ML051240138

Final - RO & SRO Written (Folder 3)

ML051240138
Person / Time
Site:	Beaver Valley
Issue date:	01/15/2005
From:	Hynes C FirstEnergy Nuclear Operating Co
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
Download: ML051240138 (201)

Text

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. Minimizes acceleration on pump start to minimize the effects of core lift when the first RCP is started during an RCS heatup from Cold Shutdown.

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. Core lift is a concern during Cold Shutdown pump starts, but is minimized by starting RCPs in opposite loops.

Technical Reference(s): 1SQS-6.3, 1OM-1. l B (Attach if not previously provided)

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

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning 0bjective: 1SQS-15.1 Objective 2 (As available)

Question Source: Bank #

Modified Bank # X (Note changes or attach parent)

New Question History:

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 1

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:

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

0 [RC-P-1A], 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 1A level is.. .

A. Lower than 1 B and 1C SG due to SG shrink when the RCP tripped.

B. Higher than 1 B and 1C SG due to less heat removal from 1 A SG.

C. Higher than 1 B and 1 C SG due to SG swell when the RCP tripped.

D. Lower than 1 B and 1C SG due to the rise in Tcold on the idle loop.

Proposed Answer: B Explanation (Optional):

A. Incorrect. Effects of shrink 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 Reference(s): T&AA Simulator (Attach if not previously provided)

NUREG-1021, Revision 9 3 BVPS Unit 1

ES-401 Sample Written Examination form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS 6.3, Obj 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 Comments:

NUREG-1021, Revision 9 4 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline 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: Boratioddilution batch control Proposed Question: Common 3 Given the following:

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

Annunciator [A4-511 Loop TAVG High is in alarm.

You are directed to adjust RCS temperature using the Boration/Dilution controls. Determine the mode of makeup control required and the expected corresponding valve lineup.

A. Borate:

FCV-1CH-l13A, Boric Acid Flow Control Valve - OPEN FCV-1CH-l14A, Primary Water Flow Control Valve - CLOSED FCV-1CH-l13B, Makeup Stop Valve To Charging Pump Suction - OPEN FCV-1CH-1148, Makeup Stop Valve To VCT - CLOSED B. Borate:

FCV-1CH-l13A, Boric Acid Flow Control Valve - OPEN FCV-1CH-l14A, Primary Water Flow Control Valve - CLOSED FCV-1CH-1138, Makeup Stop Valve To Charging Pump Suction - CLOSED FCV-1CH-1148, Makeup Stop Valve To VCT - OPEN C. Dilute:

FCV-1CH-l13A, Boric Acid Flow Control Valve - OPEN FCV-1CH-l14A, Primary Water Flow Control Valve - OPEN FCV-1CH-1138, Makeup Stop Valve To Charging Pump Suction - OPEN FCV-1CH-l14B, Makeup Stop Valve To VCT - CLOSED D. Dilute:

FCV-1CH-l13A, Boric Acid Flow Control Valve - CLOSED FCV-1CH-l14A, Primary Water Flow Control Valve - OPEN FCV-1CH-1138, Makeup Stop Valve To Charging Pump Suction - CLOSED FCV-1CH-l14B, Makeup Stop Valve To VCT - OPEN NUREG-1021, Revision 9 5 BVPS Unit 1

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

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

6. Incorrect. Although boration is required, FCV-1138 and FCV-114B are listed in the incorrect position.

C. Incorrect. Dilution is not required, and FCV-114A is in the incorrect position.

D. Incorrect. Dilution is not required, and each valve is in the opposite of its correct position Technical Reference(s): 1OM-7.4.L (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-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:

NUREG-1021, Revision 9 6 BVPS Unit 1

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 RHR Train B.

[CC-P-1A], Component Cooling Water Pump is running.

[CC-P-1B], Component Cooling Water Pump is racked out.

0 [CC-P-1C], Component Cooling Water Pump is in STANDBY connected tothe 1DF bus.

The following annunciator is received in the Control Room:

[A6-35], PRI COMP COOL PUMP DISCH PRESS LOW The crew determines that the cause is a high CCR system demand.

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

A. [CC-P-1A] bright white indication. [CC-P-1C] red indication.

B. [CC-P-1A] red indication. [CC-P-1C] bright white indication.

C. [CC-P-1A] bright white indication. [CC-P-1C] bright white indication.

D. [CC-P-1A] red indication. [CC-P-1C] red indication.

Proposed Answer: D Explanation (Optional):

NUREG-1021, Revision 9 7 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet A. Incorrect. Bright white would indicate a pump trip. Indications in root of question do not provide for a trip, rather, just a low pressure.

B. Incorrect. Bright white would indicate a pump trip. Indications in root of question do not provide for a trip, rather, just a low pressure.

C. Incorrect. Bright white would indicate a pump trip. Indications in root of question do not provide for a trip, rather, just a low pressure.

D. Correct. Both pumps run; CC-P-1C remains running when connected.

Technical Reference(s): 1SQS-15.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-15.1 Objective 21 (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 1

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 Unit is in Mode 4, cooling down for refueling.

0 RHR Pump A and heat exchanger are in service.

0 The auto setpoint on [MOV-RH-6051, 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.

8. 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. Reason is correct.

Technical Reference(@: 1SQS-10.1 (Attach if not previously provided)

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

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 1SQS-10.1 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 Comments:

NUREG-1021, Revision 9 10 BVPS Unit 1

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 malfunctionsor operations on the ECCS; and (b) based on those predictions,use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Conditions requiringactuation of ECCS Proposed Question: Common 6 Given the following conditions:

A reactor trip has occurred.

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

The following conditions develop:

0 RCS pressure is 1950 psig and slowly lowering.

0 CH-P-lA, Charging Pump is RUNNING.

0 CH-P-1B, Charging Pump is in STANDBY.

0 Charging flow is offscale HIGH.

0 Letdown is isolated.

0 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.

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

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

Proposed Answer: B Explanation (Optional):

NUREG-1021, Revision 9 11 BVPS Unit 1

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. Would 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 action is incorrect.

Technical Reference(@: ES-0.1 Left Hand Page (Attach if not previously provided)

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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination OutIine Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 007 A4.01 Importance Rating 2.7 Ability to manually operate and/or 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.

The PORV has reseated.

Which ONE of the following describes the operation of [MOV-1RC-5161, PRT Spray Valve, and

[TV-1RC-5191, PRT Primary Water Supply 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 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: C Explanation (Optional):

A. Incorrect. Both valves are manual.

B. Incorrect. MOV-516 will already be open. Would be correct for BVPS-2.

C. Correct. MOV-516 is open in NSA.

D. Incorrect. Opposite action for the valves.

Technical Reference@): 1OM-6.4.AAC (Attach if not previously provided)

NUREG-1021, Revision 9 13 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-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 1

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 P ility to a) predic 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: HighAow 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 [A6-371, PRI Comp Cool Water Surge Tank Level HIGH-LOW

[A4-711, Radiation monitoring HIGH 0 [A4-721, Radiation monitoring HIGH-HIGH CCR 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. Close Chilled Water System inlet and outlet isolation valves to determine if the leak is in the Chilled Water System.

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

D. Close TV-1CH-200AJB, & 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 required. CCP surge tank level is not offscale.

B. Incorrect. Chilled Water System is unrelated to CCR 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-1.15.1 (Attach if not previously provided)

NUREG-1021, Revision 9 15 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-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 X 55.43 Comments:

NUREG-1021, Revision 9 16 BVPS Unit 1

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 Question: Common 9 Given the following conditions:

0 A Unit heatup is in progress.

0 RCS pressure is 335 psig with [PCV-1CH-1451, Letdown Backpressure Control Valve in AUTO.

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

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 Pressurizer?

A. Less than 15 minutes B. 15 - 30 minutes C. 45 to 60 minutes D. 75 to 90 minutes Proposed Answer: C Explanation (Optional):

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

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

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

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

NUREG-1021, Revision 9 17 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 1OM-6.4.AR (Attach if not previously provided)

Steam Tables Proposed references to be provided to applicants during examination: Steam Tables Learning Objective: 1SQS-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 1

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:

The Unit was operating at 68% power.

An automatic reactor trip occurred.

The cause of the trip was low RCS flow in Loop 1A.

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 1A high pressure side flow input failed high.

B. The Loop 1 A high pressure side flow input failed low.

C. One Loop 1A low pressure side flow input failed high.

D. One Loop 1Alow 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 only causes 1 out of 3 low flow trips. 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): OM Figure 6-1 (Attach if not previously provided)

NUREG-1021, Revision 9 19 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning 0bjective: 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 2002 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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 013 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:

The Unit was operating at 100% power.

A PRZR PORV failed open.

The reactor has tripped on low PRZR pressure.

PRZR pressure stabilizes at 1700 psig.

Containment pressure is 2 psig.

Plant status is as follows:

All control rods are fully inserted.

Status Panel 62-4C light S Inj Act Sig is NOT LIT.

Normally running charging pump is in service.

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

CIA is NOT actuated.

CIB is NOT actuated.

Main steam lines are NOT isolated.

Feedwater Isolation is NOT actuated.

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

Manually initiate both trains of only ...

A. Safety Injection.

B. Safety Injection and Main Steam Line Isolation.

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

D. Safety Injection, CIB, and CIA.

NUREG-1021, Revision 9 21 BVPS Unit 1

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, SI 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. MSLl is not actuated on low PRZR pressure.

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

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

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

Att l - K 1OM-1.28 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 2002 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 1

~ ~~~

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@)and/or interlock(s) which provide for the following: Cooling of containment penetrations Proposed Question: Common 12 Which ONE of the following describes the operation of the Containment Penetration Cooling System?

Inner and outer cooling coils are supplied by.. .

A. Chilled water. Coils are isolated on CIA.

B. Chilled water. Coils are isolated on CIB.

C. Component cooling water. Coils are isolated on CIA.

D. Component cooling water. Coils are isolated on CIB.

Proposed Answer: D Explanation (Optional):

A. Incorrect. Chilled water cools other coils, but not penetration coolers.

B. Incorrect. Not cooled by chilled water. Isolates on CIB.

C. Incorrect. Isolated on CIB.

D. Correct.

Technical Reference(s): 1SQS-15.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-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 1

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 24 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examinat ion OutIine 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:

The reactor has tripped.

