technical Reference(s): FR-S. 1 Background (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-53.3 Objective 3 (As available)

Question Source: Bank # X NUREG-I 021, Revision 9 89 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

Vendor Bank - Robinson 2004 Audit NUREG-1021, Revision 9 90 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA # 038 EA1.16 Importance Rating 4.4 Ability to operate and monitor the following as they apply to a SGTR S/G atmospheric relief valve and secondary PORV controllers and indicators Proposed Question: Common 46 Given the following:

0 The Unit has sustained a Steam Generator Tube Rupture and the crew is preparing to cooldown to a target temperature of 505°F on the CETs.

A loss of offsite power occurs.

0 All equipment functions as required.

Which ONE of the following describes how the cooldown to target temperature will be accomplished?

A. Open the intact SG atmospheric dump valves at maximum rate.

B. Gradually open the intact SG atmospheric dump valves.

C. Gradually open the condenser steam dumps in Pressure Control Mode.

D. Open the condenser steam dumps in Pressure Control Mode at maximum rate.

Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. Cooldown should be performed as quickly as possible.

C. Incorrect. Condenser steam dumps are not available.

D. Incorrect. Condenser steam dumps are not available.

Technical Reference(s): E-3 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE NUREG-1021, Revision 9 91 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 3SQS-53.3 Objective 3 (As available)

Question Source: Bank # X Modified Bank ## (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Com p rehens ion or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

BVPS-1 REF ID 17089 NUREG-1021, Revision 9 92 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 KIA # 040 AA2.05 Importance Rating 4.1 Ability to determine and interpret the following as they apply to the Steam Line Rupture When ESFAS systems may be secured Proposed Question: Common 47 Given the following conditions:

A reactor trip and safety injection have occurred.

0 The crew is performing the actions of E-2, Faulted Steam Generator Isolation due to the uncontrolled depressurization of SG 21A.

The crew is evaluating if SI flow should be reduced.

The following conditions exist:

5, RCS temperature is 460°F.

3 RCS pressure is 1650 psig and rising slowly.

0 Containment pressure is 23 psig.

0 SG 21B and 21 C NR levels are 15% and rising.

c A F W flow is 375 gpm.

0 PRZR level is 20%.

Based on the conditions above, the crew may enter ES-1.1, SI Termination.. .

A. immediately 6 . after transition to E-1 when RCS subcooling criteria is met.

C. after transition to E-1 when PRZR level criteria is met.

D. after transition to E-1 when SG level criteria is met.

NUREG-1021, Revision 9 93 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: C Explanation (Optional):

A. Incorrect. PRZR level criteria is not high enough for the adverse CTMT conditions.

B. Incorrect. Due to faulted SG, subcooling criteria is easily met.

C. Correct.

D. Incorrect. While SG levels are below the criteria for adverse CTMT, AFW flow is sufficient.

Technical Reference(s): ES-1.1 Entry from E-2, E-1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

Learning Objective: 3SQS-53.3 Objective 2 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge

-/

Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 x Comments:

NUREG-1021, Revision 9 94 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA # 054 AA1.04 Importance Rating 4.4 Ability to operate and / or monitor the following as they apply to the Loss of Main Feedwater (MFW) HPI. under total fcedwater loss conditions Proposed Question: Common 48 Given the following:

0 The crew is responding to an event and is currently in FR-H.l, Response To Loss Of Secondary Heat Sink.

0 Attempts to restore feedwater flow have failed.

RCS bleed and feed has been established with one PRZR PORV open.

The other two PORV's will NOT open.

Which ONE of the following actions is required to be taken?

A. Terminate attempts to establish a SG heat sink because one PRZR PORV will provide sufficient bleed flow to permit adequate RCS heat removal.

B. Continue attempts to open the failed PRZR PORV's and reduce SI flow as necessary to prevent rapid overpressurization of the RCS.

C. Establish alternate RCS bleed paths because one PRZR PORV may not depressurize the RCS sufficiently to permit adequate cooling from the SI flow.

D. Terminate RCS bleed and feed because with only one PRZR PORV open, RCS pressure will rise causing SI flow and RCS inventory to drop.

NUREG-1021, Revision 9 95 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: C Explanation (Optional):

A. Incorrect. Efforts to establish a heat sink are on-going.

B. Incorrect. SI flow should not be reduced.

C. Correct.

D. Incorrect. Bleed and feed should not be terminated, although if no other vent paths can be opened, there may be insufficient feed.

Technical Reference(s): 20M-53B.4.FR-H.1, Step 17 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-53.3 Objective 3 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question Historv: 2001 BVPS-2 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 96 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination OutIine C ross-ref e rence: Level RO SRO Tier ## 1 Group # 1 WA # 055 EK1.02 Importance Rating 4.1 Knowledge of the operational implications of the following concepts as they apply to the Station Blackout Natural circulation cooling Proposed Question: Common 49 In ECA-0.0, Loss Of All 4KV Emergency Power during the rapid depressurization of intact SGs to 300 psig, an overshoot occurs and all 3 SGs are reduced to 180 psig before the depressurization is stabilized.

Which ONE of the following is a plant condition that may result from this overshoot in SG depressurization?

A. The Integrity CSFST may be challenged.

B. The Subcriticality CSFST may be challenged.

C. Natural circulation may not remain an effective form of heat removal.

D. Sufficient steam supply may not be available for effective turbine driven AFW pump operation.

Proposed Answer: C Explanation (Optional):

A. Incorrect. Even if the Integrity CSF was challenged, action would not be taken because there is no power.

B. Incorrect. Even if the Subcriticality CSF was challenged, action would not be taken because there is no power.

C. Correct. N2 injection to the RCS would interrupt natural circulation flow.

D. Incorrect. TDAFW pump can run down to 100 psig.

Technical Ref e rence(s) : ECA-0.0 Background (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-53.3 Objective 3 (As available)

NUREG-1021, Revision 9 97 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

Prairie Island Western Technical Bank ## 44443 NUREG-1021, Revision 9 98 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 -

WA ## 056 AA1.10 Importance Rating 4.3 Ability to operate and / o r monitor the following as they apply to the Loss of Offsite Power Auxiliary/emergency feedwater pump (motor driven)

Proposed Question: Common 50 Given the following conditions:

The Unit is at 100% power.

0 2-2 EDG is 00s.

A loss of offsite power occurs.

0 All equipment operates as designed.

Which ONE of the following describes the status of the motor driven AFW pumps?

A. 2FWEtP23A and 2FWE*P23B are both RUNNING.

B. 2FWE*P23A and 2FWE*P3B are both STOPPED.

C. 2FWE*P23A is RUNNING. ZFWE'P23B is STOPPED.

D. 2FWE*P23B is RUNNING. 2FWEtP23A is STOPPED.

Proposed Answer: C Explanation (Optional):

A. Incorrect. 2FWE*P23B can not run without power.

B. Incorrect. 2FWE*P23A will be running.

C. Correct.

D. Incorrect. Opposite of actual pump operation.

Technical Reference(s): 2SQS-24.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-24.1 Objective 15 (As available)

NUREG-1021, Revision 9 99 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 100 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA # 057 AA2.04 Importance Rating 3.7 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument B u s ESF system panel alarm annunciators and channel status indicators Proposed Question: Common 51 A loss of 120VAC Vital Bus No. 2-1 has occurred.

Which ONE of the following affected channel ESF bistable status indicators will be EXTINGUISHED following the vital bus failure?

A. HIGH 3 CNMT PRESSURE CIB CHAN I B. PRZR PRESS LO SI SETPOINT CHAN I C. MAIN STEAM HDR A PRESS LOW CHAN I

.- D. 21A SG HI-HI LEVEL CHAN I Proposed Answer: A Explanation (Optional):

A. Correct. Energize to actuate. Loss of power will not actuate bistable.

B. Incorrect. Light will be lit due to actuation.

C. Incorrect. Light will be lit due to actuation.

D. Incorrect. Light will be lit due to actuation.

Technical Reference(s): AOP 2.38.1A (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-38.1 Objective 12 (As available)

Question Source: Bank #

.- Modified Bank # (Note changes or attach parent)

NUREG-1021, Revision 9 101 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.47 x 55.43 Comments:

NUREG-1021, Revision 9 102 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA # 058 AA1.01 Importance Rating 3.4 Ability to operate and I or monitor the following as they apply to the Loss of DC Power Cross-tie of the affected dc bus wilh the alternate supply Proposed Question: Common 52 How is it ensured that loads powered off of two different 125V DC distribution buses (swing) loads do not inadvertently cross-tie the affected DC buses?

A. A mechanical interlock prevents simultaneous closure of both DC supply breakers.

B. An electrical interlock trips both DC supply breakers if they are simultaneously closed C. An alarm sounds in the Control Room to warn the operators if both DC supply breakers are simultaneously closed.

D. Administrative controls only (procedure requirements) prevent simultaneous closure of both DC supply breakers.

Proposed Answer: A Explanation (Optional):

A. Correct. A physical barrier in the design of the distribution buses ensure loads cannot be cross-tied.

B. Incorrect for reason above.

C. Incorrect for reason above.

D. Incorrect for reason above.

Technical Reference(s): (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

NUREG-1021, Revision 9 103 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

Bank 3SQS-39.1-01-08-01 NUREG-1021. Revision 9 104 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA ## 062 AA2.06 Importance Rating 2.8 Ability to determine and inlerprel the following as they apply to the Loss of Nuclear Service Water Length of lime before equipment damage Proposed Question: Common 53 Given the following conditions:

The Unit is at 100% power with all systems in NSA.

The crew was attempting to locate and isolate a CCP system leak in accordance with AOP-2.15.1, Loss Of Primary Component Cooling Water.

The US was directed by AOP-2.15.1 to go to AOP-2.6.8, Abnormal RCP Operation.

[2CCP-AOV107A], 21 A RCP Th Barr CCP Outlet Is01 Valve, is closed.

Which ONE of the following describes the maximum amount of time that RCP's can be run under these conditions?

A. 5 minutes if seal injection flow is maintained.

B. Indefinitely if seal injection flow is maintained.

C. 5 minutes, as long as RCP motor bearing temperatures are stable D. Indefinitely, as long as RCP motor bearing temperatures are stable.

Proposed Answer: B Ex p I anat ion (0ptional) :

A. Incorrect. If seal injection available, then RCP's may be run.

B. Correct.

C. Incorrect. Motor bearing temperature is a concern for loss of CCP, but not thermal barrier heat exchanger loss.

D. Incorrect. Motor bearing temperature is a concern for loss of CCP, but not thermal barrier heat exchanger loss.

Technical Reference(s): AOP-2.6.8 (Attach if not previously provided)

~

Proposed references to be provided to applicants during examination: NONE NUREG-1021, Revision 9 105 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 2SQS-6.3 Objective 19/21 (As available)

Question Source: Bank ##

Modified Bank ## (Note changes or attach parent)

New X Question Hist o ry: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 106 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA # E04 EA2.1 Importance Rating 3.4 Ability to determine and interpret the following as they apply to the (LOCA Outside Containment) Facillty conditions and selection of appropriate procedures during abnormal and emergency operations Proposed Question: Common 54 Following a reactor trip and safety injection, the crew is performing actions of E-0, Reactor Trip Or Safety Injection.

The following conditions exist:

0 All SG pressures are stable at 1000 psig.

0 All SG NR levels are approximately 25%.

AFW is supplying the SGs.

