ML12194A410

Initial Exam 2012-301 Draft SRO Written Exam

ML12194A410
Person / Time
Site:	Harris
Issue date:	07/12/2012
From:	NRC/RGN-II
To:	Progress Energy Co
References
50-400/12-301
Download: ML12194A410 (69)

Text

QUESTIONS REPORT for 2012 NRC SRO REV3 45 DAY SUBMITTAL

76. 2012 NRC SRO 001 Given the following plant conditions:

- The plant is operating at 60% power

- The crew is performing AOP-018, Reactor Coolant Pump Abnormal Conditions, due to rising temperatures on RCP A

- The following conditions exist for RCP A Time Pump Radial Bearing Temp Motor Stator Winding Temp 0800 208°F 289°F 0805 218°F 297°F 0810 226°F 303°F 0815 232°F 308°F Which ONE of the following identifies (1) the FIRST limit to be exceeded, AND (2) actions required to be directed by the CRS to the OAC?

A (1) Motor Stator Winding temperature (2) Trip the Reactor, enter PATH-i, and trip RCP A.

B. (1) Motor Stator Winding temperature (2) Reduce power to less than the P-8 setpoint and trip RCP A, lAW AOP-018.

C. (1) Pump Radial Bearing temperature (2) Trip the Reactor, enter PATH-i, and trip RCP A.

D. (1) Pump Radial Bearing temperature (2) Reduce power to less than the P-8 setpoint and trip RCP A, lAW AOP-Oi 8.

Tuesday, March 20, 2012 3:08:19 PM

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL Plausibility and Answer Analysis Reason answer is correct: AOP-018 section 3.1 step 2 checks that all RCPs are within the limits of Attachment 1. The Stator Winding Temperture exceeds its trip limit of 300°F first at time 0810. Once the Attachment 1 limits are exceeded the RCP must be stopped and CRS must evaluated the status of Reactor Power and determine that a manual RPS Reactor Trip is required to preculde and Automatic RPS Reactor Trip once the RCP A is taken to stop.

A. Correct.

B. Incorrect. Plausible if the candidate fails to recognize AOP-018 directs Reactor Power to be checked above P-8 and stop the RCP if Reactor Power is currently below P-8 at the time of the check.

C. Incorrect. Plausible if the candidate fails to recognize pump radial bearing temperature is still less than the allowable temperature of 230°F, actions for this answer would be correct when the 230°F limit is exceeded D. Incorrect. Plausible if the candidate fails to recognize pump radial bearing temperature is still less than the allowable temperature of 230°F and AOP-018 directs Reactor Power to be checked above P-8 and stop the RCP if Reactor Power is currently below P-8 at the time of the check.

Tuesday, March 20, 2012 3:08:19 PM 2

QUESTIONS REPORT for 2012 NRC SRO REV345DAYSIJBMITTAL APE: 015/017 Reactor Coolant Pump (RCP) Malfunctions 015AA2.09 Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): When to secure RCPs on high stator temperatures (CFR 43.5 / 45.13)

Importance Rating: 3.4 3.5 Technical

Reference:

AOP-018, Section 3.1 Steps 2..8 and Attachment 1 RCP Trip limits step 3, Pages 5 and 27, Rev. 40 References to be provided: No Learning Objective: AOP-018, Reactor Coolant Pump Abnormal Conditions, AOP3-18 Obj. 3.a & 4 Question Origin: NEW Comments:

Tier/Group: T1G1 SRO Justification: Assessing plant conditions (Normal, abnormal, or emergency) and the prescribing a procedure or section of a procedure to mitigate, recover or with which to proceed.

MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: A A A A A A A A A A Items Not Scrambled Origin: NEW Cog Level: C/A Difficulty:

Reference:

Ref. Provided: Key Words:

K/A 1: 015 AA2.09 K/A 2:

Tuesday, March 20, 2012 3:08:19 PM 3

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL

77. 2012 NRC SRO 002 Given the following plant conditions:

- The plant is operating at 50% power.