0 Safety Injection actuates on low PRZR pressure.

0 All equipment has started and is operating as designed.

0 RCS pressure is 340 psig and lowering.

0 CTMT pressure is 18 psig and rising.

Prior to the event, [ l VS-F-1A and 1B], Containment Air Recirculation Fans were running.

[ l VS-F-1C], Containment Air Recirculation Fan was in standby aligned to 480V Bus 1P.

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. 1VS-F-1A and 1B, Containment Air Recirculation Fans must be manually started. 1VS-F-1C is tripped and cannot be started.

D. 1VS-F-1A, 1B and 1C, Containment Air Recirculation Fans must be manually started.

Proposed Answer: B Explanation (Optional):

NUREG-1021, Revision 9 25 BVPS Unit 1

A. Incorrect. Fans trip on a CIB due to a loss of the stub bus.

B. Correct.

C. Incorrect. All fans trip. None will be manually started until after the stub bus is re-energized.

D. Incorrect. All fans trip, and cannot be manually started until after the stub bus is re-energized.

Technical Reference(s): 1SQS-44.C.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-44.C.1 Objective 13 (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 1

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:

0 A LOCA has occurred.

0 The crew is performing actions of E-1, Loss Of Reactor Or Secondary Coolant.

SI and CIA are reset.

0 The crew is evaluating whether Containment Spray should be stopped.

0 Containment pressure is (-) 3 psig.

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

A. STOP ONE train of quench spray. When containment pressure reaches 8.9 psia, STOP ONE train of recirculation spray.

B. Leave BOTH trains of quench spray running. Throttle River Water flow from the recirculation spray heat exchangers to maintain CNMT pressure > 8.9 psia.

C. Leave BOTH trains of quench spray running until containment pressure is reduced to 8.9 psia.

D. STOP quench spray chemical injection pumps. Leave quench spray pumps running until containment pressure reaches 8.9 psia.

Proposed Answer: B Explanation (Optional):

A. Incorrect. In E-1, both trains of quench spray are stopped when pressure is (-) 2 psig.

8. Correct. Applies Steps 1O.a - d, leaving quench spray running and Steps 1O.f - h to maintain containment pressure between (-) 2 psig and 8.9 psia. (SGs are not faulted.)

C. Incorrect. Quench spray and recirculation spray are stopped at this pressure.

D. Incorrect. The first step in stopping quench spray is to stop the injection pumps, but for this step, quench spray pumps are not stopped.

NUREG-1021, Revision 9 27 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet 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 1

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 3.6 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:

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

0 The reactor is critical at 1 x 10"amps on the Intermediate Range Nl's.

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 Explanation (Optional):

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

B. 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): G FE - Reactor Operational (Attach if not previously provided)

Physics NUREG-1021, Revision 9 29 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-21.1 Objective 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:

NUREG-1021, Revision 9 30 BVPS Unit 1

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

The Unit is at 100% power.

The following annunciators are in alarm:

0 [A7-451, Steam Generator 1A Level Deviation From Setpoint 0 [A7-481, Loop 1 Steam Flow Greater Than Feedwater Flow The BOP determines that [FCV-1FW-4781, SG 1A Feed Regulating Valve is opening.

Which ONE of the following describes the event taking place?

A. A controlling feedwater flow transmitter has failed high.

B. 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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 1OM-24.4.IF (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-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 1

Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 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 ascension from 0% to 100°/o power?

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

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: D 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): 1SQS-24.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

Learning Objective: 1SQS-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 1

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:

Recent Plant modification NUREG-1021, Revision 9 34 BVPS Unit 1

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 provide a direct automatic trip of [ l FW-P-1A], Main Feedwater Pump?

A. 2 out of 3 Lo-Lo Level in any SG

6. Reactor Trip coincident with Low Tavg C. 2 out of 3 Hi-Hi Level (P-14) in any SG D. MOV-1FW-l50A, Main FW 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 MFP trip.

C. Correct.

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

Technical Reference(s): 1OM-24.1.D (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-24.1 Objective 13 (As available)

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

New Question History: Last NRC Exam 2002 NUREG-1021, Revision 9 35 BVPS Unit 1

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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 1

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 and/or cause-effect relationships between the AFW and the following systems: Emergency water source Proposed Question: Common 19 Which ONE of the following describes the suction source for the Auxiliary Feedwater Pumps?

A. Normal suction aligned to PPDWST. Suction can be aligned to 1WT-TK-26, Demineralized Water Tank if the PPDWST is unavailable.

B. Normal suction aligned to 1WT-TK-26, Demineralized Water Tank. Suction can be aligned to the PPDWST if the Demineralized Water Tank is unavailable.

C. Normal suction aligned to the PPDWST. Individual pump suction lines may be cross-connected.

D. Normal suction aligned to 1WT-TK-26, Demineralized Water Tank. Individual pump suction lines may be cross-connected.

Proposed Answer: C Explanation (Optional):

A. Incorrect. TK-26 is used to fill the PPDWST.

B. Incorrect. Pumps are not aligned to TK-26.

C. Correct. Pump suctions can be aligned to make all pumps available in case of a suction line break.

D. Incorrect. Pumps are not aligned to TK-26.

Technical Reference(s): 1SQS-24.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-24.1 Objective 2 (As available)

Question Source: Bank #

NUREG-1021, Revision 9 37 BVPS Unit 1

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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination 0ut1ine 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 M , including: RCS cooldown during AFW operations Proposed Question: Common 20 The plant is in Mode 3 following a reactor trip. A plant cooldown of 5O0F/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 decreased density of the SG water as it cools.

B. AFW flow requirements are constant as long as the cooldown rate remains constant even when RHR is placed in service.

C. Less AFW flow is required to maintain SG level because heat input to the SG's decreases 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, not decrease.

B. Incorrect. When RHR is placed in service, the steaming rate is reduced if the cooldown rate is held constant.

C. Correct. Decay heat rate drops as time progresses.

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 Objective 5 (As available)

NUREG-1021, Revision 9 39 BVPS Unit 1

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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 KIA # 062 K2.01 Importance Rating 3.3 Knowledge of bus power supplies to the following: Major System Loads Proposed Question: Common 21 Given the following conditions:

0 The plant is at 90% power, with all systems in NSA.

An electrical fault causes an overcurrent trip and lockout of the 4KV Bus Feeder Breakers supplied by D USST.

Which ONE of the following describes the Reactor Coolant Pumps that are running 10 seconds after this event takes place?

A. 1A and 1C B. 1B and 1C C. 1A and 1B D. All RCPs running Proposed Answer: C Explanation (Optional):

A. Incorrect. 1C will have no power.

B. Incorrect. 1C will have no power.

C. Correct. D USST lockout will prevent B SSST from energizing 4KV Bus 1C.

D. Incorrect. USSTs are in service > 65% power. Could be correct if SSSTs are in service supplying the busses.

Technical Reference(s): 1SQS-6.3 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

NUREG-1021, Revision 9 41 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning 0bjective: 1SQS-6.3 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 Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 42 BVPS Unit 1

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 Knowledge 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 cannot start automatically or locally, and therefore cannot generate electricity.

Proposed Answer: D Explanation (Optional):

A. Incorrect. Cannot generate power if no DC available for field flash.

B. Incorrect. Auto start circuitry is disabled.

C. Incorrect. Auto start circuitry is disabled.

D. Correct. All EDG control circuits are DC powered (auto and local). Even if start solenoid was manually overridden (no procedural requirements) it would not start because there would be no fuel priming pump running (DC powered).

Technical Reference(s): 1SQS-36.2 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

Learning Objective: 1SQS-36.2 Objective 3 (As available)

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

New NUREG-1021. Revision 9 43 BVPS Unit 1

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 44 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 064 K4.02 Importance Rating 3.9 Knowledge of EDlG 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 occurred.

0 While performing actions of E-0, the RO manually initiated a safety injection.

Approximately 5 minutes later, No. 1 EDG tripped.

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

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

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

B. 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 EDG is carrying the bus.

Technical Reference(s): 1SQS-36.2 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning 0bjective: 1SQS-36.2 Objective 13 (As available)

NUREG-1021, Revision 9 45 BVPS Unit 1

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 1

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:

0 The Unit is at 100% power.

0 1OST-36.2, Diesel Generator No. 2 Monthly Test is in progress.

0 No. 2 EDG is paralleled to the grid, carrying approximately 50% load.

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

Which ONE of the following describes the response of No. 2 EDG?

A. KW output rises.

B. 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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-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 1

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 the cooling tower blowdown, when the following annunciator alarms:

[A4-701, Radiation Monitor Power Supply Failure The BOP determines that [RM-1LW-1041, Liquid Waste Effluent Monitor is failed downscale.

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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 RM-1LW-104 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 an ongoing release.

C. Incorrect. Action is correct, but RM-104 does not have to be operable if compensatory measures are taken.

D. Correct.

NUREG-1021, Revision 9 49 BVPS Unit 1

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: 1SQS-17.1 Objective 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 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 1

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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 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:

[WR-P-lA], RPRW Pump is in standby.

[WR-P-1B], RPRW Pump is racked out.

[WR-P-1C], RPRW Pump is running in place of WR-P-1B.

The Control Room is being evacuated. Control for all three (3) river water pumps is shifted to the Emergency Shutdown Panel with all control switches in AUTO.

Subsequently, a loss offsite power occurs.

Which ONE of the following describes the river water pumps that will be in operation when the EDGs have completed their loading sequence?

A. WR-P-1A ONLY B. WR-P-1C ONLY C. WR-P-1A and WR-P-1C ONLY D. NO river water pumps will be running.

Proposed Answer: C Explanation (Optional):

A. Incorrect. The swing pump, 1C will also start if racked onto the 1DF bus.

B. Incorrect. Both 1A and 1C pumps will start.

C. Correct.

D. Incorrect. Pumps that are in AUTO will receive a start signal.

Technical Reference(s): 1SQS-30.2 (Attach if not previously provided)

NUREG-1021, Revision 9 51 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-30.2 Objective 14 (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 Bank - Not previous NRC. Modified distractors NUREG-1021, Revision 9 52 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 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 With the unit in Mode 3, assuming NO operator actions, which of the following describes the effect of a loss of station instrument air on Volume Control Tank (VCT) level?