0 RCS pressure is approximately 1000 psig.

0 RCS temperature is 545°F.

0 Auxiliary Building radiation monitors are alarming.

0 Containment pressure is (-) 5 psig.

Which ONE of the following procedures will mitigate this event?

A. E-1, Loss of Reactor or Secondary Coolant B. ES-1.l, SI Termination C. ES-1.2, Post-LOCA Cooldown and Depressurization D. ECA-1.2, LOCA Outside Containment NUREG-1021, Revision 9 107 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: D Explanation (Optional):

A. Incorrect. CNMT parameters are normal.

6. Incorrect. RCS pressure is not high enough.

C. Incorrect. Entry would be from E-1, which would not be used D. Correct.

Technical Reference(s): E-0 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

Learning Objective: 3SQS-53.3 Objective 2 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 x Comments:

NUREG-1021, Revision 9 108 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA # E05 EK3.2 Importance Rating 3.7 Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink) Normal abnormdl and emergency operating procedures associated with (Loss of Secondary Heat Sink)

Proposed Question: Common 55 Given the following conditions:

0 A reactor trip and safety injection have occurred.

0 The crew has performed the actions of E-0.

0 AFW flow CANNOT be established.

0 All SG NR levels are offscale low.

0 The crew has entered FR-H.l, Response To Loss Of Secondary Heat Sink.

0 RCS pressure is 200 psig.

0 SG pressures are each 550 psig and lowering.

Which ONE of the following describes the plant conditions?

A. Remain in FR-H.l because a large break LOCA is in progress AND a secondary heat sink is required.

6 . Remain in FR-H.l because a small break LOCA is in progress AND a secondary heat sink is required.

C. Go to E-1 because a large break LOCA is in progress AND a secondary heat sink is NOT required.

D. Go to E-1 because a small break LOCA is in progress AND a secondary heat sink in NOT required.

NUREG-1021. Revision 9 109 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: C Explanation (Optional):

A. Incorrect. RCS pressure is less than SG pressure, so SG's are acting as a heat sink.

B Incorrect. SBLOCA is not in progress.

C Correct. With RCS pressure less than SG pressure, break is of a larger size and SI will provide heat removal. SG's are heat sources, not heat sinks.

D. Incorrect. SBLOCA is not in progress.

Technical Reference(s): FR-H.l and background (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

Learning Objective: 3SQS-53.3 objective 3 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 x Comments:

Robinson 2002 Audit Exam NUREG-1021, Revision 9 110 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA # E l l EK1.3 Importance Rating 3.6 Knowledge of the operational implications of the following concepts as they apply to the (Loss of Emergency Coolant Recirculation)

Annunciators and conditions indicating signals. and remedial actions associated with the (Loss of Emergency Coolant Recirculation).

Proposed Question: Common 56 Given the following conditions:

A LOCA has occurred.

Due to multiple equipment failures, the crew is performing actions of ECA-1.l , Loss Of Emergency Coolant Recirculation.

Two (2) ChargingIHHSI pumps and two (2) LHSl pumps are running RWST level is approximately 10 inches and continues to drop.

Which ONE of the following describes the action required in accordance with ECA-1.1?

- A. STOP ONE (1) HHSl and ONE (1) LHSl pump and verify NO backflow from the RWST to CTMT sump.

6. STOP ONE (1) HHSl and ONE (1) LHSl pump and initiate secondary depressurization to facilitate SI accumulator injection.

C. STOP ALL pumps taking a suction from the RWST and verify NO backflow from the RWST to CTMT sump.

D. STOP ALL pumps taking a suction from the RWST and initiate secondary depressurization to facilitate SI accumulator injection.

NUREG-1021, Revision 9 111 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: D Explanation (Optional):

A. Incorrect. RWST level is too low to leave any pumps running.

B. Incorrect. RWST level is too low to leave any pumps running.

C. Incorrect. Correct action for pumps, but instead of being concerned with backflow, the crew must initiate depressurization.

D. Correct.

Technical Reference(s): ECA-1.1 Step 36, 37 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-53.3 Objective 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level : Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 112 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 WA # 001 AA1.O1 Impodance Rating 3.5 Ability to operate and / or monitor the following as they apply to the Continuous Rod Withdrawal Bank select switch Proposed Qu est ion : Common 57 The following conditions exist:

The Unit is operating at 8O%, steady state power.

0 The Rod Control Selector Switch is in Automatic.

Control Bank D starts to step in continuously.

0 Turbine load is stable.

Which ONE of the following actions must the operator take in response to these conditions?

A. Place the Rod Control Mode Selector Switch in Manual.

B. Place the rod Control Mode Selector Switch in Bank D C. Place the Rod Control Mode Selector Switch in either S/D Bank position D. Manually trip the reactor.

Proposed Answer: A Explanation (Optional):

A. Correct. If load is stable, control rods are to be placed in Manual B. Incorrect. Wrong position.

C. Incorrect. Wrong position.

D. Incorrect. Actions not required for this type of failure.

Technical Reference(s): AOP-2.1.3 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: (As available)

NUREG-1021, Revision 9 113 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

Western Tech Bank ID 44514 NUREG-1021, Revision 9 114 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Quest ion Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 WA # 003 AK2.05 Importance Rating 2.5 Knowledge of the interrelations between the Dropped Control Rod and the following Control rod drive power supplies and logic circuits Proposed Question: Common 58 Given the following conditions:

The Unit is operating at 100% power with all systems in NSA.

The RO recognizes that Control Bank D and Bank B, Group 2 control rods drop just prior to a reactor trip.

Which ONE of the following is the cause of the failure?

A. Logic Cabinet Oscillator failure B. Logic Cabinet Master Cycler failure C. Power Cabinet Thyristor failure D. Power Cabinet Logic error Proposed Answer: C Exp Ianatio n (0ptio nal) :

A. Incorrect. Causes an urgent failure and locks up control rods.

B. Incorrect. Causes an urgent failure and locks up control rods.

C . Correct. Could cause loss of power to stationary gripper coils, resulting in a rod drop D. Incorrect. Causes an urgent failure and locks up control rods.

Technical Reference(s): 3SQS-1.3 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS- 1.3 Objective 6 (As available)

NUREG-1021, Revision 9 115 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank #

Modified Bank ## (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 116 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 ~-

WA # 037 AK1.02 Importance Rating 3.5 Knowledge of the operational implications of the following concepts as they apply to Steam Generator Tube Leak Leak Rate Versus Pressure Drop Proposed Question: Common 59 During operation at power SG tube leakage is detected and estimated at 250 gpm by the Reactor Operator. The following plant indications exist:

RCS pressure - 2200 psig and lowering Reactor power - 80%

SG pressures - 1000 psig 0 PRZR level - 42% and lowering The Unit is tripped and plant parameters following the trip are:

RCS pressure - 1700 psig and lowering Reactor power - 0%

0 SG pressures - 1100 psig 0 PRZR level - 13%

Based on the two sets of given data, which ONE of the following describes the effect on primary-to-secondary leakage?

Leakage following the trip is...

A. one half of the initial leak rate or about 125 gpm.

B. essentially equal to the initial leak rate or about 250 gpm.

C. approximately 7oyo of the initial leak rate or about 175 gpm.

D. One third of the initial leak rate or about 83 gpm.

Proposed Answer: C Explanation (Optional):

NUREG-1021, Revision 9 117 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet A. Incorrect. The DP is approximately half.

B. Incorrect. As DP changes, flow rate also changes.

C. Correct. Leak rate is proportional to the square root of the DP D. Incorrect. Inverse of distractor C.

Technical Reference(s): Thermo (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: N/A (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

Indian Point 2 2001 Audit Exam -Western Tech Bank Archive NUREG-1021, Revision 9 118 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 WA ## 061 AA2.01

~~

Importance Rating 3.5 Atxlity to determine and interpret the following as they apply to the Area Radiation Monitoring (ARM) System Alarms A R M panel displays Proposed Question: Common 60

[2RMC*RQ201A], Control Room Area Radiation Monitor indication on the RM-11 console grid display is backlit YELLOW.

Which ONE of the following describes the status of 2RMC*RQ201 A?

A. Monitor has FAILED.

B. Monitor is OFF-LINE.

C. HIGH alarm setpoint has been reached D. ALERT alarm setpoint has been reached Proposed Answer: D Explanation (Optional):

A. Incorrect. Purple or Blue indicates monitor failure.

B. Incorrect. White indicates monitor is off-line.

C. Incorrect. Red indicates high alarm.

D. Correct.

Technical Reference(s): 2SQS-43.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-43.1 Objective 7 (As available)

Question Source: Bank ##

Modified Bank # X (Note changes or attach parent)

NUREG-1021, Revision 9 119 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question History:

New Last NRC Exam 4-Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 120 BVPS Unit 2

BVPS-1 and BVPS-2 2005 NRC Examination Modified Test Items 2005 Question 60 (BVPS-2 ONLY)

L-See attached BVPS test item from facility bank

12 Points: 2.00 Multiple Choice On the RM-11 Operator's console for the Radiation Monitoring System, if a monitor appears on a GRID display in the color yellow, this means the monitor has...

A. lost power.

B. reached the alert alarm setting.

C. reached the high alarm setting.

D. lost sample flow.

Answer: B ASSOCIATED INFORMATION:

2SQS-43.1-01-18 2SQS-43.1-01-18: Describe the control, protection and interlock functions for the control room components associated with the Radiation Monitoring System, including automatic functions, and changes in equipment status as applicable.

Reference Id: 2SQS-43.1-06-01 Must appear: No Status: Active User Text:

User Number 1: 0.00 User Number 2: 0.00 Difficulty: 0.00 Time to complete: 1 Topic: On the RM-11 Operator's console for the Radiation Monitoring

-c Cross

Reference:

Comment: SOLUTION: (Why the other answers are incorrect.)

A, C and D are wrong because these will not cause the monitor to display yellow.

TECHNICAL

REFERENCE:

2 0 M chapter 43 Submitted by: Gary W. Callaway 05/16/01 Task: 043 1-016-01-013 Lesson: 2SQS-43.1, 08-02-770 Objective: 6- Describe the control, protection and interlock functions for the control room components associated with the Radiation Monitoring System, including automatic functions, and changes in equipment status as applicable.

IUA: 073 A4.02

~~

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 KIA # E01 G2.4.31 Importance Rating 3.3 Emergency Procedures / Plan Knowledge of annunciators alarms and indications, and use of the response instructions Proposed Question: Common 61 Given the following conditions:

An inadvertent Safety Injection has occurred.

0 The crew has completed action to terminate SI in accordance with ES-1.1, SI Termination.

0 The following annunciator is illuminated:

3 AUTO SAFETY INJECTION BLOCKED Which ONE of the following actions is required to clear the annunciator?

A. Depress and hold the SI reset pushbuttons until the light clears B. Reset SI, CIA, CIB, and SI Recirc Changeover C. Close, and then re-open the reactor trip breakers.

D. Depress and hold reactor trip pushbutton until the light clears.

Proposed Answer: C Explanation (Optional):

A. Incorrect. This action is what causes the annunciator to illuminate.

8. Incorrect. Resetting SI will bring in the annunciator; the other actions will have no effect C. Correct. P4 resets the auto SI circuitry, which will be actuated by cycling RTBs.