- The crew entered AOP-01 8, RCP Malfunctions, and have determined that RCP B trip limits have been exceeded.

- A Reactor trip from the MCB is unsuccessful.

Which ONE of the completes the statements below?

lAW FRP-S.1, Response To Nuclear Power Generation/ATWS, continue operating ALL RCP5 until (1) then trip the RCP B. The basis for continued RCP operation is that it (2)

A. (1) a transition is made to PATH-i (2) provides RCS pressure control preventing an overpressure condition B. (1) a transition is made to PATH-i (2) could be beneficial by temporarily cooling the core under voided RCS conditions C. (1)poweris<5%

(2) provides RCS pressure control preventing an overpressure condition D (i) power is <5%

(2) could be beneficial by temporarily cooling the core under voided RCS conditions Tuesday, March 20, 2012 3:08:19 PM 4

QUESTIONS REPORT fQr 2012 NRC SRQ REV 345 DAY SUBMITTAL Plausibility and Answer Analysis Reason answer is correct: Caution prior to step 1 of FRP-S.1, Response to Nuclear power Generation/ATWS states: To maximize core cooling, RCPs should NOT be tripped with Reactor power GREATER THAN 5%. (Normal support conditions for running RCPs are NOT required for these circumstances. The RCP TRIP CRITERIA for small break LOCA conditions is NOT applicable to this procedure.) The WOG background document supplies the reason that during an ATWS, RCP operation could be beneficial by temporarily cooling the core under voided RCS conditions.

A Incorrect. Plausible as this would be correct if FRP-S. 1 were not in effect. Normal RCS pressure control is maintained using PRZ spray and RCP B provides more effective pressurre control when in operation.

B Incorrect. Plausible as this would be correct if FRP-S. I were not in effect. The reason for continued operation is correct for A TWS conditions.

C Incorrect. Plausible as this is correct for FRP-S. I conditions, but the reason for continued operation of the RCPs is listed for normal conditions vice A TWS conditions.

D Correct.

Tuesday, March 20, 2012 3:08:19 PM 5

QUESTIONS REPORT for 2012 NRC SRQ REV 345 QAY SUM1TTAL EPE : 029 Anticipated Transient Without Scram (ATWS) 029EG2.4.20 Knowledge of the operational implications of EOP warnings, cautions, and notes.

(CFR: 41.10 /43.5 /45.13)

Importance Rating: 3.8 4.3 Technical

Reference:

EOP-FRP-S.1 Caution Prior to Step 1, Page 3, Rev. 17, ERG-BKGRD-FR-S. I References to be provided: No Learning Objective: FRP-S, Subcriticality Status Tree, EOP3-15 Obj. 5.h Question Origin: New Comments: Added second part to question asking for basis Tier/Group: TIG1 SRO Justification: Assessing plant conditions (Normal, abnormal, or emergency) and the prescribing a procedure or section of a procedure to mitigate, recover or with which to proceed.

MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: D D D D D D D D D D Items Not Scrambled Origin: NEW Cog Level: C/A Difficulty:

Reference:

Ref. Provided: Key Words:

KJA 1: 029 EG2.4.20 KJA2:

Tuesday, March 20, 2012 3:08:19 PM 6

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL

78. 2012 NRC SRO 003 Given the following plant conditions:

- The plant is operating at 100% power

- CVPETS radiation monitor is in alarm

- PRZ level is lowering at the rate of 1.4%/minute

- CVCS conditions are:

- Charging flow is 137 gpm

- Letdown flow is 106 gpm

- RCP seal injection flows are:

A 9.1 gpm, B 9.7 gpm, and C 9.2 gpm

- RCP No.1 seal return flows are:

A 2.9 gpm, B 2.5 gpm, and C 3.6 gpm Which ONE of the following completes the statements below?

For the event described above, the magnitude of the leakage should be evaluated as a Steam Generator Tube (1)

The FSAR analysis for this event assumes the contaminated secondary fluid is released directly to the atmosphere due to failure of a SG (2) in the open position.