A. VCT level decreases due to maximum charging and letdown isolating.

6. VCT level decreases due to maximum charging and letdown being diverted to the degassifiers.

C. VCT level increases due to minimum charging and the letdown pressure control valve failing open.

D. VCT level increases due to minimum charging and the letdown orifice isolation valves failing open.

Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. No divert on loss of air, just valve closure.

C. Incorrect. Charging is at maximum, letdown backpressure valve fails open, but letdown isolation valves close.

D. Incorrect. Opposite of actual effect.

Technical Reference(s): AOP-1.34.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-34.1 Objective 11 (As available)

NUREG-1021, Revision 9 53 BVPS Unit 1

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:

Harris 2004 NRC Exam Question 69 NUREG-1021, Revision 9 54 BVPS Unit 1

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 Given the following:

The plant was at 100% power.

0 A steam break occurred downstream of the Main Steam Isolation Valves.

0 A reactor trip and safety injection occurred from Train A ONLY.

Which one of the following correctly describes the status of the CNMT penetration lines for the Phase A (CIA) and Phase B (CIB) isolation valves before any operator action(s)?

A. One valve in each Phase A line is closed; one valve in each Phase B line is closed.

B. One valve in each Phase A line is closed; all Phase B valves do not change position.

C. All Phase A valves are closed; all Phase B valves are closed.

D. All Phase A valves are closed; all Phase B valves do not change position.

Proposed Answer: B Explanation (Optional):

A. Containment pressure (Phase B) is not rising for this event.

B. One valve in each Phase A line is closed; all Phase B valves are open.

C. Each train controls one Phase A valve and containment pressure is not rising.

D. Each train controls one Phase A valve and containment pressure is not rising.

NUREG-1021, Revision 9 55 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 1SQS-11.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-11.1 Objective 18 (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: There are some Phase B valves that are NSA closed.

NUREG-1021, Revision 9 56 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline 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 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 B. 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)

NUREG-1021, Revision 9 57 BVPS Unit 1

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-1M Bank Reference ID 1586 NUREG-1021, Revision 9 58 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 WA # 002 K4.05 Importance Rating 3.8 Knowledge 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 Temperature Monitoring and Containment Dew Point Monitor B. Containment Sump Monitor and Containment Temperature Monitoring C. Containment Particulate Activity Radiation Monitor and Containment Sump Monitor D. Containment Dew Point Monitor and Containment Gaseous Activity Radiation Monitor Proposed Answer: C Explanation (Optional):

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

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

C. Correct.

D. Incorrect. Containment temperature and dewpoint will indicate leakage, but are 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: N/A (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 1

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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 x Comments:

NUREG-1021, Revision 9 60 BVPS Unit 1

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

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

0 The controlling PRZR level transmitter [LT-1RC-4591 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 the plant is REDUCED to 10% power?

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 1

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

A. Incorrect for reason indicated in answer.

B. 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% when actual will start to decrease). LT-460 will show the actual PRZR level which will decrease to 14%, letdown will isolate and the heaters will cut off.

C. Incorrect for reason indicated in answer.

D. Incorrect for reason indicated in answer.

Technical Reference(s1: 1SQS-7.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-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 1

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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 # 041 A1.O1 Importance Rating 2.9 Ability to predict andor monitor changes in parameters (to prevent exceeding design limits) associated with 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 the crew entered FR-C.l, Response To Inadequate Core Cooling.

Given the following:

The Unit Supervisor has directed the depressurization of all intact SGs to 250 psig using the condenser steam dump valves.

All MSIVs are open and the condenser is available.

[AM-1MS-464B1, 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 NOT been placed in the BLOCK position.

As the SG depressurization progresses, the steam flow automatically stops.

Which ONE of the following caused the steam flow to stop?

A. SG pressure has reached 250 psig, or Main Steamline Isolation occurred due to exceeding the high steam pressure rate setpoint.

B. Steam header pressure has dropped below the setpoint on AM-1MS-464B, or Tavg is below 541O F and no action has been taken to defeat the Tavg Interlock.

C. Tavg is below 541OF and no action has been taken to defeat the Tavg Interlock, or Main Steamline Isolation occurred due to exceeding the low steam pressure rate sensitive setpoint.

D. Main Steamline Isolation due to exceeding the high steam pressure rate setpoint, or steam header pressure has dropped below the setpoint on AM-1MS-464B.

Proposed Answer: C NUREG-1021, Revision 9 63 BVPS Unit 1

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

A. Incorrect. No automatic actions halt steam dump at 250 psig.

B. Incorrect. AM-1MS-464B is in manual. Pressure setpoint has no effect.

C. Correct. As Tavg approaches 541O F , the Tavg Interlock must be defeated by holding both steam dump control bypass interlock selector switches to the DEFEAT TAVG NTLK position until the status light, 2/3 Lo-Lo Tavg is LIT. This action was not performed.

Also, the Main Steamline Isolation due to exceeding the high steam pressure rate setpoint is active and could have resulted in MSIV isolation, if the rate of depressurization was excessive.

D. Incorrect. AM-1MS-464B is in manual. Pressure setpoint has no effect.

Technical Reference(s): FR-C.l, Step 16 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-21.1 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 Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

2002 NRC exam NUREG-1021, Revision 9 64 BVPS Unit 1

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 off load to SFP.

6. Correct.

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

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

Technical Reference(s): 1SQS-20.1 (Attach if not previously provided)

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

NUREG-1021. Revision 9 65 BVPS Unit 1

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 1

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 of 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:

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

0 Fuel movement is in progress.

0 Containment Purge System is operating.

[RM-1VS-l04A], 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.

6. Refueling may continue as long as RM-219A and B, Containment Area Monitors are operabIe.

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

D. Refueling may continue as long as RM-1VS-1048, Containment Purge And Exhaust Radiation Monitor remains operable.

Proposed Answer: A Explanation (Optional):

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

B. Incorrect. No requirement for RM219NB to replace RM104A, 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): 1OM-44C.1 (Attach if not previously provided)

NUREG-1021, Revision 9 67 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-44C.1, Objective 17 (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 68 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 KIA # 045 K1.18 Importance Rating 3.6 Knowledge of the physical connections and/or cause-effect relationships between the MT/G system and the following systems: RPS Proposed Question: Common 35 Given the following conditions:

Reactor power is at approximately 106% and slowly rising on 3 channels.

The remaining power range channel is 104.5% and rising.

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 constant rate of 200% per minute until load is reduced to 20%,

with no further automatic action.

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

Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. There is no limit to 20% 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): 1SQS-35.3 (Attach if not previously provided)

NUREG-1021, Revision 9 69 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-35.3 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 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 1

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 conditions:

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

0 A batch discharge of the contents of [ l LW-TK-7A1, Steam Generator Drain Tank 7A is in progress.

0 [RM-1LW-1041, Liquid Waste Effluent Monitor has generated a HIGH-HIGH radiation signal.

How will this affect the Liquid Waste Disposal System?

A. TV-LW-105, Liquid Waste Effluent Trip Valve receives a close signal and FCV-LW-104-1, Liquid Waste Effluent Low Range Flow Control Valve remains in its current position.

B. The running steam generator drain tank pump will stop and FCV-LW-104-1, Liquid Waste Effluent Low Range Flow Control Valve closes.

C. The running steam generator drain tank pump will stop and FCV-LW-104-2, Liquid Waste Effluent High Range Flow Control Valve closes.

D. FCV-LW-104-1 and FCV-LW-104-2, Liquid Waste Effluent High and Low Range Flow Control Valves and TV-LW-105, Liquid Waste Effluent Trip Valve receive a signal to close.

Proposed Answer: D Explanation (Optional):

A. Incorrect. FCV-LW-104-1 receives a closed signal on high radiation.

B. Incorrect. The radiation signal does not generate a signal to stop the SG drain tank pump.

C. Incorrect. The radiation signal does not generate a signal to stop the SG drain tank pump.

D. Correct. All three valves receive a close signal on high radiation.

Technical Reference(s): 1OM-17.1.D (Attach if not previously provided)

NUREG-1021, Revision 9 71 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet 1OM-17 Figure 17-22 Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-17.1 Objective 5 (As available)

Question Source: Bank # 1SQS-17-05-01 Modified Bank # (Note changes or attach parent)

New

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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 72 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 KIA # 071 A1.06 Importance Rating 2.5 Ability to predict and/or monitor changes in parameters(t0 prevent exceeding design limits) associated with Waste Gas Disposal System operating the controls including:Ventilation system Proposed Question: Common 37 A gaseous waste release is in progress in accordance with 1OM-l9.4.E, Decay Tank Discharge.

0 [lGW-F-lA], GW Disposal Blower is operating.

0 [TV-1GW-1031, GW Decay Tank Disch to CTWR Valve is open.

0 [TV-1GW-103~21,GW Decay Tank Bleed Valve is open.

0 [ l GW-D-1-1A], GW Disposal Damper associated with the A GW Disposal Blower

[ l GW-F-1A] is open.

0 The operator adjusts FCV-1GW-105, Decay Tank Bleed Control Valve, from 75% to 100% while the discharge is in progress.

0 [RM-1GW-10881, GW Disposal Blower Discharge Radiation Monitor alarms on High-High gaseous activity.

Which ONE of the following automatic actions will occur to limit radioactive release to the Unit 1 Process Vent?

A. Only 1GW-F-1A, GW Disposal Blower trips.

B. Only 1GW-D-1-1A, GW Disposal Damper shuts.

C. Valve TV-1GW-103 and valve TV-1GW-103A2 shut.

D. Blower 1GW-F-1A trips and damper 1GW-D-1-1A shuts.

Proposed Answer: C Explanation (Optional):

A. Incorrect. GW Disposal Blower unaffected by RM-1GW-108B.

B. Incorrect. GW Disposal Damper unaffected by RM-1GW-108B.

C. Correct. [TV-1GW-1031and [TV-1GW-103A21automatically shut on High-High Radiation as detected by RM-1GW-108B or RM-1GW-108A.