D. Incorrect. If the RTBs are already open, this will have no effect.

Technical Reference(s): ES-1.1, Step 31 (Attach if not previously provided)

NUREG-1021, Revision 9 121 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning 0bjective: 3SQS-53.3 Objective 3 (As available)

Question Source: Bank ##

Modified Bank ## (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 122 BVPS Unit 2

~~ ~

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier ## 1 Group ## 2 WA # E07 EK3.3 Importance Rating 3.8 Knowledge 01 the reasons for the following responses as they apply to the (Saturated Core Cooling) Manipulation of controls required to obtain desired operating results during abnormal and emergency situations.

Proposed Question: Common 62 Select the statement that describes the purpose of depressurizing the SGs in FR-C.l, Response To Inadequate Core Cooling.

A. To prevent the SGs from acting as a source of heat to the inadequately cooled core B. To reduce RCS pressure in order to allow SI accumulator and/or LHSl flow C. To maximize the effectiveness of reflux boiling as a means of core cooling.

D. To minimize the possibility of lifting a secondary safety valve in the event of a SG tube rupture.

Proposed Answer: 6 Exp Ianat ion (0pt io nal) :

A. Incorrect. If in FR-(2.1, SGs are already a marginal heat sink.

B. Correct.

C. Incorrect. Reflux boiling is most likely not the mode of heat transfer in this condition.

D. Incorrect. Reducing pressure would provide this function, but is not performed for this reason in FR-C.1.

Technical Reference(s): FR-C.1 Background (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-53.3 Objective 3 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New NUREG-1021, Revision 9 123 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Cornprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

BVPS-1 Bank 3777 NUREG-1021, Revision 9 124 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group ## 2 KIA # -

E08 EK3.3 Importance Rating 3.7 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.

Proposed Question: Common 63 Following a small break LOCA, the crew is performing action contained in FR-P.l, Response To Imminent Pressurized Thermal Shock Conditions.

Which ONE of the following describes the difference in SI termination criteria for FR-P.l as opposed to the criteria in ES-1.1, Safety Injection Termination?

The criteria in FR-P.l is ...

A. less restrictive to allow for a faster reduction in RCS pressure.

B. more restrictive to allow for a more controlled reduction in RCS pressure C. less restrictive because subsequent RCP restart is likely to cause propagation of any existing flaw in the reactor vessel walls.

D. more restrictive because subsequent RCP restart is likely to cause propagation of any existing flaw in the reactor vessel walls.

Proposed Answer: A Exp Ianat ion (0pt io nal) :

A. Correct. The criteria are less restrictive so that SI reduction can aid the RCS pressure reduction. RVLlS level rather than PRZR level is used as a measure of inventory.

B. Incorrect. Opposite of actual reason.

C. Incorrect. RCP restart will not cause a crack to propagate under any of the conditions analyzed for this procedure. However, propagation of flaws is a major concern in a PTS event.

D. Incorrect. RCP restart will not cause a crack to propagate under any of the conditions analyzed for this procedure. However, propagation of flaws is a major concern in a PTS event.

Technical Reference(s): FR-P.1 Background (Attach if not previously provided)

NUREG-1021, Revision 9 125 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-53.3 Objective 3 (As available)

Question Source: Bank # X Modified Bank # (Note changes or ;.tach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

Salem 2001 NRC exam Western Tech Bank Archive NUREG-1021, Revision 9 126 BVPS Unit 2

~ ~~ ~ ~ ~ ~

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Out line Cross-reference: Level RO SRO Tier # 1 Group # 2 WA ## E13 EK2.1 Importance Rating 3.0 Knowledge of the interrelations between the (Steam Generator Overpressure) and the following- Components. and functions of control and safety systems, including instrumentation. signals, interlocks. failure modes, and automatic and manual features Proposed Question: Common 64 A reactor trip has occurred. The crew has entered FR-H.2, Response To Steam Generator Overpressure based upon a YELLOW condition on the Heat Sink CSF Status Tree. The following conditions exist:

SG 21A pressure indicates 1 150 psig.

0 SG 21 B and 21 C pressures indicate 1010 psig.

SG 21A NR level is 65%.

Instrument air header pressure is 30 psig and lowering.

Which ONE of the following actions will be required to mitigate the SG overpressure condition?

A. Initiate AFW flow.

6. Open condenser steam dump valves.

C. Go to FR-H.3, Response to SG High Level to reduce pressure by reducing SG level.

D. Operate the residual heat release valve to reduce SG pressure.

Proposed Answer: D Explanation (Optional):

A. Incorrect. Do not initiate Fvv or AFW flow with a high level present.

B. Incorrect. Condenser steam dump is not available.

C. Incorrect. Only go to FR-H.3 if level is greater than 94"/".

D. Correct. Loss of instrument air requires use of RHR valve to lower SG pressure Technical Reference(s): FR-H.2 (Attach if not previously provided)

NUREG-1021, Revision 9 127 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQSD-53.3 Objective 3 (As available)

Question Source: Bank ##

Modified Bank # X (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

Western Tech Bank Archive NUREG-1021, Revision 9 128 BVPS Unit 2

BVPS-1 and BVPS-2 2005 NRC Examination Modified Test Items 2005 Question 64 See attached test item Robinson 2001 Audit Exam Question

H.B. Robinson Site Specific Written NRC Examination Reactor Operator Final Worksheet Question RO 067 !

N ti in ber :

I Question: Given the following conditions:

A reactor trip has occurred.

The crew has entered FRP-H.2, Response to Steam Generator Overpressure, based upon a YELLOW condition on the Heat Sink Status Tree.

0 A SG pressure indicates 1 150 psig 0 B and C SG pressures indicate 1010 psig A SG level is 65%

0 APP-002-F7, INST AIR HDR LO PRESS, is lit 0 Instrument Air Header Pressure is 30 psig Which one of the following actions will be required to mitigate the SG Overpressure condition?

A. Initiate AFW flow B. Locally operate A SG PORV to dump steam C. Go to FRP-H.3, Response to SG High Level, to reduce pressure by reducing SG level D. Align Nitrogen to SG PORVs using AOP-017, Loss of Instrument Air, and attempt to dump steam Answer : D. Align Nitrogen to SG PORVs using AOP-017. Loss of Instrument Air, and attempt to dump steam Justification: A- Incorrect. Do not initiate FW or AFW flow with a high level present.

B- Incorrect. There is no guidance for local operation of PORVs in this procedure C- Incorrect. Only go to FR-H.3 if level is greater than 84%

D- Correct. If Loss of Instrument Air is present, step 4 has the crew align Nitrogen..

Tier/Group 113 10CFR55.41 41 IOCFR55.43 B/N/M New KIA #:

K/A Values: 3 .O I Cog Level: Coin prehens ion

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 WA # -

068 G2.1.30 Importance Rating 3.9 Conduct of Operations: Ability to locate and operate components, including local controls Proposed Question: Common 65 The Control Room is being evacuated to the Emergency Shutdown Panel. The crew is preparing to evacuate in accordance with AOP-2.33.1A, Control Room Inaccessibility. All equipment is operating as designed.

Which ONE of the following describes the operation of the emergency diesel generators (EDGs) during this evolution?

A. EDGs are started and vital equipment is loaded from the Control Room. Control is transferred to the Emergency Shutdown Panel after evacuation.

6 . EDGs remain in standby status. Control is switched to the Emergency Shutdown Panel after evacuation.

C. EDGs remain in standby status. Control is transferred to the local control panel from the Control Room prior to evacuation.

D. EDG control is switched to the local control panel after evacuation. EDGs are started and vital equipment is loaded as soon as local control is established.

Proposed Answer: B Explanation (Optional):

A. Incorrect. EDGs are not started unless necessary.

6 . Correct.

C. Incorrect. EDG control is established at the ESP.

0 . Incorrect. EDG control is established at ESP, and only if needed.

Technical Ref erence(s): AOP-2.33.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: None NUREG-1021, Revision 9 129 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 2SQS-56G.1 Objective 4 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2002 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

BVPS-2 2002 Audit Exam NUREG-1021, Revision 9 130 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 1 KIA # (22.1.1 Importance Rating 3.7 Knowledge of conduct of operations requirements.

Proposed Question: Common 66 You are a licensed Reactor Operator and have been assigned to an administrative function.

You are current in maintaining qualification in the Licensed Operator Requalification Program.

The date is February 23, 2005 and you are preparing to return to shift duties.

The time you were on shift since this assignment is as follows:

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months on December 24,2004 BOP 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months on November 23,2004 BOP 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months on November 22,2004 BOP 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months on September 19,2004 RO 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months on September 18,2004 RO Which ONE of the following describes the status of your license in accordance with 1/2-ADM-13511Licensed Operator Retraining Program?

A. Your license is active. You may stand watch with no restrictions.

B. Your license is active. You must regain qualification as RO by standing three (3) additional 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts in the RO position.

C. Your license is inactive. You must reactivate your license by standing five (5) 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shifts under instruction in the RO position ONLY.

D. Your license is inactive. You must reactivate you license by standing five (5) 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shifts under instruction as either RO or BOP.

NUREG-1021, Revision 9 131 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: D Explanation (Optional):

A. Incorrect. License is inactive due to insufficient hours last quarter.

B. Incorrect. Proficiency is not based on board position.

C. Incorrect. May regain proficiency in either position.

D. Correct. Last calendar quarter did not stand 5 shifts.

Technical Reference(s): 112 ADM 1351 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

Learning Objective: N/A (As available)

Question Source: Bank #

Modified Bank # X (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Cornments:

Robinson 2004 Audit exam - Western Tech Bank Archive NUREG-1021, Revision 9 132 BVPS Unit 2

BVPS-1 and BVPS-2 2005 NRC Examination Modified Test Items 2005 Question 66 IX See attached LXR file

Qu&P~/L 66 QUESTIONS REPORT BUPS for AUDIT FINAL

1. G2.I.24 00 1 You are a Licensed Reactor Operator. You have been assigned to an administrative function since January 29, 2004.

You are current in Licensed Operator Requalification.

The date is July 23, 2004. You are preparing to return to shift duties.

The times you were on shift since this assignment are as follows:

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months on June 24 BOP 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months on May 23 BOP 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months on May 22 BOP 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months on March 19 RO 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months on March 18 RO Which ONE (1) of the following describes the status of your license IAW OMM-001-05, Training and Qualification?

A. Your license is active. You may stand watch with no restrictions B. Your license is active. You must regain qualification as RO by standing 3 additional 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts in the RO position C. Your license is inactive. You must reactivate your license by standing four 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts under instruction in the RO position ONLY D,' Your license is inactive. You must reactivate your license by standing four 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts under instruction as either RO or BOP D is correct. Last calendar quarter did not stand 5 shifts Common Question 066 Tier 3 WA Importance Rating - RO 2.8 / SRO 2.8 Ability to obtain and interpret station electrical and mechanical drawings.

Reference(s) - OMM-001-5 Proposed References to be provided to applicants during examination - None Learning Objective -

Question Source - Modified Bank Question History - 2002 Audit Question Cognitive Level - Application 10 CFR Part 55 Content - 41 Comments - Change KA Wednesday, January 05,2005 10:49:43AM 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group ## 1 WA ## G2.1.25 Importance Rating 2.8 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data Proposed Quest ion: Common 67 Given the following conditions:

0 The Unit has been at 100% power for 3 weeks. All systems are in NSA 0 RCS boron concentration is 1000 ppm.

0 A controlled power reduction to 50% is to be performed.

Using the references provided and maintaining control rods at their current position, which ONE of the following describes the MINIMUM amount of boric acid required to initially maneuver the plant to 509'0 power?