A. (1) leak (2) PORV B. (1) leak (2) Safety C (1) rupture (2) PORV D. (1) rupture (2) Safety Tuesday, March 20, 2012 3:08:19 PM 7

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL Plausibility and Answer Analysis Reason answer is correct: Per AOP-016 a leak is bounded by the ability to make up for RCS losses via the normal sources using the VCT. Leakage in excess of the VCT make rate of 50 to 120 gpm is classified as a rupture and require Safety injection to be actuated. FSAR analysis for assume a SG PORV fails in the open position allowing a path to the environment until the PORV can be isolated.

A. Incorrect. Plausible if candidate incorrectly calculates the leak rate at a value below 120 gpm and assume Safety injection is not required for these conditions, basis for SGTR leakage to the atmosphere is correct.

B. Incorrect. Plausible if candidate incorrectly calculates the leak rate at a value below 120 gpm and assume Safety injection is not required for these conditions, basis for SGTR leakage to the atmosphere is incorrect as it is based on a failed PORV which is isolable vice a Safety valve which has no isolation valves.

C. Correct.

D. Incorrect. Plausible if candidate correctly calculates the leak rate at a value above 120 gpm and Safety injection is required for these conditions, basis for SGTR leakage to the atmosphere is incorrect as it is based on a failed PORV which is isolable vice a Safety valve which has no isolation valves.

Tuesday, March 20, 2012 3:08:19 PM 8

QUESTIONS REPORT for 2012 NRC SRO REV 3 45 DAY SUBMITTAL EPE: 038 Steam Generator Tube Rupture (SGTR) 038EA2.13 Ability to determine or interpret the following as they apply to a SGTR:

Magnitude of rupture (CFR 43.5 / 45.13)

Importance Rating: 3.1 3.7 Technical

Reference:

Procedure, Step #, Page #, Rev #

References to be provided: None Learning Objective: PATH-2, EOP3-2, Obj. l.a Question Origin: New Comments:

Tier/Group: T1G1 SRO Justification: Knowledge of tech spec bases that is required to analyze tech spec required actions and terminology MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: CCCCCCCCCC Items Not Scrambled Origin: NEW Cog Level: C/A Difficulty:

Reference:

Ref. Provided: Key Words:

K/Al: 038EA2.13 KJA2:

Tuesday, March 20, 2012 3:08:19 PM 9

QUESTIONS REPORT for 201? NRC SRO REV 345 DAY SUBMITTAL

79. 2012 NRC SR0004 Given the following plant conditions:

- The plant is operating at 100%

- The ASI pump is under clearance

- A loss of Offsite Power has occurred

- EDG A and B started but neither EDG output breaker, 106 nor 126, will close lAW EPP-001, Loss of AC Powerto 1A-SA and lB-SB Busses, which ONE of the following is (1) the MINIMUM pressure that the intact SGs will be depressurized to AND (2) what will this pressure reduction accomplish?

A. (1)l3opsig (2) Reduces the AP across RCP seals to minimize leakage and loss of RCS inventory.

B. (1)l3opsig (2) Maximizes Natural Circulation flow to allow Reactor Vessel Head to cool since CRDM cooling fans are unavailable.

C (1)l8opsig (2) Reduces the AP across RCP seals to minimize leakage and loss of RCS inventory.

D. (1)l8opsig (2) Maximizes Natural Circulation flow to allow Reactor Vessel Head to cool since CRDM cooling fans are unavailable.

Tuesday, March 20, 2012 3:08:19 PM 10

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL P/a usibility and Answer Analysis Reason answer is correct: With ASI pumps not avialble the SG pressure is reduce 230 psig while cooling down the RCS cold legs as close to 100°F/hr as possible. Once SG pressure is below 230 psig the pressure is controlled between 180 to 230 psig in order to minimize RCS inventory loss while cooling the RCP seals in a controlled manner.