D. Incorrect. Blower and damper both unaffected NUREG-1021. Revision 9 73 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 1OM-19.4.E (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

Learning Objective: 1SQS-19.1 Objective 3 (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:

Editorially Modified from BVPS-1 2002 NRC Exam Question 20 NUREG-1021, Revision 9 74 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination OutIine Cross-reference: Level RO SRO Tier # 2 Group # 2 WA # 075 K1.02 Importance Rating 2.9 Knowledge of the physical connections and/or cause-effect relationships between the circulating water system and the following systems: Liquid radwaste discharge Proposed Question: Common 38 A Liquid Waste Disposal System Precaution & Limitation 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 & Limitation?

A. The discharge permit for discharging the contents of a single liquid waste tank is based upon a dilution rate which includes 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 1 cooling tower blowdown.

Proposed Answer: A Explanation (Optional):

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): 1OM-17 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE NUREG-1021, Revision 9 75 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 1SQS-17.1 Objective 7 (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:

NUREG-1021, Revision 9 76 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA # 007 EA1.09 Importance Rating 3.2 Ability to operate and monitor the following as they apF., 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 The crew is performing actions of ES-0.1, Reactor Trip Response.

0 Steam Dumps have been closed.

0 Safety Injection is NOT actuated OR required.

0 PRZR level has recovered to 22%.

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. Place PCV-1CH-145, Letdown Backpressure Regulator in MANUAL.

B. OPEN TV-1CH-204, Letdown Containment Isolation Valve.

C. Ensure PCV-1CH-145 Letdown Backpressure Regulator is CLOSED.

D. Ensure W - 1CH-204, Letdown Containment Isolation Valve is CLOSED.

Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. If no CIA, valve should already be open.

C. Incorrect. As Found may be closed, but valve is required to be open.

D. Incorrect. Valve should remain open without a CIA.

Technical Reference(s): ES-0.1 Step 7.C RNO (Attach if not previously provided)

NUREG-1021, Revision 9 77 BVPS Unit 1

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-1021, Revision 9 78 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 KIA # 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 plant operating at 100% power, the reactor trips on low PRZR pressure.

[PI-1RC-4721, 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 281OF. PRZR safety relief line temperatures slowly rising.

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

C. PORV relief line temperature stabilized at 281O 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 1

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

A. Correct. 281O 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 PORVs.

C. incorrect. 281OF 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 PORVs.

E. 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 PORVs.

Technical Reference(s): Steam Tables (Attach if not previously provided) 1OM-6.4 Annunciator Response Proposed references to be provided to applicants during examination: Steam Tables Learning Objective: 1SQS-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 NUREG-1021, Revision 9 80 BVPS Unit 1

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% power, NSA with the exception of [PT-4471, Turbine First Stage Pressure Transmitter, which is in the process of being removed from service due to erratic operation. The condenser steam dumps are in the Tavg mode. A loss of reactor plant component cooling water then results in a manual reactor trip. Ten minutes after the trip, the following conditions exist during the performance of ES-0.1, Reactor Trip Response:

SG Pressure 1A 1000 psig and stable 1B 1005 psig and stable 1c 995 psig and stable All RCPs are OFF.

RCS pressure is 2230 psig and stable.

Thot is approximately 575°F in all three (3) loops and slowly lowering.

Core Exit TCs indicate approximately 580°F and stable.

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

Reactor Trip Breaker A failed to open.

Which ONE of the following describes 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 dump valves are maintaining heat removal.

D. Natural circulation does NOT exist. Heat removal will be established by opening the SG atmospheric steam dump valves.

NUREG-1021, Revision 9 81 BVPS Unit 1

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

A. Incorrect. Natural circulation does not exist because Tcold temperatures are too high and stable.

B. Correct. 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 ADVs are open for heat removal.

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

Technical Reference(s): EOP Attachment 2-G (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:

BVPS-1 2002 Audit Examination As written, the condenser steam dumps should have been open attempting to maintain Tavg at 547F. Since Tavg is at 565F and SG pressures are stable, one would assume that the condenser steam dumps are not available/working. Therefore, the preferred method of heat removal would be the ADVs. To make the chosen answer correct (condenser steam dumps preferred), amplifying information was added to the stem to prevent the condenser steam dumps from operating in the Tavg mode, which would explain why they were not working post trip.

NUREG-1021, Revision 9 82 BVPS Unit 1

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

The crew has isolated letdown flow while attempting to restore charging flow.

0 The RO reports that PRZR level is lowering at a rate of 1% every five (5) minutes.

0 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> C. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> D. 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 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. Pressurizer level program will be approximately 55% of scale between 22% and 54%. Pressurizer heater cutout is at 14%. Therefore, with level lowering at 1% every 5 minutes, it will take 128 minutes to reach 14%.

D. Incorrect. Value is close and symmetrical.

Technical Reference(s): 1SQS-6.4 (Attach if not previously provided)

NUREG-1021, Revision 9 83 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQSD-6.4 Objectives 16/19 (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 1

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 Abiltty to operate and / o r monitor the following as they apply to 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.

0 A loss of RHR cooling occurred due to a loss of CCR.

0 The RO reports that all CCR pumps are tripped.

0 The crew is performing actions of AOP-1.10.1, Residual Heat Removal System Loss.

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

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

B. RHR temperature must be logged to determine time available to vent RHR pumps.

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

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

Proposed Answer: C Explanation (Optional):

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

B. Incorrect. Core exit temperatures, not RHR temperature is logged.

C. Correct.

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

Technical Reference(s): AOP 1.10.1, Step 9 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE NUREG-1021, Revision 9 85 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 1SQS-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 1

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:

o [A4-111, Pressurizer Control Press LOW The RO determines that [PT-1RC-4451, Pressurizer Pressure Transmitter is failing LOW.

Assuming NO operator action is taken, which ONE of the following describes the expected indication on PT-1RC-444 PRZR Control Pressure?

A. Rises until PCV-1RC-455CI PRZR PORV Relief Valve OPENS.

B. Rises until PCV-1RC-455D 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 PT-445 fails low, the only indication will be the alarm. Heaters and spray valves are controlled from the master controller.

B. Incorrect. These 2 valves are controlled by PT-445, 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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 1OM-6.4.IF (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination 0utline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA # 029 EK3.11 Importance Rating 4.2 Knowledge of the reasons for the following responses as the apply to the A W S : Initiating emergency boration Proposed Question: Common 45 Which ONE of the following describes the reason that emergency boration is initiated in FR-S.1, Response To Nuclear 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.l.

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

Technical Reference(s): FR-S.l 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-1021, Revision 9 89 BVPS Unit 1

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 1

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 apF., to a SGTR: S/G atmospheric relief valve and secondary PORV controllers and indicators Proposed Question: Common 46 Given the following:

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

A loss of offsite power occurs.

All equipment functions as required.

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

A. Fully open the intact SG atmospheric dump valves to establish maximum cooldown rate.

B. Gradually open the intact SG atmospheric dump valves to establish a cooldown rate below Technical Specification limits.

C. Gradually open the condenser steam dumps in Pressure Control mode to establish a cooldown rate below Technical Specification limits.

D. Fully open the condenser steam dumps in Pressure Control mode to establish maximum cooldown 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)

NUREG-1021, Revision 9 91 BVPS Unit 1

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 # 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:

NUREG-1021, Revision 9 92 BVPS Unit 1

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

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

The crew is evaluating if SI flow should be reduced.

The following conditions exist:

o RCS temperature is 460°F and slowly dropping.

o RCS pressure is 1650 psig, and rising slowly.

o Containment pressure is 23 psig.

o SG B and C NR levels are 15% and rising.

o A M I flow is 375 gpm.

o PRZR level is 20%.

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

A. immediately.

B. 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 1

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: NONE 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 1

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 feedwater loss conditions Proposed Question: Common 48 Given the following:

The crew is responding to an event and is currently in FR-H.1, Response To Loss Of Secondary Heat Sink.

Attempts to restore feedwater flow have failed.

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

The other two PORVs 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 PORVs 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.

Proposed Answer: C Explanation (Optional):

NUREG-1021, Revision 9 95 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet 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): 1 OM-538.4.FR-H.1, Step 19 (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: 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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 KIA # 055 EKl.02

~~

Importance Rating 4.1 Knowledge of the operational implicationsof the following concepts as they apply to the Station Blackout : Natural circulation cooling Proposed Question: Common 49 In ECA-0.0, Loss Of All Emergency 4KV Power during the rapid depressurization of intact SGs to 250 psig, an overshoot occurs and all SGs are reduced to 160 psig before the depressurization is stabilized.

Which ONE of the following conditions may result from this overshoot in SG depressurization?

A. The Integrity CSFST may be challenged.

B. The Subcriticality CSFST may be challenged requiring entry into a Functional Restoration Procedure.

C. Natural circulation may be impeded by accumulator Nitrogen injection.

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

Proposed Answer: C Explanation (Optional):

A. Incorrect. Tsat for 160 psig is above the temperature limit for a Red or Orange path on the Integrity status tree.

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

C. Correct. NPinjection to the RCS would interrupt natural circulation flow.

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

Technical Reference(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 1

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 1

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 I or monitor the following as they apply to the Loss of Offsite Power: Auxiliaqdemergency feedwater pump (motor driven)

Proposed Question: Common 50 Given the following conditions:

0 A reactor trip occurred from 100% power.

0 No. 2 EDG is 00s.

0 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. 1-FW-P-3A and 1FW-P3B are both RUNNING.

B. 1 FW-P-3A and 1FW-P-3B are both STOPPED.

C. 1 FW-P-3A is RUNNING. 1FW-P-3B is STOPPED.

D. 1FW-P-3B is RUNNING. 1FW-P-3A is STOPPED.

Proposed Answer: C Explanation (Optional):

A. Incorrect. 1 FW-P-3B can not run without power.

B. Incorrect. 1 FW-P-P3A will be running.

C. Correct.

D. Incorrect. Opposite of actual pump operation.

Technical Reference(s): 1SQS-24.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE NUREG-1021, Revision 9 99 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 1SQS-24.1 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 X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 100 BVPS Unit 1

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 Bus: ESF system panel alarm annunciators and channel status indicators Proposed Question: Common 51 A loss of 120VAC Vital Bus No. 1 has occurred.