A. 800 gallons B. 1 100 gallons C. 1400 gallons D. 1700 gallons Proposed Answer: B Exp Ianat ion (0ptiona I) :

A. Correct. Power defect is approximately 1000 pcm (2050 - 1050). A critical boron concentration of 1000 ppm indicates approximately 9500 MWD/MTU. Differential Boron worth at this concentration is approximately - 6.5 pcrdppm. Therefore, 1OOO/ - 6.5 = 154 ppm. Using boron addition nomograph shows approximately 900 gallons of boric acid or less.

B. Incorrect. High enough to allow for minor interpretation differences on nomograph reading.

C . Incorrect. Used to provide consistent distractor and allows for minor interpretation differences.

D. Incorrect. Used to provide consistent distractor and allows for minor interpretation differences.

NUREG-1021, Revision 9 133 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): Curve Book (26-13, CB-21, CB- (Attach if not previously provided) 28, CB-31, CB-36 Proposed references to be provided to applicants during examination: Curve Book Learning Objective: 2SQS-7.1 Objective 17 (As available)

Question Source: Bank #

Modified Bank # X (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

BVPS-1 2002 NRC exam NUREG-1021, Revision 9 1 34 BVPS Unit 2

Critical Boron Concentration vs Burnup HFP, ARO, Equilibrium Xenon Unit 2, Cycle 11 0

C n

m C

(D D Burnup (MWD/MTU) 2 0

CB-21 Record Jype # A9.3450

- wm 0

---250 pprn

- - -500ppm

750ppm

- - IO00 ppm

-1250 ppm

- 1600 ppm'

-2100 ppm Issue 11 Rev 0

CURVE BOOK - BVPS I1 CB-28 Record Type # A9.3450 0006 1 0008 1 OOOL 1 00091 000s1 OOOP 1 OOO 1 OOOZl t-00011 n

00001 g Y

0006 5 c

0008 5 Po OOOL 0009 0005 OOOP OOO 000z 000 1 0

Issue 11 Rev 0

- ~~ -

CURVE BOOK - BVPS ll CB-31 Record Type #9A.3450

-3ooo

-700

- 600

-so0

-wo

- 2500 v -MI"[

-8.33 7000 - ci 7000-Cf ) -3w

- 200

-2ooo -150 8 I

0' W

- loo z

- 90

- IS00 - 80 k

- 70 9

- 60 5 E

a

- so a0m

- lo00 - IO E a

- 30

- 20 t

IS

- 100

- 10 19 Boron Addition - Refer to Table 1 for Correction Factors (Refer to 20M-6.5.B.2, "RCS Volume")

ISSUE 11 REV 0

CURVE BOOK - BVPS II CB-36 Record Type #9A345D NOMOGRAPH CORRECTION FACTORS Plant Conditions Correction Factor Pressure T (AVG) (K)

(PSig) (OF) Pressurizer Level (See Note) 2235 547-570 Normal Operating 1.00 1600 500 No-Load 1.05 1200 450 No-Load 1-10 800 400 No- Load 1.16 400 350 No-Load 1.18 400 300 No-Load 1.20 400 300 Solid Water 1.35 400 200 -

No Load 1.28 400 200 S o l id Water 1.40 400 100 So1id Water 1.47 NOTE : CORRECTION FACTORS ARE APPLIED AS FOLLOWS:

(a) Boron Additiyn and Dilution Total Volume Nomographs V(Corrected) = (Nomograph)

(b) Boron Addition and Dilution Rate Nomographs dc -1 dc dt (Corrected) = K x dt (Nomograph)

ISSUE 11 REV 0

BVPS-1 and BVPS-2 2005 NRC Examination Modified Test Items 2005 Question 67 Given the following conditions:

0 The plant has been at 100% power for 3 weeks. All systems in NSA.

0 RCS boron concentration is 1I 0 0 ppm.

0 A controlled power reduction to 50% is required.

Using the references provided and maintaining control rods at their current position, which one of the following describes the amount of boric acid required to initially maneuver the plant to 50% power?

A. 900 gallons B. 1100 gallons C. 1300 gallons D. 1500 gallons Answer: A BVPS-1 2002 NRC Question 35

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group ## 2 WA # G2.2.12 Importance Rating 3.0 Knowledge of surveillance procedures Proposed Question: Common 68 When performing an OST procedure, which one of the following conditions PROHIBITS the use of N/A in the sign-off spaces provided?

A. Performance of partial tests.

6. Inability to perform the OST as written.

C. Performing an OST that pre-establishes conditions for non-performance of steps D. Performance of steps that cannot be performed due to plant conditions but do not change the intent of the procedure.

Proposed Answer: B Explanation (Optional):

A. Incorrect. Partial tests allow N/A.

6. Correct. Situation requires issuing a revision after placing equipment in a safe condition C. Incorrect. N/A is specifically used for this condition.

D. Incorrect. May use N/A as long as procedure intent is not altered.

Technical Reference(s): 1/2-ADM-O104 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SSG-Admin Objective 5 (As available)

NUREG-1021, Revision 9 135 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

BVPS-1 2002 NRC exam NUREG-1021, Revision 9 136 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 2 WA # G2.2.25 Importance Rating 2.5 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits Proposed Question: Common 69 Regarding Technical Specification SAFETY LIMITS, which ONE of the following core limitations does the OTAT reactor trip prevent exceeding?

A. Total Core Power B. Power Density (KW/ft)

C. Axial Flux Difference (AFD)

D. Departure from Nucleate Boiling (DNB)

Proposed Answer: D Explanation (Optional):

A. Incorrect. Power Range and OPAT trips provide protection for total core power B. Incorrect. Power Range and OPAT trips provide protection for power density.

C. Incorrect. Protection is from the power range trips.

D. Correct.

Technical Reference(s): TS Bases 3.3.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-1.1, Objective 16 (As available)

Question Source: Bank # X Modified Bank ## (Note changes or attach parent)

New Question History: Last NRC Exam NUREG-1021, Revision 9 137 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Level: Memory or Fundamental Knowledge X Cornprehens ion or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 x Comments:

BVPS-1 2002 NRC S36 NUREG-1021. Revision 9 138 BVPS Unit 2

Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 2 WA # G2.2.30 Importance Rating 3.5 Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area communication with fuel storage facility systems operated from the control room in support of fueling operations and supporting instrumentation Proposed Question: Common 70 Which ONE of the following is the responsibility of the Reactor Operator during refueling operations?

A. Monitor source range count rate during core reload, and remain cognizant of 1/M plot resuIts.

B. Verify the operability of the containment evacuation alarm each shift C. Maintain a 1/M plot or ICRR during fuel shuffle.

D. Update the Control Room Status Board for each core alteration as it is performed Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. Verified each day.

C. Incorrect. Reactivity monitoring function performed by the Refueling Group.

D. Incorrect. Reactivity monitoring function performed by the Refueling Group.

Technical Reference(s): Ops Expectations handbook (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: N/A (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam NUREG-1021, Revision 9 139 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

Prairie Island Western Tech Bank Question ID 44573 NUREG-1021, Revision 9 140 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 3 WA # G2.3.10 Importance Rating 2.9 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure Proposed Question: Common 71 Given the following conditions:

0 You are required to make an entry to a Locked High Radiation Area.

0 Your year-to-date exposure is 2.6 Rem Total Effective Dose Equivalent (TEDE).

0 The job is planned to take 20 minutes to complete, with 5 minutes transit time each way Transit path radiation levels are 400 mR/hr.

0 Work area radiation levels are 1200 mR/hr.

Which ONE of the following describes your eligibility to perform this task?

A. You may perform this task provided you are signed onto a High Radiation Area RWP

6. You may not perform this task because you will exceed the BVPS Administrative TEDE limit.

C. You may perform this task provided you meet the requirements for a Planned Special Exposure (PSE).

D. You may not perform the task because your current year to date exposure is already within 80°/b of the BVPS Administrative TEDE Limit.

Proposed Answer: A Explanation (Optional):

A. Correct.

6. Incorrect. BVPS TEDE is 4 Rem. Actual exposure results in a little over 3 Rem C. Incorrect. PSE not required, rates not high enough.

D. Incorrect. 80% of BVPS TEDE would be 3.2 Rem.

Technical Reference(s): 1/2 ADM 1601 (Attach if not previously provided)

NUREG-1021, Revision 9 141 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: (As available)

Question Source: Bank ## X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2002 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 x Comments:

BVPS-2 2002 NRC S94 NUREG-1021, Revision 9 142 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 3 WA ## G2.3 11 Importance Rating 2.7 Abilliy to control radiation releases Proposed Question: Common 72 Given the following conditions:

0 A rzpid load reduction from 100% power to 65% power was performed approximately 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ago.

[ZCHS*RQlOl A], Reactor Coolant Letdown Low Range Monitor is in high alarm.

[ZCHS'RQl 01B], Reactor Coolant Letdown High Range Monitor has just reached its HIGH alarm setpoint.

Actions of 20M-43.4.AAC, Radiation Monitoring HIGH have been completed.

0 Chemistry confirms RCS activity exceeds TS 3.4.8 limits.

The US directs a plant shutdown be performed.

Which ONE of the following actions is subsequently performed to limit the release of radioactivity?

A. MSlVs are closed.

B. SG atmospheric dump valve setpoints are raised.

C. RCS is cooled down below 5 0 0 T D. Maximum condensate polishers are placed in service.

Proposed Answer: C Explanation (Optional):

NUREG-1021, Revision 9 143 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet A. Incorrect. Closing MSIVs would contribute to radiation release through the SG ADVs and safety valves if cooldown and depressurization were not performed in a timely manner.

B. Incorrect. SG ADV setpoints are normally raised in SGTR procedure, but are operated manually at BVPS.

C. Correct.

D. Incorrect. Condensate polishing would help clean the secondary plant, but is not an action performed in accordance with the ARPs.

Technical Reference(s): T.S. 3.4.8 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-43.1 Objectives 9/10 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

BVPS-1 2002 NRC Western Tech Bank 46428 NUREG-1021, Revision 9 144 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 4 KIA ## G2.4.29 Importance Rating 2.6 Knowledge of the emergency plan.

Proposed Question: Common 73 Which of the following is the LOWEST emergency classification at which the Technical Support Center (TSC) MUST be activated?

A. Unusual Event B. Alert C. Site Area Emergency D. General Proposed Answer: B Explanation (Optional):

A. Incorrect. NUE does not require TSC staffing.

B. Correct.

C. Incorrect. Staffed at the Alert level.

D. Incorrect. Staffed at the Alert level.

Technical Reference(s): 1/2 EPP-1-3 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New NUREG-1021, Revision 9 145 BVPS Unit 2

~ ~ _ _ _ ~ ~ ~

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

Indian Point 3 Audit Exam; 2002 Western Technical Services, Inc. Exam Bank ID 44958.

NUREG-1021, Revision 9 146 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier ## 3 Group # 4 WA # G2.4.20 Importance Rating 3.3 Knowledge of operational implications of EOP warnings, cautions, and notes Proposed Question: Common 74 During the performance of EOP actions, the crew observes a NOTE prior to Step 1 of the EOP, and a CAUTION prior to Step 3 of the EOP.