A. Incorrect. Plausible as 130 psig is the lower end of the control band for SG pressure following depressurizing during FRP-C. 1. Basis for these actions are correct for the SG pressure reduction to minimize RCS leakage via the RCP seals B. Incorrect. Plausible as 130 psig is the lower end of the control band for SG pressure following depressurizing during FRP-C. 1. Basis for these actions are incorrect for the SG pressure reduction as it will maximize RCS natural circulation, but does not provide adequate flow in the Upper head region of the RCS.

C. Correct.

D. Incorrect. Plausible as 180 psig is the lower end of the control band for SG pressure following depressurizing the below 230 psig. Basis for these actions are incorrect for the SG pressure reduction as it will maximize RCS natural circulation, but does not provide adequate flow in the Upper head region of the RCS.

Tuesday, March 20, 2012 3:08:19 PM 11

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL EPE: 055 Loss of Offsite and Onsite Power (Station Blackout) 055EG2.4.9 Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

(CFR: 41.10 /43.5 /45.13)

Importance Rating: 3.8 4.2 Technical

Reference:

EPP-001, Step 35, Page 56, Rev 40 and WOG background document for ECA-0.0 (EPP-001) page 117 Rev. 2 References to be provided: None Learning Objective: EPP-001, 002 & 003, Loss of All AC Power and recovery w/ or w/o Safety Injection, EOP3-7 Obj. 6 Question Origin: New Comments:

Tier/Group: TIGI SRO Justification: Assessing plant conditions (Normal, abnormal, or emergency) and the prescribing a procedure or section of a procedure to mitigate, recover or with which to proceed.

MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: CCCCCCCCCC Items Not Scrambled Origin: NEW Cog Level: FUIIDAMENTAL Difficulty:

Reference:

Ref. Provided: Key Words:

KJA 1: 055 EG2.4.9 K/A 2:

Tuesday, March 20, 2012 3:08:19 PM 12

QUESTIONS REPORT for 2012 NRC SRQ REV. 3 4 AY SUMtTTAL

80. 2OI2NRC SRO 005 Given the following plant conditions:

- The plant is operating at 100%

- ALB-015-5-4, 125 VDC EMER BUS B TROUBLE alarms

- The DC Voltmeter reads 128 VDC locally Which ONE of the following states (1) the MINIMUM total terminal voltage required to maintain the Battery OPERABLE lAW Technical Specifications, AND (2) the actions required for these conditions?

A (1)129VDC (2) Restore the inoperable D.C. electrical source to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

B. (1)129VDC (2) Restore the inoperable D.C. electrical source to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

C. (1)132VDC (2) Restore the inoperable D.C. electrical source to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

D. (1)132VDC (2) Restore the inoperable D.C. electrical source to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Plausibility and Answer Analysis Reason answer is correct: The 129 VDC is the minimum total battery terminal voltage per Technical Specification Surveillance Requirement 4.8.2.1 .a.2. The required action for this condition is to restore the inoperable D.C. source to operable within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per T.S. 3.8.2.1.

A. Correct.

B. Incorrect. Plausible if candidate recognizes minimum total battery terminal voltage for tech specs is 129 VDC, but applies the action statement for Onsite Power Distribution Operating T. S. 3.8.3.1 vice 3.8.2.1.

C. Incorrect. Plausible if candidate recognizes minimum total battery terminal voltage for rounds guidance is 132 VDC, correctly applies the action statement for D.C. Sources Operating T.S. 3.8.2.1.

D. Incorrect Plausible if candidate recognizes minimum total battery terminal voltage for rounds guidance is 132 VDC, but applies the action statement for Tuesday, March 20, 2012 3:08:19 PM 13

QUESTIONS REPORT for 2012 NRC SRQ REV 3 4DAY SUMlTTkL APE: 058 Loss of DC Power 058AA2.02 Ability to determine and interpret the following as they apply to the Loss of DC Power: 125V dc bus voltage, low/critical low, alarm (CFR: 43.5 /45.13)

Importance Rating: 3.3 3.6 Technical

Reference:

Tech Spec Surveillance requirement 4.8.2.1 .a.2 page 3/4 8-12 References to be provided: None Learning Objective: DC Power Obj. 12 Question Origin: Bank CIT Development 063 G2.4.50 Comments:

Tier/Group: T1G1 SRO Justification: Application of required actions (Section 3) and surveillance requirements (Section 4) in accordance with rules of application requirements (Section 1)

MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: A A A A A A A A A A Items Not Scrambled Origin: BANK Cog Level: C/A Difficulty:

Reference:

Ref. Provided: Key Words:

K/Al: 058AA2.02 K/A2:

Tuesday, March 20, 2012 3:08:19 PM 14

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL

81. 2O12NRC SRO 006 Given the following plant conditions:

- The plant was operating at 100%

- A Grid voltage problem results in a LOSP and a Reactor trip

- EDG A Fails to start

- Subsequently a Small Break LOCA occurs and the crew actuates Safety Injection.

- DSDG trips after starting Which ONE of the following completes the statements below?

Group (1) of indicators will NOT be available long term for MCR monitoring while performing recovery actions AND the Tech Spec required action is to restore the inoperable channels to OPERABLE status within (2) days.

Group 1 MCB indicators Group 2 MCB indicators TI-413.1, RCS Hot Leg Temp Loop A TI-420.1, RCS Cold Leg Temp Loop B PI-7160A, WR CNMT Pressure P1-403.1, WR RCS Pressure Ll-7162A, CNMT WR Sump Level Ll-487.1, SG Level Loop B (WR)

A. (1)1 (2) 30 B. (1)2 (2) 30 C (1)1 (2) 7 D. (1)2 (2) 7 Tuesday, March 20, 2012 3:08:19 PM 15

QUESTIONS REPORT for 2012 NRC SRO REV 3 45 DAY SUBMITTAL Plausibility and Answer Analysis Reason answer is correct: TI-413.1, RCS Hot Leg Temp, Pl-7160A, WR CNMT Pressure, LI-7162A, CNMT WR Sump Level will all become unavailable to the operator following depletion of the the A safety batteries. Tech Spec 3.3.3.6 action a. will apply at that time due to the loss of the A safety bus and the inability to charge up the A safety batteries A. Incorrect. Plausible if the T. S. 3.3.3.6 action d for RVLIS indication vice containment sump level is taken.

B. Incorrect. Plausible if the T. S. 3.3.3.6 action d for RVLIS indication vice containment sump level is taken.

C. Correct.

D. Incorrect. Plausible if the T. S. 3.3.3.6 action c for RCS subcooling monitor is taken due to the RCS pressure indication being loss.

Tuesday, March 20, 2012 3:08:19 PM 16

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL APE: 077 Generator Voltage and Electric Grid Disturbances 077AG2.4.3 Ability to identify post-accident instrumentation.

(CFR: 41.6 / 45.4)

Importance Rating: 3.7 3.9 Technical

Reference:

AOP-024, pages 27 and 34, Rev. 44, OST-1020, Attachment 1 pg 10 and 11, Tech Specs 3.3.3.6 action a References to be provided: None Learning Objective: AOP-024, Loss of Uninteruptible Power Supply, AOP3-24 Obj. 4 Question Origin: New Comments: None Tier/Group: T1GI SRO Justification: Based on the information provided the SRO must assess plant conditions, determine which indicators will be useable for recovery actions and then prescribe mitigation methods for the event lAW a section of an emergency procedure. The Tech Spec action is> 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and the information required to answer the Tech Spec is below the line.

SRO guidance justification provided by the Region II NRC: Knowledge of tech spec bases that is required to analyze tech spec required actions and terminology.

MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: CCCCCCCCCC Items Not Scrambled Origin: NEW Cog Level: C/A Difficulty:

Reference:

Ref. Provided: NONE Key Words: EARLY SUBMIT K/Al: 077 AG2.4.3 K/A 2:

Tuesday, March 20, 2012 3:08:19 PM 17

QUESTIONS REPORT for 2012 NRC SRQ RV 45 DAY SIJM1TTAL

82. 2012 NRC SRO 007 Given the following plant conditions:

- The plant is operating at 80% after a load rejection.