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

A. HHCP PRESS CH TRIP/DEFEAT B. PRZR PRESS LOW SI ST.PT.

C. PZR HI LEVEL RX TRIP D. LOOP S.G. HI-HI LEVEL 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-1.38.1 A Step 7 (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 1

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: 55.41 X 55.43 Comments:

NUREG-1021, Revision 9 102 BVPS Unit 1

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 / or monitor the following as they apply to the Loss of DC Power: Cross-tie of the affected dc bus with the alternate supply Proposed Question: Common 52 How is it ensured that loads powered off of two different 125VDC buses (swing) loads do not inadvertently cross-tie the affected DC buses?

A. A mechanical interlock prevents simultaneous ctosure 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 1

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:

NUREG-1021, Revision 9 104 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA # 062 G2.4.4 Importance Rating 4.0 Emergency ProceduredPlan:Ability to recognize abnormal indications for system operating parameters which are entry level conditions for abnormal and emergency operating procedures.

Proposed Question: Common 53 Given the following conditions:

The Unit is at 35% power with all systems in NSA performing a normal plant shutdown due to the inoperability of the No. 1 EDG, which is currently on clearance.

When transferring the electrical busses to the offsite source, an electrical fault occurred resulting in the following breakers tripping open on overcurrent:

o Main generator exciter breaker o Both main generator output breakers o 4KV Bus A feeder breakers from both the USST and SSST Which ONE of the following procedures IMMEDIATE operator actions should be performed first?

A. AOP-1.1.3, RCCA Control Bank Inappropriate Continuous Movement B. AOP-1.26.1 Turbine And Generator Trip C. AOP-1.36.2, Loss Of 4KV Emergency Bus D. E-0, Reactor Trip Or Safety Injection Proposed Answer: D Explanation (Optional):

A. Incorrect. Reactor trip will occur on loss of the A RCP; this would be correct if just a load rejection occurred.

B. Incorrect. Reactor trip will occur on loss of the A RCP; this would be correct if just a turbine trip occurred.

C. Incorrect. E-0 immediate actions performed first, then these immediate actions are performed.

D. Correct.

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

NUREG-1021, Revision 9 105 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning 0bjective: (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 9 106 BVPS Unit 1

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) Facility 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:

All SG pressures are stable at 1000 psig.

All SG NR levels are approximately 25%.

AFW is supplying the SGs.

RCS pressure is approximately 1000 psig.

RCS temperature is 545°F.

[RM-1VS-1lo], CTMT/SLCRS Exhaust Monitor SPING 4 is in alarm.

[RM-1VS-1121, CTMT/SLCRS Exhaust Monitor SA 9/10 is in alarm.

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-1.1, 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 1

Proposed Answer: D Explanation (Optional):

A. Incorrect. CNMT parameters are normal.

B. Incorrect. RCS pressure 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: NONE 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 1

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, abnormal 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, Reactor Trip Or Safety Injection.

0 A M I flow CANNOT be established.

0 All SG NR levels are offscale low.

0 The crew has entered FR-H.1, 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 required actions?

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

B. 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 is NOT required.

NUREG-1021, Revision 9 109 BVPS Unit 1

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 SGs 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. SGs 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)

Document 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:

Robinson 2002 Audit Exam NUREG-1021, Revision 9 110 BVPS Unit 1

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 indicatingsignals, 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-1.1, Loss Of Emergency Coolant Recirculation.

Two (2) CharginUHHSI pumps and two (2) LHSl pumps are running.

RWST level is approximately 1.5 feet and continues to lower.

Which ONE of the following describes the action required in accordance with ECA-1. l ?

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

B. STOP ONLY ONE (1) HHSl and ONLY 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 back flow from the RWST to the 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 1

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 35 (Attach if not previously provided)

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 9 112 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 WA # 001 AA1.01 Importance Rating 3.5 Ability to operate and I or monitor the following as they apply to the Continuous Rod Withdrawal: Bank select switch Proposed Question: Common 57 The following conditions exist:

The Unit is operating at 80%, steady-state power.

0 The Rod Control Selector Switch is in Automatic.

Control Bank D starts to step in continuously.

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 position.

C. Place the Rod Control Mode Selector Switch in either Shutdown Bank position.

D. Manually trip the reactor and actuate safety injection.

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-1.1.3 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning 0bjective: (As available)

NUREG-1021, Revision 9 113 BVPS Unit 1

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:

NUREG-1021, Revision 9 114 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 KIA # 003 AK2.05 Importance Rating 2.5 Knowledge of the interrelationsbetween 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, Group 2, and Control 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 Explanation (Optional):

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

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

C. Correct. Will cause a loss of power to stationary gripper coils, resulting in a rod drop.

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

Tee, mica1 Reference@): 3SQS-1.3 (Attach if not previously probIUzd)

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 1

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 1

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

0 RCS pressure - 2000 psig and lowering 0 Reactor power - 80%

0 SG pressures - 800 psig 0 PRZR level - 42% and lowering The Unit is then tripped and plant parameters following the trip are:

0 RCS pressure - 1600 psig and lowering 0 Reactor power - 0%

0 SG pressures - 1000 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.

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

C. approximately 70% 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 1

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 1

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 Ability to determine and interpret the following as they apply to the Area Radiation Monitoring(ARM) System Alarms: ARM panel displays Proposed Question: Common 60 For a source check on a radiation monitor to be considered satisfactory, the radiation monitor meter must deflect enough to ...

A. indicate above background ONLY B. illuminate the HIGH alarm status light ONLY.

C. illuminate the HIGH and HIGH-HIGH status lights ONLY.

D. illuminate the HIGH and HIGH-HIGH status lights, and annunciators [A4-711, Radiation Monitor High and [A4-721, Radiation Monitor High-High.

Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. Does not have to deflect to alarm point. Calibration does this.

C. Incorrect. Does not have to deflect to alarm point. Calibration does this.

D. Incorrect. This indication should exist if distractor C was the criteria for a source check.

Technical Reference(s): 1SQS-43.1 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning 0bjective: 1SQS-43.1 Objective 7 (As available)

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

New NUREG-1021, Revision 9 119 BVPS Unit 1

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:

Editorially enhanced NUREG-1021, Revision 9 120 BVPS Unit 1

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

The crew has completed the SI termination actions of ES-1.l, SI Termination.

0 The following status light on Panel 62 is illuminated:

0 AUTO SAF INJ. BLOCK Which ONE of the following actions is required to clear the status light in accordance with ES-1.1, SI Termination?

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 the trip pushbutton until the light clears.

Proposed Answer: C Explanation (Optional):

A. Incorrect. This action is what causes the status light to actuate.

B. Incorrect. Resetting SI will bring in the light; the other actions will have no effect.

C. Correct. P4 resets the auto SI circuitry, which will be actuated by cycling the RTB's.

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 1

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

NUREG-1021, Revision 9 122 BVPS Unit 1

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 of 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 the initial depressurization of 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 LHSI flow.

C. To provide driving head for a controlled two phase natural circulation cooldown of the RCS.

D. To minimize the possibility of lifting a secondary safety valve in the event of a SG tube rupture.

Proposed Answer: B Explanation (Optional):

A. Incorrect. If in FR-(2.1, SGs are already a marginal heat sink.

B. Correct.

C. Incorrect. Two phase natural circulation is unlikely 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.l 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)

NUREG-1021, Revision 9 123 BVPS Unit 1

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 Bank ID 3777 NUREG-1021, Revision 9 124 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 WA # 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 the actions contained in FR-P.1, 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.1 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 Explanation (Optional):

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.l Background (Attach if not previously provided)

NUREG-1021, Revision 9 125 BVPS Unit 1

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 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:

Salem 2001 NRC exam Western Tech Bank Archive NUREG-1021, Revision 9 126 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 KIA # E13 EK2.1 Importance Rating 3.0 Knowledge of the interrelationsbetween 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 A pressure indicates 1150 psig.

SG B and C pressures indicate 1010 psig.

SG A NR level is 65%.

Instrument air header pressure has been lost.

Which ONE of the following actions is available to mitigate the SG overpressure condition?

A. Initiate SG blowdown flow.

B. Open condenser steam dump valves.

C. Go to FR-H.3, Response To SG High Level to reduce pressure by reducing SG level.

D. Locally open the residual heat release valve to reduce SG pressure.

Proposed Answer: D Explanation (Optional):