Which ONE of the following describes the applicability of these statements during the performance of the EOP?

A. The NOTE is applicable throughout the entire procedure. The CAUTION applies to Step 3 ONLY.

6. The NOTE applies to Step 1 ONLY. The CAUTION applies to Step 3 ONLY C. The NOTE is applicable throughout the entire procedure. The CAUTION applies to all steps of the procedure that succeed it.

D. The NOTE applies to Step 1 ONLY. The CAUTION applies to all steps of the procedure that succeed it.

Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. Note applies to the entire procedure.

C. Incorrect. Caution applies only to the step it precedes D. Incorrect. Opposite of actual application.

Technical Reference(s): EOP User's Guide (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-53.1 Objective 1 (As available)

Question Source: Bank #

NUREG-1021, Revision 9 147 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level : Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 148 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 4 WA # G2.4.48 Importance Rating 3.5 Ability to interpret control room indications to verify the status and operation of system and understand how operator &tons and directives dffmt plant and system conditions Proposed Question: Common 75 Given the following conditions:

A reactor trip and safety injection have occurred.

All equipment is operating as designed.

The crew is performing diagnostic actions of E-0, Reactor Trip Or Safety Injection Containment pressure is 19 psig and LOWERING.

RCS pressure is 1250 psig and STABLE.

RCS subcooling margin is 46°F and STABLE.

PRZR level is 4% and RISING.

All AFW pumps are running with 400 gpm flow.

All RCPs are STOPPED.

Based upon conditions above, in which ONE of the following procedures will the crew start a reactor coolant pump, if it is desired?

A. ES-1.3. Transfer to Cold Leg Recirculation B. ES-1.1, SI Termination C. E-1, Loss Of Reactor Or Secondary Coolant D. ES-1.2, Post-LOCA Cooldown And Depressurization Proposed Answer: D Explanation (Optional):

A. Incorrect. Use of ES-1.3 is not appropriate for these conditions.

6 . Incorrect. SI Termination criteria is not met.

C. Incorrect. Transition to ES-1.2 occurs first.

D. Correct. ES-1.2 is performed which will start RCPs during the RCS cooldown NUREG-1021, Revision 9 149 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): ES-1.2 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-53.3 Objective 3 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 x Comments:

Byron Western Technical Services, Inc. Exam Bank ID 42085 NUREG-1021, Revision 9 150 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA # 025 AA2.02 Importance Rating 3.8 Ability to determine and interpret the following as they apply to the Loss of Residual Heal Removal System Leakage of reactor coolant from RHR into closed cooling water system or into reactor building atmosphere Proposed Question: SRO 76 Given the following conditions:

The Unit is in Mode 4.

RHS Train B is in service.

PRZR level is 20% and dropping.

Containment sump alarms are occurring.

Containment radiation monitors are alarming.

Which ONE of the following describes the action required under these conditions?

A. Manually initiate Safety Injection in accordance with AOP-2.6.5, Shutdown LOCA.

B. Stop RHS Pump 21B in accordance with AOP-2.10.1 Residual Heat Removal System Loss I

C. Isolate letdown and raise charging flow in accordance with AOP-2.6.5. Shutdown LOCA D. Operate HHSl pumps as necessary to maintain RCS inventory in accordance with AOP-2.10.1, Residual Heat Removal System Loss.

Proposed Answer: C Explanation (Optional):

A. Incorrect. Plant conditions preclude initiation of SI.

B. Incorrect. Would not stop RHS pump until cavitation, and wrong procedure.

C. Correct.

D. Incorrect. Wrong procedure, and would perform other steps prior to using HHSl Technical Reference(s): AOP-2.6.5 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE NUREG-1021 Revision 9 151 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 2SQS-53C. 1 Objective 5 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comp rehens ion or Analysis X 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 5 because the SRO must assess plant conditions and choose the correct procedure and action.

NUREG-1021, Revision 9 152 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Out Iine Cross-ref e rence : Level RO SRO Tier # 1 Group # 1 KIA # 029 EA2.01 Importance Rating 4.7 Ability to determine or interpret the following as they apply to a ATWS Reactor nuclear instrumentation Proposed Question: SRO 77 Given the following conditions:

0 A manual reactor trip is attempted by the RO.

Reactor Trip Breaker B indicates closed on PSMS.

All lights on the DRPl display are extinguished.

Reactor power indicates 28% and stable.

The crew has entered E-0, Reactor Trip Or Safety Injection.

Which ONE of the following describes the condition of the reactor and the appropriate action?

A. The reactor is tripped. Continue in E-0,Reactor Trip Or Safety Injection.

B. The reactor is tripped. Emergency boration is required per ES-0.1, Reactor Trip Response.

C. The reactor is NOT tripped. Transition to FR-S.1, Response To Nuclear Power Generation -

ATWS.

D. The reactor is NOT tripped. Dispatch an operator to locally trip the reactor and initiate a turbine trip per E-0, Reactor Trip Or Safety Injection.

Proposed Answer: C Explanation (Optional):

A. Incorrect. Power Range indication does not show prompt drop as expected post-trip.

B. Incorrect. The reactor is not tripped, transition is to FR-S.1, not ES-0.1.

C. Correct.

D. Incorrect. E-0 does not dispatch anyone to locally trip the reactor.

Technical Reference@): E-0, FR-S.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE NUREG-1021, Revision 9 153 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 3SQS-53.3 Objective 3 (As available)

Question Source: Bank #

Modified Bank #f (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 5 because the SRO must assess plant conditions and choose the correct procedure.

NUREG-1021, Revision 9 154 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 KIA # 038 ~ 2 . 2 . 2 5 Importance Rating 3.7 Equipment Control Knowledge of bases in technical specifications for limiting conditions for operations and safety limits Proposed Question: SRO 78 With the plant in Mode 1, 2, or 3, Technical Specifications limit the RCS activity to 5 0.35 ,uCi/gm Dose Equivalent 1-131.

Which ONE of the following describes the basis for this limit?

A. In the case of a steam break-induced steam generator tube rupture, ensures offsite dose does not exceed a small fraction of 10CFRlOO guidelines.

B. In case of a LOCA, ensures offsite dose does not exceed a small fraction of 10CFRlOO guidelines.

C. In case of a steam break-induced steam generator tube rupture, ensures offsite dose rates do not exceed1 OCFR20 limits.

D. In case of a LOCA, ensures offsite dose rates do not exceed 10CFR20 limits.

Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. LOCA is not the concern for RCS activity.

C. Incorrect. 10CFR20 limits are for normal operation.

0 . Incorrect. LOCA is not the concern, and 10CFR20 limits are for normal operation Technical Reference@): T.S. 3.4.8Bases (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQSTS.3 Objective 5.B (As available)

Question Source: Bank # X NUREG-1021, Revision 9 155 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 x Comments:

BV-2 Audit 2002 10CFR55.43(b)item 2 because the SRO must understand Technical Specification Bases.

NUREG-1021, Revision 9 156 BVPS Unit 2

BVPS-1 and BVPS-2 2005 NRC Examination Modified Test Items 2005 Question 78 With the plant in Mode I , 2, or 3, Tech. Specs limit the reactor coolant system activity to I 0.35 pCilgm dose equivalent 1-131.

Which One (I) of the following describes the basis for this limit?

A. In case of a steam generator tube rupture, ensures off-site dose does not exceed a small fraction of 10CFRI 00 guidelines.

B. In case of a LOCA, ensures off-site dose does not exceed a small fraction of 10CFRI 00 guidelines.

C. In case of a steam generator tube rupture, ensures off-site dose rates do not 10CFR20 limits.

A. In case of a LOCA, ensures off-site dose rates do not 10CFR20 limits.

Answer: A BVPS-2 2002 Audit Question 51

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO S RO Tier # 1 Group # 1 WA # 058 G2.2.25 Importance Rating 3.7 Equipment control Knowledge of bases in technical specifications for limiting conditions for operations and safety limits Proposed Question. SRO 79 Given the following conditions:

0 The Unit is in Mode 6.

Refueling is in progress with an irradiated fuel assembly movement in progress in containment.

Train Ais the Protected Train.

Train B 125V DC Bus 2-2 is out-of-service for battery replacement.

125VDC Bus 2-3 sustains a fault and is de-energized. The Refueling crew is ordered to complete the move in progress and then suspend refueling operations.

Which ONE of the following describes the reason that Technical Specifications requires suspending fuel movement?

A. The failure of DC Bus 2-3 also makes 120V AC distribution inoperable B. Failure of protected train DC power raises the Shutdown Risk level to an unacceptable RED status.

C. The plant no longer meets the initial conditions assumed in the safety analysis of a redundant set of AC and DC power sources operable during an assumed loss of off-site AC power and single failure of 1 other AC source.

D. There is insufficient instrumentation and control power available to recover from a postulated event, such as a Fuel Handling Accident.

Proposed Answer: D Explanation (Optional):

A. Incorrect. Even though the statement is true, it is not the reason that fuel movement is suspended.

B. Incorrect. May be a true statement, but Shutdown Risk and TS are not interdependent.

C. Incorrect. Basis for operability in Modes 1 - 4. Plant is in Mode 6.

D. Correct.

NUREG-1021, Revision 9 157 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): TS 3.8.2.4 Basis (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQSTS.3 Objective 5.B (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 x Corn ments:

10CFR55.43(b) item 2 because the SRO must understand Technical Specification Bases NUREG-1021, Revision 9 158 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group ## 1 WA ## 062 G2.4.31 Importance Rating 3.4 Emergency Procedures / Plan Knowledge of Annunciators alarms and indications, and use of the response instructions Proposed Question: SRO 80 Given the following conditions:

The plant is at 100% power with all systems in NSA The following annunciators are in alarm:

[A1- 4 q , Service Water Pump Auto StarVAuto Stop 0 [A1-4G], Service Water Header Pressure Low

[A1-5F], Standby Service Water Pump Auto Start/Auto Stop Additionally, the operators note the following conditions:

[2SWS*P21A], Service Water Pump is tripped (previously running) 0 [2SWE-P21A], Service Water Pump remains in Standby.

Which ONE of the following actions is required to restore the Service Water System?

A. Start 2SWE-P21A], remove 2SWS*P21 A from service, and place 2SWS*P21C on the 2AE Bus in accordance with the ARPs and the applicable section of 20M-30.

8. Start 2SWE-PZl A, remove 2SWS*P21 A from service, and place 2SWS*P21C on the 2DF Bus in accordance with the ARPs and the applicable section of 20M-30.

C. Align 2SWS*P21B to the Aheader, and place 2SWS*P21C on the 2AE Bus in accordance with AOP-2.30.1, Service Water/Normal Intake Structure Loss.

D. Align 2SWS*P21B to the Aheader, and place 2SWS*P21 C on the 2DF Bus in accordance with AOP-2.30.1, Service Water/Normal Intake Structure Loss.

Proposed Answer: A Explanation (Optional):

NUREG-1021, Revision 9 159 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet A. Correct. Start the standby pump and place the swing pump on the bus with the pump that is inoperable.

B. Incorrect. 2DF Bus already has a running SW pump.

C. Incorrect. Wrong action for the given failure, and wrong procedure use.

D. Incorrect. Wrong action and wrong bus for the failure given, and wrong procedure usage.

Technical Reference(s): 20M-30.4.AfV4, AAB, AAF (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE -

Learning Objective: 2SQS-30.1 Objective 9 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 5 because the SRO must assess plant conditions and choose the procedure and actions for mitigation.