- It has been determined that two control rods in Bank D are misaligned by approximately 20 steps.

- BOTH rods are stuck and immovable.

- The AC dispatched to investigate reports no blown fuses or obvious electrical problems at the Rod Control Cabinets.

- All rods have been verified above the Rod Insertion limits.

Which ONE of the following actions are required in accordance with Technical Specifications and AOP-001, Malfunction of Rod Control and Indication System?

Check SDM within limits of the COLR within one hour and...

Ab place the unit in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

B. place the unit in MODE 4 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C. power may be maintained at the current value if a power distribution map based on movable incore detectors is verified to be within limits.

D. power may be maintained at the current value if reevaluation of accident analysis results remain valid for the current condition.

Plausibility and Answer Analysis Reason answer is correct: T.S. 3.1.3, Reactivity Control Systems Movable Control Assemblies action a. requires the unit to be placed in Mode 3 (Hot Standy) within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> in two or more rods are inoperable due to excessive friction or mechanical interference or known to be untrippable A. Correct.

B. Incorrect. Plausible because for a condition with no actions T. S. 3.0.3 allows 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to be in Mode 4 (Hot Shutdown), but the Mode of applicability for this LCO is Mode 1 and 2 only C. Incorrect. Plausible because the actions are correct if the control rod is trippable and not inoperable due to any of the conditions listed in action a

0. Incorrect. Plausible because the actions are correct if the control rod is inoperable due to a conditions not listed in action a, and shutdown margin is satisfied Tuesday, March 20, 2012 3:08:19 PM 18

QUESTIONS REPORT foy 2012 NRC SRQ REV 3 4 AY SLJMITTAL APE: 005 Inoperable/Stuck Control Rod 005AG2.2.22 Knowledge of limiting conditions for operations and safety limits.

(CFR: 41.5 / 43.2 / 45.2)

Importance Rating: 4.0 4.7 Technical

Reference:

T.S. 3.1.3.1 References to be provided: No Learning Objective: AOP-001, Malfunction of Rod Control and Indication, AOP3-1 Obj. 4 Question Origin: CIT Development Bank 005 AA2.03 2 Comments: 2008 Audit SRO Tier/Group: T1G2 SRO Justification: Knowledge of tech spec bases that is required to analyze tech spec required actions and terminology.

MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 67 89 Answer: AAAAAAAAAA Items Not Scrambled Origin: BANK Cog Level: C/A Difficulty:

Reference:

Ref. Provided: Key Words:

KJA 1: 005 AG2.2.22 K/A 2:

Tuesday, March 20, 2012 3:08:19 PM 19

QUESTIONS REPORT for 2012 NRC SRQ REV 345 AY S.IJMiTTAL

83. 2012 NRC SRO 008 Given the following plant conditions:

- A plant start up is in progress lAW GP-004, Reactor Startup (Mode 3 to Mode 2)

- Rx Power is Stable at 108 Amps to collect Critical Data

- ALB-01 3, 2-3; Source Range Loss of Detector Voltage is LIT Which ONE of the following completes the statement below?

CONTINUE operation, (1) because Reactor Power is (2)

A (1)IAWGP-004 (2) above P-6 with Source Range trips blocked B. (1)IAWGP-004 (2) below P-6 with Source Range trips enabled C. (1) REFER to OWP-RP, Reactor Protection (2) above P-6 with Source Range trips blocked D. (1) REFER to OWP-RP, Reactor Protection (2) below P-6 with Source Range trips enabled Plausibility and Answer Analysis Reason answer is correct: GP-004 directs Source range detectors to be blocked after exceeding P-6, Source range block permissive 10-10 Amps. With this condition satisfied the CRS should direct the continued operation of the plant per GP-004 once the critical data is collected at 10-8 Amps.

A. Correct.

B. Incorrect. Plausible because the action to block the Source range detectors has been previously directed within GP-004 and that the P-6 value is below 108 Amps.

C. Incorrect. Plausible because the APP directs this action if the source range detectors have a malfunction and require maintenance to investigate to repair the detector.