A. Incorrect. Do not initiate ARN 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 1

~~~~~ ~ ~ ~~~

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 # 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:

NUREG-1021, Revision 9 128 BVPS Unit 1

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 has been evacuated due to a fire. The crew is performing the actions of 1OM-56C.4.B, Alternate Safe Shutdown Outside Control Room using Train B equipment.

SG NR levels are 10% and trending down in all three (3) SGs.

Which ONE of the following describes the preferred method of maintaining secondary heat sink?

A. Maintain SG NR levels 25 - 50% by manually increasing turbine driven AFW pump speed OR by manually throttling HCV-1MS-104, Residual Heat Release Valve.

B. Maintain SG WR levels 25-50% by manually increasing turbine driven AFW pump speed OR manually throttling PCV-1MS-101A, B, C, SG Atmospheric Dump Valves.

C. Maintain SG NR levels greater than 50% by operating the dedicated ARN pump OR by manually throttling HCV-1MS-104, Residual Heat Release Valve.

D. Maintain SG WR levels greater than 50% by operating the dedicated A N V pump OR manually throttling PCV-1MS-101A, B, C, SG Atmospheric Dump Valves.

Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. Atmospheric dump valves are the alternate method of controlling steam release.

C. Incorrect. Dedicated AFW pump is only used for situations where inventory is limited.

D. Incorrect. Dedicated AFW pump is only used for situations where inventory is limited. SG ADVs are alternate method of steam removal.

Technical Reference(s): 1OM-56.4.B (Attach if not previously provided)

NUREG-1021, Revision 9 129 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-56C.1 Objective 4 (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 x Comments:

BVPS-1 2002 NRC S77 NUREG-1021, Revision 9 130 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 1 WA # G2.1.1 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:

0 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on December 24,2004 BOP 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on November 23,2004 BOP 0 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on November 22,2004 BOP 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on September 19,2004 RO 0 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on September 18,2004 RO Which ONE of the following describes the status of your license in accordance with 1/2-ADM-1351, Licensed 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-hour shifts in the RO position.

C. Your license is inactive. You must reactivate your license by standing five (5) 8-hour shifts under instruction in the RO position and one 8-hour shift in any one of the Non-licensed tour positions.

D. Your license is inactive. You must reactivate your license by standing five ( 5 ) 8-hour shifts under instruction as either the RO or BOP.

NUREG-1021, Revision 9 131 BVPS Unit 1

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. Non-licensed tour position not required.

D. Correct. Last calendar quarter did not stand 5 shifts.

Technical Reference(s): 1/2 ADM-1351 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE 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 Comments:

Robinson 2004 Audit exam -Western Tech Bank Archive NUREG-1021, Revision 9 132 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination 0utIine 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 Question: Common 67 Given the following conditions:

0 The Unit has been at 100% power for 3 weeks. All systems are in NSA.

RCS boron concentration is 1000 ppm.

A controlled power reduction to 50% is to be performed.

Using the references provided and maintaining control rods at their current position, assuming no change in xenon concentration, which ONE of the following describes the approximate amount of boric acid required to initially maneuver the plant to 50% power?

A. 700 - 800 gallons B. 850 - 950 gallons C. 1000 - 1100 gallons D. 1150 - 1250 gallons Proposed Answer: C Explanation (Optional):

A. Incorrect. Low enough to allow for minor interpretation differences on nomograph reading.

B. Incorrect. Used to provide consistent distractor and allows for minor interpretation differences.

C. Correct. Power defect is approximately 910 pcm (1880 - 970). A critical boron concentration of 1000 ppm indicates approximately 10,300 MWD/MTU. Differential Boron worth is approximately - 6.73 pcdppm. Therefore, 9101 - 6.73 = 152 ppm. Using boron addition nomograph results in approximately 1050 gallons of boric acid or less.

D. Incorrect. High enough to provide consistent distractor and allows for minor interpretation differences.

Technical Reference(s): Curve Book CB-13, CB-21, (Attach if not previously provided)

NUREG-1021, Revision 9 133 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet CB-28, CB-31, CB-36 Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-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 9 134 BVPS Unit 1

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.

B. Inability to perform the OST as written.

C. Performing an OST that pre-establishes conditions for non-performance of steps.

D. Non-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 use of N/A.

B. 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-NOP-LP-2601 (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 1

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 2002 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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 2 KIA # 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 0bjective: 3SQS-1.1 Objective 16 (As available)

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

New Question History: Last NRC Exam 2002 NUREG-1021, Revision 9 137 BVPS Unit 1

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 x Comments:

NUREG-1021, Revision 9 138 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examinat ion OutIine 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 a responsibility of the Reactor Operator during refueling operations?

A. Monitor source range count rate during core reload, and remain cognizant of 1/M plot results.

B. Maintain continuous communication between the control room and refueling deck.

C. Maintain a 1/M plot during core 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. Performed by Refueling Group.

C. Incorrect. Reactivity monitoring function performed by Refueling Group.

D. Incorrect. Status updates performed by 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 NUREG-1021. Revision 9 139 BVPS Unit 1

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:

Prairie Island Western Tech Bank Question ID 44573 NUREG-1021, Revision 9 140 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 KIA # 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:

You are required to make an entry to a Locked High Radiation Area.

Your year-to-date exposure is 2.6 Rem Total Effective Dose Equivalent (TEDE).

The job is planned to take 20 minutes to complete, with 5 minutes transit time each way.

Transit path radiation levels are 400 mFUhr.

0 Work area radiation levels are 1200 mFUhr.

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 and have received authorization to exceed the exposure Admin Control Level.

B. You may not perform this task because you will exceed the BVPS Admin Guide for TEDE.

C. You may perform this task provided you are signed onto a High Radiation Area RWP with no other restrictions other than that listed on the RWP.

D. You may not perform the task because your current year to date exposure is already within 80% of the BVPS Admin Guide for TEDE.

Proposed Answer: A Explanation (Optional):

A. Correct. Admin Control Level for BVPS is 2000 mRem.

B. incorrect. BVPS Admin Guide for TEDE is 4 Rem. Actual exposure results in 3067 mRem.

C. Incorrect. Authorization to exceed the Admin Control Level is required.

D. incorrect. 80% of BVPS TEDE would be 3.2 Rem.

NUREG-1021, Revision 9 141 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): 1/2 ADM-1601 (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 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 x Comments: The guidelines for a PSE are extremely vague. They are simply: authorized only in exceptional situations when alternatives to avoid a higher exposure are unavoidable or impracticable. They also limit exposure to the 10CFR20 limit (5000 mR). This does not mean that they cannot be used to receive the dose indicated in this question (-447mr).

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 Ability to control radiation releases.

Proposed Question: Common 72 Given the following conditions:

0 A rapid load reduction from 100% power to 65% power was performed approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago.

0 [RM-1CH-101B], Reactor Coolant Letdown Low Range Monitor is in alarm.

0 [RM-1CH-101A], Reactor Coolant Letdown High Range Monitor has just reached its Alarm setpoint.

0 Actions of 1OM-43.4.AACI Radiation Monitoring HIGH-HIGH have been completed.

0 Chemistry confirms RCS activity exceeds TS 3.4.8 limits.

The Unit Supervisor directs a plant shutdown to be performed.

Which ONE of the following actions is subsequently performed to limit the release of radioactivity?

A. MSIV's are closed.

6. SG atmospheric dump valve setpoints are raised.

C. RCS is cooled down below 5OO8F.

D. Maximum condensate polishers are placed in service.

NUREG-1021, Revision 9 143 BVPS Unit 1

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

A. Incorrect. Closing MSIVs would contribute to a radiation release through SG ADVs and safety valves if cooldown and depressurization was 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 does not exist at BV-1, although it would help clean up the secondary plant.

Technical Reference(s): TS 3.4.8 (Attach if not previously provided) 1OM-43.4.AAC Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-43.1 Objectives 9 and 10 (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-1 2002 NRC Western Tech Bank 46428 NUREG-1021, Revision 9 144 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 4 WA # G2.4.29 Importance Rating 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. Unusual Event 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 1

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 1

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 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.

B. 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 that it precedes.

D. Incorrect. Opposite of actual application.

Technical Reference(s): EOP Users 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 1

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 1

~~ ~

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 actions and directives affect 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.

RWST level is 47 feet and trending down at 2 inches every 10 minutes.

All AFW pumps are running with 400 gpm flow.

All RCPs are STOPPED.

Based upon the conditions above, which ONE of the following procedures will the crew transition to, which will then provide guidance to start a reactor coolant pump, if it is desired?

A. ES-1.3, Transfer to Cold Leg Recirculation B. ES-0.1, Reactor Trip Response 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. ES-1.3 is not appropriate for these conditions.

B. Incorrect. SI is actuated.

C. Incorrect. E-1 does not start an RCP.

D. Correct. ES-1.2 is performed which will start RCPs during the RCS cooldown.

NUREG-1021, Revision 9 149 BVPS Unit 1

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 1

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 Heat 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 5.

RHR Pump B is in service.

The following annunciator is received:

o [A1-1261, Residual Heat Removal System Disch Flow Low

[RM-1VS-104A1, Containment Purge Exhaust Monitor, is in alarm Which ONE of the following describes the plant condition and action required under these conditions?

A. An RHR leak exists in Containment. Enter AOP-1.6.5, Shutdown LOCA.

B. An RHR leak exists in the Auxiliary Building. Enter AOP-1.6.7, Excessive Primary Plant Leakage.

C. An RHR leak exists in Containment. Enter AOP-1.10.1, Residual Heat Removal System Loss.

D. An RHR leak exists in the Auxiliary Building. Enter AOP-1.6.5, Shutdown LOCA.

Proposed Answer: C Explanation (Optional):

A. Incorrect. AOP-1.6.5 applies in Modes 3 and 4.

B. Incorrect. AOP-1.6.7 applies in Modes 1 and 2, and with purge exhaust in alarm, the leak is in containment.

C. Correct.

D. Incorrect. AOP-1.6.5 is for Modes 3 and 4, and leak is in containment.

Technical Reference(s): AOP-1.10.1 (Attach if not previously provided)

NUREG-1021, Revision 9 151 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-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 correct procedure and action.

NUREG-1021, Revision 9 152 BVPS Unit 1

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

A manual reactor trip is attempted by the RO.

Reactor Trip Breaker A has lost position indication.

0 Reactor Trip Breaker B indicates closed.

Reactor power indicates 6% 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 NOT tripped. Emergency boration is required per ES-0.1, Reactor Trip Response.

C. The reactor is NOT tripped. Transition to FR-S.l, 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.l, not ES-0.1.

C. Correct.

D. Incorrect. E-0 does not dispatch anyone to locally trip the reactor.