NUREG-1021, Revision 9 160 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 KIA # E l l EA2.1 Importance Rating 4.2 Ability to determine and interpret the following as they apply to the (Loss of Emergency Coolant Recirculation) Facility conditions and selection of appropriate procedures during abnormal and emergency operations Proposed Quest ion: SRO 81 A reactor trip and safety injection have occurred ECA-1.2, LOCA Outside Containment has been entered from E-0, Reactor Trip Or Safety Injection.

After closing the valves listed in ECA-1.2, the following conditions exist:

RCS pressure is 1400 psig and STABLE.

ECCS flow is STABLE.

Which ONE of the following describes the status of the LOCA and required action?

A. The LOCA is isolated. Transition to E-1, Loss Of Reactor Or Secondary Coolant B. The LOCA is NOT isolated. Transition to ECA-1.1, Loss Of Emergency Coolant Recirculation.

C. The LOCA is NOT isolated. Transition to E-0, Reactor Trip Or Safety Injection D. The LOCA is isolated. Transition to ES-1.1, SI Termination Proposed Answer: B Ex pI anat ion (0ptio nal) :

A. Incorrect. LOCA is NOT isolated with RCS pressure and SI flow stable.

B. Correct. Unisolable LOCA, use ECA-1.1.

C. Incorrect. E-0 is the wrong transition.

D. Incorrect. LOCA is NOT isolated.

Technical Reference(s): ECA-1.2 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE NUREG-1021, Revision 9 161 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 3SQS-53.3 Objective 3 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 x Comments:

BVPS-2 Audit Exam 2002 Western Technical Services, Inc. Exam Bank ID 47439.

10CFR55.43(b) item 5 because the SRO must assess plant conditions and choose the appropriate procedure.

NUREG-1021, Revision 9 162 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Quest ion Worksheet Examinat i on Out Iine Cross-reference: Level RO SRO Tier # 1 Group # 2 WA ## 037 G2.4.30 Importance Rating 3.6 Erncrgency Procedures / Plan Knowledge of which events related to system operationdstatus should be reported to outside dyencies Proposed Question: SRO 82 Given the following conditions:

0 0802: A SG tube leak is discovered.

0 0814: A plant shutdown is commenced.

0 081 8: The reactor is tripped and safety injection is initiated based upon inability to maintain PRZR level.

0822: ALERT is declared.

Which ONE of the following is the LATEST time that the NRC may be notified of this event?

A. 0902

6. 0914 C. 0918 D. 0922 Proposed Answer: D Exp Ianat ion (0ptio nai) :

A. Incorrect. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after initial indication of the event.

6 . Incorrect. 1hour after shutdown commenced (would be a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months notification).

C . Incorrect. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after reactor trip and conditions are available for the classification D. Correct. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after declaration of the event is the longest time allowed.

Technical Reference(s): 1/2 EPP-1-1B (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: (As available)

NUREG-1021, Revision 9 163 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 5 because the SRO must assess the event and reportability, and determine the correct time to meet the NRC commitment.

NUREG-1021, Revision 9 164 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 KIA # EO9 EA2.2 Importance Rating 3.8 Atiility to determine and interpret the following as they apply to the Natural Circulation Operations Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments Proposed Question : SRO a3 Given the following conditions:

0 A reactor trip has occurred due to a loss of offsite power.

0 The crew is performing actions of ES-0.2, Natural Circulation Cooldown 0 RVLIS is NOT available.

0 The crew has commenced RCS depressurization to 1950 psig.

The following conditions are indicated:

RCS pressure is 2030 psig and trending DOWN.

0 RCS Tavg is 547QFand trending DOWN slowly.

0 PRZR Level is 21% and trending DOWN slowly.

Which ONE of the following actions is required?

A. Continue depressurization to 1950 psig and block SI B. Initiate Safety Injection and go to E-0, Reactor Trip Or Safety Injection.

C. Stop the cooldown, Block SI, and initiate depressurization to 1950 psig D. Stop the depressurization and go to ES-0.4, Natural Circulation With Steam Void In Vessel (Without RVLlS ) .

Proposed Answer: A Explanation (Optional):

NUREG-1021, Revision 9 165 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet A. Correct. Plant conditions are consistent with maintaining the cooldown.

B. Incorrect. SI actuation criteria are not met.

C. Incorrect. SI block does not occur until 1950 psig.

D. Incorrect. Indications of voiding, or conditions that may cause voiding, do not exist.

Technical Reference(s): ES-0.2 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQSD-53.3 Objective 3 (As available)

Question Source: Bank #

Modified Bank # X (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 5 because the SRO must evaluate plant conditions and select the appropriate procedural action.

NUREG-1021, Revision 9 166 BVPS Unit 2

BVPS-1 and BVPS-2 2005 NRC Examination Modified Test Items 2005 Question 83 Given the following conditions:

A reactor trip has occurred due to Loss of Off-Site Power.

0 The crew is performing actions of ES-0.2, Natural Circulation Cooldown.

0 Train A of RVLIS is Out of Service.

0 The crew has commenced RCS cooldown and depressurization.

o RCS pressure is 1780 psig and Trending DOWN.

o RCS Tavg is 448OF and Trending DOWN.

o The RO determines that a Safety Valve on SG A is partially failed open.

o RCS cooldown rate is approximately 40°F/Hr and CANNOT be reduced.

o Pressurizer Level is 35% and Trending UP slowly.

Which one of the following actions will be required in accordance with ES-0.2?

A. Repressurize the RCS to minimize void growth.

B. initiate Safety Injection and transition to E-2, Faulted Steam Generator Isolation.

C. Transition to ES-0.3, Natural Circulation with Steam Void in Vessel (With RVLIS).

D. Transition to ES-0.4, Natural Circulation with Steam Void in Vessel (Without RVLlS) .

Answer: C BVPS-1 2002 NRC Question SRO 75

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 KIA # E01 EA2.1 Importance Rating 4.0 Ability to determine and interpret the following as they apply to the (Reactor Trip or Safety Injection Rediagnosis) Facility conditions and selection of appropriate procedures during abnormal and emergency operations Proposed Question: SRO 84 Following a reactor trip and safety injection due to a faulted SG inside containment, the f 01lowing conditions exist:

All equipment is operating as designed.

The crew has performed actions of E-2, Faulted Steam Generator Isolation Containment pressure is 19 psig and LOWERING.

RCS pressure is 1850 psig and STABLE.

RCS subcooling margin is 110°F and STABLE.

PRZR level is 40% and RISING.

Affected SG WR level is 10%.

All AFW pumps are running with 390 gpm flow.

Unaffected SG NR levels are 33% and RISING.

Which ONE of the following conditions exists, and which ONE of the following procedures will be used next?

A. The affected SG is still blowing down. Remain in E-2, Faulted Steam Generator Isolation.

B. SI Termination criteria is satisfied. Go to ES-1.1 SI Termination.

C. A LOCA is in progress. Go to E-1 Loss Of Reactor Or Secondary Coolant.

D. A RED condition exists on the Heat Sink CSF Status Tree. Go to FR-H.l, Response To Loss Of Secondary Heat Sink.

Proposed Answer: B Explanation (Optional):

A. Incorrect. May transition once steps are complete.

6. Correct.

C. Incorrect. LOCA is not evidenced based on the conditions given.

D. Incorrect. A Red Path does not exist, only 1 SG with level < FR-H.l entry conditions.

NUREG-1021, Revision 9 167 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): E-2 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-53.3 Objective 3 (As available)

Question Source: Bank #

Modified Bank # X (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 5 because the SRO must determine plant conditions and select appropriate procedure response.

Robinson 2002 NRC Exam; Western Technical Services, Inc. Exam Bank ID 19019 NUREG-1021, Revision 9 168 BVPS Unit 2

BVPS-1 and BVPS-2 2005 NRC Examination Modified Test items 2005 Question 84 Given the following conditions:

A Reactor Trip and Safety Injection have occurred.

0 The crew is performing actions of PATH-I. The following conditions exist:

o SPDS is reset. STA is monitoring CSF Status Trees.

o RCS Pressure is 2200 psig and stable.

o Pressurizer level is 22% and stable.

o SG Narrow Range levels are 25% and stable.

o SG Pressures are 1040 psig and stable.

o RCS temperature is 547 deg F and stable.

Which ONE ( I ) of the following describes the appropriate procedure for mitigation of the event in progress?

A. EPP-4, Reactor Trip Response.

B. EPP-7, SI Termination.

C. EPP-8, Post LOCA Cooldown and Depressurization.

D. GP-004, Post Trip Stabilization.

Answer: A Robinson 2002 NRC Exam Question 72

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group ## 2 WA # E06 G2.4.4 Importance Rating 4.3 Emergency Procedures / Plan Ability to recognize abnormal indications for system operating parameters which are entrydevel conditions for emergency and abnormal operating prmedures.

Proposed Question: SRO 85 Given the following conditions:

A LOCA has occurred.

ECCS has NOT functioned as required.

All RCP's are TRIPPED.

CET's indicate 626°F.

RVLlS Full Range is 40°/".

All SG pressures are approximately 1070 psig.

Total AFW flow is 380 gpm.

SG NR levels are 13Y0, 11%, and 17%, respectively.

Which ONE of the following procedures should the crew implement for these conditions?

A. FR-H.1, Response To Loss of Secondary Heat Sink 6 . FR-H.2, Response To Steam Generator Overpressure C. FR-C.1, Response To Inadequate Core Cooling D. FR-C.2, Response To Degraded Core Cooling Proposed Answer: D Explanation (Optional):

A. Incorrect. A Red Path on Heat Sink is not indicated.

B. Incorrect. A Yellow Path on Sink conditions does not exist.

C. Incorrect. Core Cooling CSF is Orange Path condition, not a Red Path.

D. Correct. Core Cooling CSF is in Orange Path condition.

Technical Reference(s): CSF Status Trees (Attach if not previously provided)

NUREG-1021, Revision 9 169 BVPS Unit 2

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ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-53.3 Objective 5 (As available)

Question Source: Bank ## X Modified Bank ## (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 5 because the SRO must evaluate plant conditions and determine the appropriate procedure selection.

Robinson/Harris 2004 Western Technical Services. Inc. Exam Bank archive NUREG-1021, Revision 9 170 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group ## 1 WA # 003 G2.1.33 Importance Rating 4.0 Conduct of Operations Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications Proposed Question: SRO 86 Given the following conditions:

0 The Unit is in Mode 1 after a refueling.

0 [2CHS'P21 A], Charging Pump and [2CHS*P21B], Charging Pump are operating. Pump discharge pressure indication is 2450 psig.

0 An extra letdown orifice is in service for RCS cleanup.

0 Total RCP seal injection flow indicates 30 gpm.

0 [2CHS'HCV186], Seal Water Filter Control Valve is FULL OPEN.

The US determines that seal injection flow is higher than the T.S. limit Which ONE of the following actions must be taken to restore RCP seal Injection flow to within Technical Specification Iimits?

A. Throttle closed 2CHS*HCVl86.

B. Adjust manual seal injection throttle valves C. Reduce the running speed of the operating charging pumps.

D. Remove a letdown orifice from service and stop one (1) charging pump Proposed Answer: B Explanation (Optional):

A. Incorrect. Design basis of SI system is violated with valve full open.

6 . Correct. Only way to ensure operability of ECCS.