D. Incorrect. Plausible because the APP directs this action if the source range detectors have a malfunction and require maintenance to investigate to repair the detector and the action to block the Source range detectors has been previously directed within GP-004.

Tuesday, March 20, 2012 3:08:19 PM 20

QUESTIONS REPORT for 2012 NRC SRO REV 3 45 DAY SUBMITTAL APE: 032 Loss of Source Range Nuclear Instrumentation 032AG2.4.31 Knowledge of annunciator alarms, indications, or response procedures.

(CFR: 41.10 /45.3)

Importance Rating: 4.2 4.1 Technical

Reference:

APP-ALB-013, page 9, Rev. 30 References to be provided: None Learning Objective: GP-004, Reactor Startup, GP3-4 Obj. l.a Question Origin: New Comments: None Tier/Group: T1G2 SRO Justification: Based on the information provided the SRO must assess plant conditions in an abnormal plant condition then prescribe a procedure to proceed with.

SRO guidance justification provided by the Region II NRC: Assessing plant conditions (Normal, abnormal, or emergency) and the prescribing a procedure or section of a procedure to mitigate, recover or with which to proceed.

MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: A A A A A A A A A A Items Not Scrambled Origin: NEW Cog Level: C/A Difficulty:

Reference:

Ref. Provided: Key Words: EARLY SUBMIT KJA1: 032AG2.4.31 KIA2:

Tuesday, March 20, 2012 3:08:19 PM 21

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL

84. 2012 NRC SRO 009 Given the following plant conditions:

- The plant was operating at 100%

- A LOCA occurs

- The CRS has transitioned from PATH-i to FRP-P.1, Response to Imminent Pressurized Thermal Shock Thirty (30) minutes after the initiating event, the following conditions are observed:

- RCS pressure has lowered to 600 psig and is now stable

- Tcolds have lowered to 235°F and are now stable

- Containment pressure is 12.3 psig and slowly rising The CRS is now at the step to determine if a RCS Soak is required. Which ONE of the following identifies requirements for this event lAW FRP-P.1?

Soak Requirement Subsequent Cooldown Limit A Soak required <50°F in any 60 minute period B. Soak required < 100°F in any 60 minute period C. Soak NOT required <50°F in any 60 minute period D. Soak NOT required <100°F in any 60 minute period Plausibility and Answer Analysis Reason answer is correct: The trend over the last 30 minutes would warrant implementation of procedural guidance to perform a 1 hr soak and subsquent cooldown limit of 50°F/hr.

A Correct.

B Incorrect. Plausible since a one hour soak is required but 100°F/hr is not established in FRP-P. 1. 100°F/hr is the cooldown rate used in other EOPs (EPP-009, EPP-020, EPP-021).

C Incorrect. Plausible since a soak is not always required in FRP-P. 1 but with the existing cooldown in the last 30 mTh, a soak is required. .Subsquent cooldown limit of 50°F/hr is correct.

D Incorrect. Plausible since a soak is not always required in FRP-P. I but with the existing cooldown in the last 30 mm, a soak is required. 100°F/hr is not established in FRP-P. I but this is plausible since 100°F/hr is the cooldown rate used in other EOPs (EPP-009, EPP-020, EPP-021).

Tuesday, March 20, 2012 3:08:19 PM 22

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL E08 Pressurized Thermal Shock WEO8EA2.2 Ability to determine and interpret the following as they apply to the (Pressurized Thermal Shock): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

(CFR: 43.5 /45.13)

Importance Rating: 3.5 4.1 Technical

Reference:

EOP-FRP-P.1 Steps 32 and 33, pages 44 and 46, Rev.

22 References to be provided: None Learning Objective: FRP-P, Integrity Status Tree, EOP3-14 Obj. 1.d & i.e Question Origin: OIT Development Bank 062 K4.Oi Comments: None Tier/Group: T1G2 SRO Justification: Based on the information provided the SRO must assess plant conditions and then determine an emergency procedure strategy to proceed and recover from the event.