Technical Reference(s): E-0, FR-S.l (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE NUREG-1021, Revision 9 153 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 3SQSD-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 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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 WA # 038 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 78 With the plant in Mode 1, 2, or 3, Technical Specifications limits the RCS activity to 50.1 pCi/gm Dose Equivalent 1-131.

Which ONE of the following describes the basis for this limit?

A. In case of a steam break-induced steam generator tube leakage, ensures offsite dose does not exceed a small fraction of 10CFRl 00 guidelines.

B. In case of a LOCA, ensures offsite dose does not exceed a small fraction of 10CFR100 guidelines.

C. In case of a steam break-induced steam generator tube leakage, ensures offsite dose rates do not exceed1OCFR20 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.

D. Incorrect. LOCA is not the concern, and 10CFR20 limits are for normal operation.

Technical Reference(s): T.S. 3.4.8 Bases (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning 0bjective: 3SQSTS.3 Objective 5.8 (As available)

Question Source: Bank # X NUREG-1021, Revision 9 155 BVPS Unit 1

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 1

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

The Unit is in Mode 6.

Refueling is in progress, with an irradiated fuel assembly movement in progress in containment.

Train A is the Protected Train.

Train B 125V DC Bus 1-2 is out-of-service for battery replacement.

125VDC Bus 1-3 sustains a fault and is de-energized. The Refueling crew is ordered to complete the fuel assembly movement in progress and then suspend refueling operations.

Which ONE of the following describes the reason that Technical Specifications requires suspending the fuel movement?

A. The failure of DC Bus 1-3 also makes 120V AC distribution inoperable.

6. 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 offsite 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 1

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 0bjective: 3SQSTS.3 Objective 5.8 (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 Comments:

10CFR55.43(b) item 2 because the SRO must understand Technical Specification Bases.

NUREG-1021, Revision 9 158 BVPS Unit 1

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

[Al-401, CC WTR HT EXCH RIVER WTR PP DISCH LINE A PRESS LOW

[Al-591, INTAKE STRUCT RIVER WATER PP DISCH LINE PRESS LOW

[Al-821, RIVER WATER PP AUTO START-STOP Additionally, the operators note the following conditions:

[WR-P-lA], River Water Pump is tripped (previously running).

0 [WR-P-1B], River Water Pump remains in Standby.

Which ONE of the following actions is required to restore River Water System flow?

A. Start WR-P-1B, remove WR-P-1A from service, and place WR-P-IC on the 1AE Bus in accordance with the ARPs and the applicable section of 1OM-30.

B. Start WR-P-1B, remove WR-P-1A from service, and place WR-P-1C on the 1DF Bus in accordance with the ARPs and the applicable section of 1OM-30.

C. Start WR-P-6A or WR-P-6B, Turbine Plant River Water Pumps and place WR-P-1C on the 1AE Bus in accordance with AOP-1.30.2, River Water/Normal Intake Structure Loss.

D. Start WR-P-6A or WR-P-6B, Turbine Plant River Water Pumps and place WR-P-1C on the 1DF Bus in accordance with AOP-1.30.2, River Water/Normal Intake Structure Loss.

Proposed Answer: A Explanation (Optional):

NUREG-1021, Revision 9 159 BVPS Unit 1

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. 1DF bus already has a running RW pump.

C. Incorrect. Wrong action for the given failure, and wrong procedure usage.

D. Incorrect. Wrong action and wrong bus for the failure given, and wrong procedure usage.

Technical Reference(s): 1OM-30.4 AAC, AAF (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS -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 1

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 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 Question: 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 Explanation (Optional):

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@): 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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 3SQS-53.3Objective 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 1

~ _ _ ~ _ _

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 037 G2.4.30 Importance Rating 3.6 Emergency Procedures I Plan Knowledge of which events related to system operationdstatusshould be reported to outside agencies.

Proposed Question: SRO 82 Which ONE of the following events requires a 1 HOUR report to the NRC in accordance with 10CFR50.72?

A. Initiation of a plant shutdown in accordance with T.S. 3.0.3 B. Initiation of a Licensee Event Report (LER)

C. Confirmed violation of Fitness for Duty requirements D. Declaration of an Unusual Event Proposed Answer: D Explanation (Optional):

A. Incorrect. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B. Incorrect. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C. Incorrect. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> D. Correct.

Technical Reference(s): 10CFR50.72, BVBP-SITE-0016 (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 Question History: Last NRC Exam NUREG-1021, Revision 9 163 BVPS Unit 1

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 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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 WA # EO9 EA2.2 Importance Rating 3.8 Ability 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 facilitys license and amendments Proposed Question: SRO 83 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.

The crew has commenced RCS depressurization to 1950 psig.

The following conditions are indicated:

RCS pressure is 2030 psig and trending DOWN slowly.

0 RCS Tavg is 5479F and trending DOWN slowly.

PRZR level is 21% and trending DOWN slowly.

Which ONE of the following operator actions will be 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 Cooldown With Steam Void In Vessel (Without RVLIS).

Proposed Answer: A Explanation (Optional):

NUREG-1021, Revision 9 165 BVPS Unit 1

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 SI 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: 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 evaluate plant conditions and select the appropriate procedural action.

NUREG-1021, Revision 9 166 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 WA # 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 Given the following conditions:

A reactor trip and safety injection have occurred.

The crew was performing action contained in E-1, Loss Of Reactor Or Secondary Coolant.

The US was concerned about conflicting indications, and the crew entered ES-0.0, Rediagnosis.

The crew determines that there is an increasing trend on [RM-1MS-1011, FW-P-2 Monitor and [RM-1MS-1OOA], Steam Relief Monitor.

Which one of the following describes how the crew will transition to the correct procedure?

A. Go directly to the appropriate E-3 or ECA-3 series procedure.

B. Return to E-0 diagnostic steps to verify indications that will confirm the event in progress.

C. Return to E-1 step in effect and use the Symptomatic ResponsehJnexpectedConditions page to direct entry to E-3.

D. Direct Chemistry sample of steam generators to confirm radiation monitor readings prior to making a determination of appropriate procedure entry.

Proposed Answer: A Explanation (Optional):

A. Correct. ES-0.0 Step 3.

B. Incorrect. Once in ES-0.0, transition back to E-0 will not be made.

C. Incorrect. Once E-1 is exited, ES-0.0 will direct entry to the appropriate procedure.

NUREG-1021, Revision 9 167 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet D. Incorrect. Procedure is entered without confirmatory sample.

Technical Reference(s): ES-0.0, Step 3 (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: BVPS-1 2002 NRC Exam #55 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.

NUREG-1021, Revision 9 168 BVPS Unit 1

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 entry-level conditions for emergency and abnormal operating procedures.

Proposed Question: SRO 85 Given the following conditions:

A LOCA has occurred.

ECCS has NOT functioned as required.

All RCPs are TRIPPED.

CETs indicate 626°F.

RVLlS Full Range is 39%.

All SG pressures are approximately 1070 psig.

Total ARN flow is 350 gpm.

SG NR levels are 13%, 1 1Yo,and 17%, respectively.

Which ONE of the following procedures should the crew implement for these conditions?

A. FR-H.l, Response To Loss Of Secondary Heat Sink B. 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 Heat Sink does not exist.

C. Incorrect. Core Cooling CSF is in Orange Path condition, not a Red Path.

D. Correct. Core Cooling CSF is in Orange Path condition.

Technical Reference(@: CSF Status Trees (Attach if not previously provided)

NUREG-1021, Revision 9 169 BVPS Unit 1

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 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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group ## 1 KIA ## 003 G2.1.33 Importance Rating 4.0 Conduct of Operations: Ability to recognize indications for system operating parameters which are entty-level conditions for technical specifications.

Proposed Question: SRO 86 Given the following conditions:

0 The Unit is in Mode 3 during a plant heatup with all RCPs in operation.

RCP B has been stopped due to vibration concerns.

0 While investigating the high vibration on RCP B , the US determines that RCP C should also be stopped due to vibration concerns.

RCP A is unaffected.

Which ONE of the following actions is required?

A. Correct the cause of the high vibration on B and C RCPs or be in Cold Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

B. Correct the cause of the high vibration on at least ONE of the affected RCPs or be in Cold Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

C. Immediately suspend any operations involving a reduction in RCS boron concentration and initiate corrective action to restore at least ONE RCP to service.

D. Immediately de-energize control rod drive mechanisms or align the rod control system so it is incapable of control rod withdrawal.

Proposed Answer: D Explanation (Optional):

A. Incorrect. Action for Hot Shutdown with loop not operable.

B. Incorrect. Action for Hot Shutdown with loop not operable.

C. Incorrect. Action for all loops inoperable, or none in operation.

D. Correct.

Technical Reference(s): Tech Spec 3.4.1.2 (Attach if not previously provided)

NUREG-1021, Revision 9 171 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 3SQSTS.2 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 55.43 x Comments:

10CFR55.43(b) item 2 because the SRO must determine Technical Specification applicability for starting RCPs.

NUREG-1021. Revision 9 172 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 010 G2.2.22 Importance Rating 4.1 Equipment Control: Knowledge of limiting conditions for operations and safety limits.

Proposed Question: SRO 87 With the Unit in Mode 1, the relief capacity of pressurizer safety valve(s) is greater than the maximum surge rate resulting from a complete loss of load WITHOUT immediate reactor trip, assuming operation.

A. all no PORV or Steam Dump B. all PORV and Steam Dump C. each no PORV or Steam Dump D. each PORV and Steam Dump Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. No PORV or steam dump assumed.

C. Incorrect. All safety valves combined, not each.

D. Incorrect. All safety valves combined, not each, and no PORV or steam dump assumed.

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 Question History: Last NRC Exam NUREG-1021, Revision 9 173 BVPS Unit 1

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 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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 039 A2.05 Importance Rating 3.6 Ability to (a) predict the impacts of the following mal-functions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Increasing steam demand, its relationship to increases in reactor power Proposed Question: SRO a8 Given the following conditions:

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

0 The RO has recently performed a small dilution for RCS temperature control.

The following indications are available in the Control Room:

o Power Range Nls are increasing.

o Tavg is decreasing.

o Steam flow and feed flow are slightly elevated.

Reactor power is 101YOand 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.

B. 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).

B. 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.

NUREG-1021, Revision 9 175 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): Simulator (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 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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 078 A2.01 Importance Rating 2.9 Ability to (a) predict the impacts of the following malfunctions or operations on the IAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunctions Proposed Question: SRO 89 Given the following conditions:

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

0 [IA-1PI-1061, Instrument Air Pressure has been slowly decreasing and is reading 85 psig.

The crew enters AOP-1.34.1, Loss Of Station Instrument Air.

0 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-1.34.1, Loss Of Station Instrument Air?