C. Incorrect. Pumps are centrifugal pumps and the speed cannot be adjusted.

D. Incorrect. Reducing operating equipment still does not change basis of TS.

Technical Reference(s): TS 3.5.4 (Attach if not previously provided)

NUREG-1021, Revision 9 171 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: (As available)

Question Source: Bank ##

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 2 because the SRO must understand Technical Specification LCOs NUREG-1021, Revision 9 172 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # ~-1 KIA # 010 G2.2.22 Importance Rating 4.1 Equipment control Knowledge of limiting conditions for operations and safety limits Proposed Question: SRO 87 Which ONE of the following describes the components that are assumed to operate at their setpoints to ensure that RCS pressure remains below the Technical Specification Safety Limit?

Pressurizer Safety Valves.

A. ONLY.

B. and at least ONE (1) PRZR PORV.

C. and at least TWO(2) PRZR PORVs.

D. and all THREE (3) PRZR PORVs.

Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. PORVs are only required for LTOP.

C. Incorrect. PORVs are only required for LTOP.

D. Incorrect. PORVs are only required for LTOP.

Technical Reference(s): Tech Spec 3.4.3 (Attach if not previously provided)

~~

Proposed references to be provided to applicants during examination: NONE Learning Objective: (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X NUREG-1021, Revision 9 173 BVPS Unit 2

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ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 2 because the SRO must understand the basis for operability of equipment required by Technical Specifications.

NUREG-1021, Revision 9 174 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 KIA # 039 A2.05 Importance Rating 3.6 Ability to (a) predict the impacts of the lollowing mal-functions or operations on the MRSS and (b) based an predictions use prwedures to correct, control, or mitigate the consequences of those malfunctions or operations Increasing steam demand Its relationship to increase?in reactor power Proposed Question: SRO 88 Given the following conditions:

0 The plant is at 100% power with all systems in NSA.

0 The RO has recently performed a small dilution for Tavg control.

0 The following indications are available in the Control Room:

C) Power Range Nls are increasing.

o Tavg is decreasing.

o Steam flow and feed flow are slightly elevated Reactor power is 101?/o and rising slowly.

Which ONE of the following describes the event in progress and the action required?

A. Main steam line leak; reduce power by reducing turbine load as necessary

6. Inadvertent RCS dilution; reduce power and Tavg by inserting control rods.

C. Main steam line leak; trip the reactor and enter E-0, Reactor Trip Or Safety Injection D. Inadvertent RCS dilution; trip the reactor and enter E-0, Reactor Trip Or Safety Injection Proposed Answer: A Explanation (Optional):

A. Correct. Power increasing and temperature decreasing mean the transient is induced by the secondary (steam demand).

6. Incorrect. Temperature would be rising if a dilution was occurring.

C. Incorrect. No requirement for a reactor trip.

D. Incorrect. Not a dilution, and no reactor trip requirement is met.

Technical Reference@): Simulator (Attach if not previously provided)

NUREG-1021, Revision 9 175 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: (As available)

Q uest ion Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 5 because the SRO must evaluate plant conditions and determine appropriate procedural action.

NUREG-1021, Revision 9 176 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 KIA # 078 A2.01 Importance Rating 2.9 Ability to (a) predict the impacts of the following mallunctions or operations on the IAS, and (b) based on those predictions USF:

prwedures to correct control or mitigate the consequences of those malfunctions or operations Air dryer and filter malfunctions Proposed Qu estion SRO 89 Given the following conditions:

The Unit is at 100% power with all systems in NSA.

[21AS-PI-106], Instrument Air Pressure has been slowly decreasing and is reading 85 psig.

The crew enters AOP-2.34.1, Loss Of Station Instrument Air.

All station air compressors are running. No reports of air leakage have been received Which one of the following actions will be performed next in accordance with AOP-2.34.1, Loss Of Station Instrument Air?

A. Place the instrument air dryer bypass filters in service.

B. Place feedwater regulating valve control in MANUAL.

C. Start the motor driven AFW pumps.

D. Trip the reactor and enter E-0, Reactor Trip Or Safety Injection.

Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. Air pressure not low enough.

C. Incorrect. Have not lost control of MFPs, no need to start MDAFW pumps D. Incorrect. Reactor trip criteria on low air pressure is not met.

Technical Reference(s): AOP-2.34.1 (Attach if not previously provided)

NUREG-1021, Revision 9 177 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Quest ion Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-53C.1 Objective 5 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2002 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 5 because the SRO must evaluate plant conditions and determine appropriate procedural action.

NUREG-1021, Revision 9 178 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 103 A2.04 Importance Rating 3.6 Ability to (a) predict the impacts of the following malfunctions or operations on the containment system-and (b) based on those predictions, use procedures to correct, control, or mltlgate the consequences of those malfunctions ar operations Containment evacuation (including recognition of the alarm)

Proposed Question: SRO 90 The Unit is in Mode 6. Refueling operations are in progress. The Refueling SRO reports that a fuel assembly has been dropped.

Containment Purge Process Monitors are in high alarm.

For these conditions, which one of the following actions will be required by AOP-2.49.1, Irradiated Fuel Damage While Refueling?

A. Initiate a containment evacuation B. Manually initiate Control Room ventilation isolation.

C. Reset CREVS and manually align Control Room ventilation.

D. Start the Containment Air Recirculation System.

Proposed Answer: A Explanation (Optional):

A. Correct.

6. Incorrect. Control Room high radiation is not indicated requiring this action.

C. Incorrect. CREVS should not be actuated. High radiation for CREVS is not indicated.

D. Incorrect. Containment air recirculation system does not function to mitigate this event Technical Reference(s): AOP-2.49.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-53C.1 Objective 5 (As available)

NUREG-1021, Revision 9 179 BVPS Unit 2

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ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank ##

Modified Bank ## X (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 x Comments:

BVPS-1 2002 NRC Exam 10CFR55.43(b) item 5 and item 6 because the SRO must assess conditions and choose procedural action for a refueling accident.

NUREG-1021, Revision 9 180 BVPS Unit 2

BVPS-1 and BVPS-2 2005 NRC Examination Modified Test Items 2005 Question 90 Given the following conditions:

0 The plant is in Mode 1.

0 Spent Fuel is being loaded into shipping casks in the Spent Fuel Pool area.

Health Physics reports that a cask has been dropped. Immediately following the report, the Fuel Building evacuation alarm sounds.

Radiation Monitors [RM-IVS-l03A and B], Fuel Building Ventilation Exhaust, are in alarm.

Based on the above conditions, which one of the following actions will be required by AOP-1.49.1, Irradiated Fuel Damage?

A. Initiate Site Evacuation.

B. Manually initiate Control Room Isolation.

C. Reset CREBAPS and manually align Control Room Ventilation D. Align Leak Collection Exhaust flow to the Main Filter Banks using the Containment Purge System.

Answer: B BVPS-1 2002 NRC Exam Question SRO 87

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 WA # 001 G2.1.32 Importance Rating 3.8 Conduct 01 Operations Ability to explain and apply all system limits and precautions Proposed Question: SRO 91 The Unit is in Mode 1 at 91% power. Control Bank D Group 1 indicates the following:

0 Group step counter position is 136 steps 0 DRPl indicates the following:

o Control Rod H02 at 134 steps.

o Control Rod H14 at 145 steps.

3 Control Rod PO8 at 122 steps.

o Control Rod 608 at 120 steps.

Which ONE of the following describes the action(s) required by Technical Specifications and AOP-2.1.8, Rod Inoperability?

A. Immediately trip the reactor and emergency borate the RCS.

6. Reduce thermal power to less than 80% within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and restore both control rods to within alignment within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

C. Restore both control rods to within alignment in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in Hot Standby within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months D. Verify shutdown margin is within the limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in Hot Standby within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Proposed Answer: D Explanation (Optional):

A. Incorrect. A reactor trip is required for 2 dropped rods. Boration for stuck rods.

B. Incorrect. Power reduction is not required for rod misalignment.

C. Incorrect. More than 1 rod is misaligned. No opportunity provided for restoration D. Correct.

NUREG-1021, Revision 9 181 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): AOP-2.1.8 (Attach if not previously provided)

Tech Spec 3.1.3.1 Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-53C.1 Objective 5 (As available)

Question Source: Bank # X Modified Bank ## (Note changes or attach parent)

New Question History: Last NRC Exam 2002 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 2 and item 5 because the SRO must choose the appropriate action for the plant condition in accordance with Technical Specifications.

NUREG-1021, Revision 9 182 BVPS Unit 2

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ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 WA # 035 A2.01 Importance Rating 4.5 A h l i l y lo (a) predict the impacts of Ihe following malfunctions or operation on the SG/S system. and (b) based on those prediclions use procedures lo correct. control, or mitigate the consequences of those malfunctions or operations. Faulted or Ruptured SG Proposed Question: SRO 92 Given the following conditions:

A reactor trip and safety injection have occurred.

RCS pressure is 1600 psig and DECREASING.

PRZR level is offscale LOW.

Tavg is 500°F and DECREASING.

Containment pressure is 3 psig and INCREASING.

SG 21A pressure is 620 psig and DECREASING SG 21 B and 21 C pressures are 900 psig and STABLE.

Which ONE of the following procedures will be used immediately following transition from E-0. Reactor Trip Or Safety Injection?

A. ES-1.1, SI Termination B. ES-1.2, Post LOCA Cooldown And Depressurization C. E-2, Faulted Steam Generator Isolation D. ES-0.1, Reactor Trip Response Proposed Answer: C Explanation (Optional):

A. Incorrect. Criteria is not met for SI Termination.

6 . Incorrect. Transition to ES-1.2 occurs from E-1.

C. Correct.

D. Incorrect. SI is actuated, ES-0.1 would not apply.

NUREG-1021, Revision 9 183 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): E-2 Entry, E-0 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-53.3, Objective 3 (As available)

Question Source: Bank #

Modified Bank # X (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 x Comments:

BVPS-1 2002 Audit Exam 10CFR55.43(b) item 5 because the SRO must assess conditions and choose the correct procedure for the event in progress.

NUREG-1021, Revision 9 184 BVPS Unit 2

BVPS-1 and BVPS-2 2005 NRC Examination Modified Test Items 2005 Question 92 The reactor has tripped.

Safety Injection and Main Steam Line Isolation have actuated.

The crew is performing actions of E-0, Reactor Trip or Safety Injection. After evaluating RCP trip criteria, the following conditions exist:

RCS pressure 1650 psig and trending up SG Pressures approximately 770 psig and stable Tave 520' F and trending up AFW flow approximately 200 GPM to each SG SG NR levels off scale low Pressurizer level 15% and trending up Containment temperature is 105' F and stable Containment pressure is -0.1 psig and stable Which one of the following procedure transitions will be made upon exit from E-O?

A. E-2, Faulted Steam Generator Isolation

6. ES-1.I, SI Termination C. E-I, Loss of Reactor or Secondary Coolant D. ECA-1.2, LOCA Outside Containment Answer: B

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 -

Group # 2 KIA # 056 G2.4.50 Importance Rating 3.3 Emergency Procedures / Plan Ability to verify system alarm setpoints and operate controls identified in the alarm response manual Proposed Question: SRO 93 The Unit is at 7296 power with all systems in NSA The following annunciators are in alarm:

[ A M D ] , Condensate Pump Auto Start-Stop

[A&lOB], Steam Generator Feed Pump 21NB Suction Press Low The BOP determines that Condensate Pump 21 B has tripped. The control switch bright white indication is LIT.

Condensate Pump 21 C trips on overcurrent when a manual start is attempted Which ONE of the following describes the action required?

A. Trip the reactor. Enter E-0, Reactor Trip Or Safety Injection.

6. Reset and attempt one (1) restart of Condensate Pump 21 B C. Reduce power to less than 65% in accordance with AOP-2.24.1, Loss Of Main Feedwater D. Reduce load in accordance with the ARPs until Annunciator [A6-1OB] is clear Proposed Answer: D Explanation (Optional):

A. Incorrect. Do not meet reactor trip criteria.

6. Incorrect. Bright white indication would preclude restart of the pump.

C. Incorrect. Action is for a loss of a main feed pump.

D. Correct.

Technical Ref erence(s): 20M-22A.4.AAC (Attach if not previously provided) 20M-24.4.AAF

-_ Proposed references to be provided to applicants during examination: NONE NUREG-1021, Revision 9 185 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 2SQS-53C.1 Objective 5 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 5 because the SRO must assess plant conditions and choose the appropriate procedure.

NUREG-1021, Revision 9 186 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Out Iine Cross- refe rence: Level RO SRO Tier # 3 Group # 1 WA # G2.1.20 Importance Rating 4.2 Atiilily to execute procedure steps.

Proposed Question: SRO 94 Given the following conditions:

The crew is performing E-0, Reactor Trip Or Safety Injection.

The BOP has been directed to perform Attachment A-0.11, Verification Of Automatic Act ions, While performing Attachment A-0.11, the US determines that a transition to E-1, Loss Of Reactor Or Secondary Coolant is necessary.

Which ONE of the following actions is required?

A. Discontinue action in Attachment A-0.11 until directed by E-1 B. Continue action in Attachment A-0.11, but do not perform actions of any other Attachment until directed by E-1 .

C. Complete the action in Attachment A-0.11 prior to transitioning to E-1 D. Transition to E-1 and continue action as necessary in Attachment A-0.11 Proposed Answer: D Explanation (Optional):

A. Incorrect. Attachment A-0.11 is in progress and must be completed.

B. Incorrect. If other attachments become necessary, they will be performed as resources are available.

C. Incorrect. Performance of Attachment A-0.11 will not delay the actions of E-1.

D. Correct.

Technical Reference(s): EOP Users Guide (Attach if not previously provided)

NUREG-1021, Revision 9 187 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-53.1 Objective 1 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 x Comments:

BVPS-1 2002 Audit Exam 10CFR55.43(b) item 5 because the SRO must evaluate plant conditions and determine the correct procedural response.

NUREG-1021, Revision 9 188 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 1 WA ## G2.1.14 Importance Rating 33 Knowledge of system status criteria which require the notification of plant personnel Proposed Question: SRO 95 You are the Unit Supervisor on night shift, Saturday evening.

You receive a report from the Outside Tour Operator that a safety related component is mispositioned and there is indication of tampering.

Which ONE of the following describes the action required in accordance with 1/2-ADM-0701, Reporting and Notification of Potential Mispositioning or Tampering Events?

A. Direct the Operator to reposition the component and immediately report to the Control Room. Notify the Security Shift Supervisor.

B. Direct the Operator to reposition the component and immediately report to the Control Room. Direct the PAB Tour Operator to second check the component position.

C. Direct the Operator to leave the component in its current position and remain in the area.

Direct the PAB Tour Operator to verify the mispositioning.

D. Direct the Operator to leave the component in its current position and remain in the area Notify the Security Shift Supervisor.

Proposed Answer: D Explanation (Optional):

A. Incorrect. The component must not be repositioned.

B. Incorrect. The component must not be repositioned, thus no second check either.

C. Incorrect. A second verification is not required; Security must be notified.

D. Correct.

Technical Reference(s): 1/2 ADM 0701 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

Learning Objective: (As available)

NUREG-1021, Revision 9 189 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 5 because the SRO must determine the event and evaluate procedural action.

NUREG-1021, Revision 9 190 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 2 WA # G2.2.28 Importance Rating 3.5 Knowledge of new and spent fuel movement procedures Proposed Question: SRO 96 The Unit is in Mode 6. Fuel movement is in progress.

Which ONE of the following describes the person accountable to ensure overall adherence to all Technical Specifications related to Refueling?

A. Shift Manager B. Outage Manager C. Refueling Coordinator D. Refueling SRO Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. Responsible for work related outage activities, but may not be licensed.

C. Incorrect. Acts as go between for vendor and facility for refueling operations.

D. Incorrect. Responsible for verifying compliance prior to initiation, and ensure compliance for what indications and parameters are available in the control room, but does not carry overall responsibilty.

Technical Reference(s): 1/2 RP-1.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: (As available)

Question Source: Bank #

NUREG-1021, Revision 9 191 BVPS Unit 2

~~~~~ ~~~~ ~ ~ ~

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 2 and item 7 because the SRO must understand responsibilities of Refueling personnel and TS requirements.

NUREG-1021, Revision 9 192 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 2 WA # G2.2.22 Importance Rating 4.1 Knowledge of limiting conditions for operations and safety limits Proposed Question: SRO 97 During hydrostatic testing of the RCS in Mode 5, RCS pressure is increased to 2770 psig.

Which ONE of the following describes the MAXIMUM time allowed in accordance with Technical Specifications to reduce pressure below the Safety Limit?

A. 5 minutes B. 15 minutes C. 30 minutes D. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. Corresponds to time allotted to notify local authorities.

C. Incorrect. Time frame is not relevant, used for symmetry.

D. Incorrect. Corresponds to time allotted to notify the NRC.

Technical Reference(s): Tech Spec 2.1.2 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

Learning Objective: (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

NUREG-1021, Revision 9 193 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 2 because the SRO must evaluate an action requirement when a safety limit has been violated.

NUREG-1021, Revision 9 194 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 3 KIA # G2.3 9 Importance Rating 3.4 Knowledge of the process for performing a containment purge Proposed Question: SRO 98 The Unit is in Mode 5. Containment purge through the SLCRS unfiltered flow path is being initiated.

[2HVR*MOD23A], CNMT Purge Discharge lsol Damper, [2HVR*MOD21, 221, Containment Purge Exhaust Motor Operated Dampers, and [2HVR*MOD25A], CNMT Purge Supply Damper are in their correct positions.

Which ONE of the following describes the correct sequence for completing the Containment purge lineup in accordance with 20M-44C.4.A, Containment Air Purge And Exhaust System Startup?

A. Place the NORMAUPURGE control switch for containment purge air supply to PURGE.

Start 2HVS-FN2636, Leak Collection Normal Exhaust Fan and throttle 2HVR*MOD23B to obtain the desired flow rate required by the RWDA permit.

B. Start 2HVS-FN263B, Leak Collection Normal Exhaust Fan. Place the NORMAUPURGE control switch for containment purge air supply to purge and throttle 2HVR*MOD236 to obtain the desired flow rate required by the RWDA permit.

C. Throttle 2HVR*MOD23B to obtain the setpoint required by the RWDA permit. Place the NORMAUPURGE control switch for containment purge air supply to PURGE. Start 2HVS-FN263B, Leak Collection Normal Exhaust Fan.

D. Place the NORMAUPURGE control switch for containment purge air supply to PURGE.

Throttle 2HVR*MOD23B to obtain the setpoint required by the RWDA permit. Start 2HVS-FN263B, Leak Collection Normal Exhaust Fan.

Proposed Answer: A Explanation (Optional):

NUREG-1021, Revision 9 195 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet A. Correct.

.. B. Incorrect. Place switch in PURGE first.

C. Incorrect. No setpoint, actual flow rate is obtained. Also, out of order sequence.

D. Incorrect. No setpoint, actual flow rate is obtained. Also, out of order sequence.

Technical Reference(s): 20M-44C.4.A (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-44C.1 Objective 1 (As available)

Question Source: Bank #

Modified Bank # X (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 4 because the SRO must know the proper procedure to line up containment systems related to radioactive release.

NUREG-1021, Revision 9 196 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Quest ion Worksheet L. Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 4 WA # G2.4.35 Importance Rating 3.5 Knowledge of local auxiliary operator tasks during emergency operations including system geography and system implications Proposed Question: SRO 99 Given the following conditions:

You are the Shift Manager.

The Control Room is being evacuated due to a fire.

The affected fire area is CB-1, Cable Spreading Area.

You are assigning responsibilities.

0 The Outside Tour Operator is available to perform 20M-56C.4.E, Nuclear Operator #2 Which ONE of the following actions will the Outside Tour Operator perform?

A Go to the Alternate Shutdown Panel and initiate equipment transfer to LOCAL.

B Manual feed SGs using the turbine driven AFW pump locally.

C. Align charging pump control for manual local operation.

D. Align cooling and auxiliary support systems for RCS cooldown operations.

Proposed Answer: D Explanation (Optional):

A. Incorrect. Unit Supervisor will go to the ASP.

B. incorrect. This is performed from the ASP.

C. Incorrect. This is performed from the ASP.

D. Correct.

Technical Ref erence(s): 20M-56C.4.E (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 2SQS-56C.1 Objective 2 (As available)

NUREG-1021, Revision 9 197 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

-- Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 x Comments:

10CFR55.43(b) item 5 because the SRO must direct the actions of Operators during an emergency requiring control room evacuation.

NUREG-1021, Revision 9 198 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 4 WA # G2.4.4 Importance Rating 4.3 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnarrnal operating procedures Proposed Question: SRO 100 Given the following conditions:

The Unit is operating at 100% power.

EDG 2-2 is out of service and is expected to return to service in two (2) hours.

A loss of offsite power occurs.

The reactor is tripped and the crew enters E-0, Reactor Trip Or Safety Injection.

SI is NOT actuated.

The crew made a transition to FR-H.1, Loss Of Secondary Heat Sink based on a CSFST RED Path.

-*- Subsequently, EDG 2-1 output breaker trips on a bus fault.

Which ONE of the following actions will be taken?

A. Immediately transition to ECA-0.0, Loss Of All 4KV Emergency Power.

6 . Restore feed FR-H.1, and then return to E-0 to restore EDG 2-1.

C . Remain in FR-H.l until directed to return to procedure in effect, and then transition to ECA-0.0.

D. Remain in FR-H.l unless a higher priority RED condition is observed. When directed to return to procedure in effect, return to E-0. Restore EDG 2-1 or 2-2 in ES-0.1, Reactor Trip Response.

NUREG-1021, Revision 9 199 BVPS Unit 2

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. No AC power is available, therefore transition to ECA-0.0 is required.

C. Incorrect. Transition to ECA-0.0 immediately, even if a RED condition exists.

D. Incorrect. This would be correct if only one EDG was tripped.

Technical Reference(s): ECA-0.0, EOP User's Guide (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQS-53.1 Objective 1 (As available)

Question Source: Bank # X Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 55.43 x Comments:

Robinson 2002 NRC Exam 10CFR55.43(b) item 5 because the SRO must assess facility conditions and determine the appropriate procedural action during a loss of all 4KV AC power.

NUREG-1021, Revision 9 200 BVPS Unit 2

ML051030205

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