A. Place the instrument air dryer bypass filters in service.

6. Place main 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.

6. Incorrect. Air pressure is 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-I .34.1 (Attach if not previously provided)

NUREG-1021, Revision 9 177 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQSD-53C.1 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 X Comprehension or Analysis 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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 WA # 103 G2.1.12 Importance Rating 4.0 Conduct of Operations: Ability to apply Technical Specifications for a system Proposed Question: SRO 90 While operating in Mode 4, which ONE of the following is required to be operable for each containment airlock?

A. Both doors B. Only the inner door C. Only the outer door D. Only one door, either the inner or outer door Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. Two doors are required.

C. Incorrect. Two doors are required.

D. Incorrect. Two doors are required.

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

Tech Spec 3.6.3 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 9 179 BVPS Unit 1

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:

BVPS-2 2002 NRC exam 10CFR55.43(b) item 2 because the SRO must know basis for equipment operability.

NUREG-1021, Revision 9 180 BVPS Unit 1

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 of Operations: Ability to explain and apply all system limits and precautions.

Proposed Question: SRO 91 The Unit is in Mode 1 at 89% power. Control Bank D Group 1 step counter position is 196 steps.

CERPl and primary coil voltages indicate the following:

Control Rod H02 at 194 steps.

Control Rod H14 at 205 steps.

Control Rod PO8 at 182 steps.

Control Rod BO8 at 180 steps.

Which ONE of the following describes the action(s) required by Technical Specifications and AOP-1.1.8, Rod Inoperability?

A. Immediately trip the reactor and initiate emergency boration of the RCS.

B. Reduce thermal power to less than 80% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and restore both control rods to within alignment within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

C. Restore both control rods to within alignment in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in Hot Standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

D. Verify shutdown margin is within the limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in Hot Standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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 misalignment of rods.

C. Incorrect. More than 1 rod is misaligned. No opportunity provided for restoration.

D. Correct.

NUREG-1021, Revision 9 181 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(s): AOP-1.1.8 (Attach if not previously provided)

Tech Spec 3.1.3.1 Proposed references to be provided to applicants during examination: NONE Learning Objective: (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 2 and item 5 because the SRO must choose the appropriate action for the plant condition in accordance with Technical Specifications.

BVPS-2 2002 NRC Exam NUREG-1021, Revision 9 182 BVPS Unit 1

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 Ability to (a) predict the impacts of the following malfunctions or operation on the SlGS system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Faulted or Ruptured SG Proposed Question: SRO 92 Given the following conditions:

0 A reactor trip and safety injection have occurred.

0 RCS pressure is 1600 psig and DECREASING.

0 PRZR level is offscale LOW.

0 Tavg is 5OOQFand DECREASING.

0 Containment pressure is 3 psig and INCREASING.

0 SG A pressure is 620 psig and DECREASING.

0 SG B and 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.l, 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.

B. 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 1

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 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 1

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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 # 056 G2.4.50 Importance Rating 3.3 Emergency ProceduresI Plan Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

Proposed Question: SRO 93 The Unit is at 72% power with all systems in NSA.

The following annunciators are in alarm:

0 [A7-11, Condensate Pump Auto Start-Stop 0 [A7-5], Condensate Pump Disch Press Low 0 [A7-61, Steam Generator Feed Pump Suction Pressure Low The BOP determines that [CN-P-1B], Condensate Pump has tripped. The control switch bright white indication is LIT.

Which ONE of the following describes the action required?

A. Verify the standby heater drain pump auto started and maintain current power level until Condensate Pump 1 B is returned to service.

B. Reset and attempt ONE (1) restart of Condensate Pump 1 B .

C. Reduce power to less than 65% in accordance with AOP-1.24.1, Loss Of Main Feedwater.

D. Reduce turbine load until Annunciator A7-6 is clear in accordance with AOP-1.24.1, Loss Of Main Feedwater.

Proposed Answer: D Explanation (Optional):

A. Incorrect. Reactor will trip if current power level is maintained.

B. Incorrect. Bright white indication would preclude restart of the pump.

C. Incorrect. Action is correct for a loss of a main feed pump.

D. Correct.

Technical Reference(s): AOP 1.24.1, 1OM-22A.4 AAC, (Attach if not previously provided)

AAD, AAE NUREG-1021, Revision 9 185 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Proposed references to be provided to applicants during examination: NONE Learning Objective: 1SQS-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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 1 KIA # G2.1.20 Importance Rating 4.2 Ability 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 l-K, Verification Of Automatic Actions.

While performing Attachment 1-K, 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 actions in Attachment l - K until directed to by E-1 B. Continue actions in Attachment 1-K, but do not perform actions of any other attachment until directed to by E-1.

C. Complete the actions required by Attachment 1-K prior to transitioning to E-1.

D. Transition to E-1 and continue actions as necessary in Attachment 1-K.

Proposed Answer: D Explanation (Optional):

A. Incorrect. Attachment 1-K 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 1-K 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 1

~~ ___

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 X Comprehension or Analysis 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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 1 WA # G2.1.14 Importance Rating 3.3 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 are indications 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 1

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 1

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 Given the following conditions:

0 The Unit is in Mode 6.

0 Core reload is being initiated in accordance with 1/2RP-3.24, Core Reload.

Prior to an assembly being placed on the manipulator crane, it is desired to reposition a fuel assembly loading guide (shoehorn).

0 A bridge and trolley interlock must be defeated to access and reposition the loading guide.

Which ONE of the following describes the requirement(s) that must be met in order to defeat interlocks required to reposition the loading guide?

A. Refueling SRO only must grant permission.

B. Shift Manager and Refueling SRO must grant permission.

C. The evolution must be governed by a written procedure and the Hoist interlock may NOT be bypassed.

D. The evolution must be governed by a written procedure and the Refueling SRO must grant permission.

Proposed Answer: A Explanation (Optional):

A. Correct.

8. Incorrect. Shift Manager permission not required.

C. Incorrect. Hoist interlock restriction does not exist, and a written procedure only required for defeating interlocks when not moving lights or positioning loading guides.

D. Incorrect. Written procedure not required if only positioning lights or loading guides.

NUREG-1021, Revision 9 191 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Technical Reference(@: 1/2 RP-3.24 (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 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 6 and item 7 because the SRO must understand responsibilities of Refueling personnel related to bypassing interlocks on Refueling Equipment NUREG-1021, Revision 9 192 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 2 KIA # 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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): T.S. 2.1.2 (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 9 193 BVPS Unit 1

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 1

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. Preparations are being made to enter containment.

Which ONE of the following describes the correct sequence for initiating a containment purge to the Ventilation Vent in accordance with 1OM-44.C.4?

A. Open the supply and exhaust dampers; start 1VS-F-5, CNMT Purge Exhaust Fan.

Ensure the NORMAUREFUELING control switch is in the NORMAL position. If desired, start 1VS-HV-5, CNMT Purge Vent Supply Fan.

B. Open the supply and exhaust dampers; start 1VS-F-5, CNMT Purge Exhaust Fan.

Ensure the NORMAUREFUELING control switch is in the REFUELING position. If desired, start 1VS-HV-5, CNMT Purge Vent Sup Fan.

C. Start 1VS-F-5, CNMT Purge Exhaust Fan. Ensure the supply and exhaust dampers open. Place the NORMAUREFUELING control switch in the NORMAL position and start 1VS-HV-5, CNMT Purge Vent Supply Fan.

D. Start 1VS-F-5, CNMT Purge Exhaust Fan. Ensure the supply and exhaust dampers open. Place the NORMAUREFUELING control switch in the REFUELING position and start 1VS-HV-5, CNMT Purge Vent Supply Fan.

Proposed Answer: A Explanation (Optional):

A. Correct.

B. Incorrect. Switch should be placed in the NORMAL position.

C. Incorrect. Wrong sequence, and dampers are manually aligned.

D. Incorrect. Wrong sequence, wrong switch position, and dampers are manually aligned.

Technical Reference(s): 1OM-44C.4.A (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE NUREG-1021, Revision 9 195 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 1SQS-44.C.1 Objective 1 (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 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 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 4 WA ## G2.4.35 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.

0 The Control Room is being evacuated due to a fire.

0 The affected fire area is CS-1, Cable Spreading Area.

0 The available train is Train B.

You are assigning responsibilities in the Brigade Room in accordance with 1OM-56C.4, Alternate Safe Shutdown from Outside the Control Room.

0 The PAB Tour Operator is available to perform the Nuclear Operator procedure.

Which ONE of the following actions will you direct the PAB Tour Operator to perform?

A. Go to the Remote Shutdown Panel and initiate equipment transfer to LOCAL.

B. Manually feed SGs using the turbine driven A M I pump locally.

C. Align charging pump control for manual local operation.

D. Align the available EDG and support systems for operation.

Proposed Answer: D Explanation (Optional):

A. Incorrect. Unit Supervisor goes to the Remote Shutdown Panel.

B. Incorrect. This is performed from the Remote Shutdown Panel.

C. Incorrect. This is performed from the Remote Shutdown Panel.

D. Correct.

Technical Reference(s): 1OM-56C.4.D (Attach if not previously provided)

Proposed references to be provided to applicants during examination: NONE NUREG-1021, Revision 9 197 BVPS Unit 1

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet Learning Objective: 1OM-56C.1 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 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 1

Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 4 KIA # G2.4.4 Importance Rating 4.3 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Proposed Question: SRO 100 Given the following conditions:

The Unit is operating at 100% power.

EDG No. 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 transitions to FR-H.1, Loss Of Secondary Heat Sink based on a CSFST RED Path condition.

Subsequently, EDG No. 1 output breaker trips on a fault.

Which ONE of the following actions will be taken?

A. Immediately transition to ECA-0.0, Loss Of All 4KV Emergency Power.

B. Restore feed flow in FR-H.1, and then return to E-0 to restore EDG No. 1.

C. Remain in FR-H.1 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 No. 1 or No. 2 in ES-0.1, Reactor Trip Response.

NUREG-1021, Revision 9 199 BVPS Unit 1

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 Users 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 1

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2004 SECTION 111, DIVISION 1 - NB (a)

/I6 in. (1.5 mm) min. x 45 deg chamfer /I6in, (1.5 mrn) min. x 45 deg chamfer i

f

\ \

[Note (2)l buildup added, when required, to meet reinforcement limitations (dl (e)

[Note (311 NOTES:

(1) If weld buildup is not used, r1 shall apply to the inside diameter of base material instead of the inside diameter of weld buildup.

(2) The 3/4 r,, min. dimension applies t o the fillet leg and the J-groove depth.

(3)Weld buildup, if used, shall be examined as required i n NB-5244.

FIG. NB-4244(dI-l PARTIAL PENETRATION NOZZLE AND BRANCH P I P I N G CONNECTIONS (For Definitions of Symbols and Other Related Requirements, see N B-3352.4(d).)

158