SRO guidance justification provided by the Region II NRC: Recalling what strategy or action is written into a plant procedure, including when the strategy or action is required MCS Time: I Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9 Answer: A A A A A A A A A A Items Not Scrambled Origin: BANK Cog Level: C/A Difficulty:

Reference:

Ref. Provided: Key Words: EARLY SUBMIT K/A I: WEO8 EA2.2 K/A 2:

Tuesday, March 20, 2012 3:08:19 PM 23

QUESTIONS REPORT for 2Q12 NRC SRO REV 45 DAY S1JMITTAL

85. 2OI2NRCSROO1O Given the following plant conditions:

- The CRS is evaluating FRPs for implementation.

- Containment pressure is 0.8 psig

- The following Steam Generator conditions exist:

- SG A Pressure = 1175 psig

- SG A Level = 79%

- SG B Pressure = 1235 psig

- SG B Level = 65%

- SG C Pressure = 1100 psig

- SG C Level = 23%

Which ONE of the following identifies the FRP terminus that is CURRENTLY displayed on the CSF-3, Heat Sink, Critical Safety Function Status Tree?

A FRP-H.2, Response to Steam Generator Overpressure B. FRP-H.3, Response to Steam Generator High Level C. FRP-H.4, Response to Loss of Normal Steam Release Capability D. FRP-H.5, Response to Steam Generator Low Level Plausibility and Answer Analysis Reason answer is correct: FRP-H.2 (Yellow path procedure) would be addressed first by the status tree because Narrow Range level in at least one SG is > 25% and pressure in any SG is> 1230 psig.

A Correct.

B Incorrect. Plausible since FRP-H.3 is a yellow path that will need to be addressed for the A Steam Generator but current conditions will require addressing the overpressure condition first.

C Incorrect. Plausible since FRP-H. 4 is a yellow path that will need to be addressed for the A Steam Generator but the current conditions require implementing H. 2 D Incorrect. Plausible since FRP-H. 5 is a yellow path that will need to be addressed for C Steam Generator but the current conditions require implementing H.2 Tuesday, March 20, 2012 3:08:19 PM 24

QUESTIONS REPORT for 2012 NRC SRQ REV 3 4 AY SUMLTTAL E13 Steam Generator Overpressure WEI3EA2.1 Ability to determine and interpret the following as they apply to the (Steam Generator Overpressure): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Importance Rating: 2.9 3.4 Technical

Reference:

EOP-CSFST Rev. 9, page 2 of 3 (Side 1)

References to be provided: None Learning Objective: FRP-H, Heat Sink Status Tree, EOP3-1 1 Obj. 4a Question Origin: Bank CIT Development WE13EA2.1 Comments:

Tier/Group: T1G2 SRO Justification: Assessing plant conditions (Normal, abnormal, or emergency) and the prescribing a procedure or section of a procedure to mitigate, recover or with which to proceed.

MCS Time: I Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9 Answer: A A A A A A A A A A Items Not Scrambled Origin: BANK Cog Level: C/A Difficulty:

Reference:

Ref. Provided: Key Words:

KIA1: WEI3EA2.1 KJA2:

Tuesday, March 20, 2012 3:08:19 PM 25

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL

86. 2O12NRC SRO 011 Given the following plant conditions:

- The plant was operating at 100%

- ALB-015, 2-2, PlC 1-2-3-4-9-10-13-14 Power Failure, is intermittently alarming and clearing.

- Troubleshooting reveals the PlC Cabinet 3 Card C3-845 for the Channel III, SF/FF trip bistable 478B has an open circuit.

Which ONE of the following completes the statement below?

The CRS is required to implement (1) in order to replace the defective card AND the Tech Spec required action is to place the channel in the tripped condition within (2) hours.

A (1) OWP - RP, Reactor Protection (2) 6 B. (1) OWP - RP, Reactor Protection (2) 4 C. (1) OWP - ESF, Engineered Safety Feature Actuation (2) 6 D. (1) OWP ESF, Engineered Safety Feature Actuation (2) 4 Tuesday, March 20, 2012 3:08:19 PM 26

QUESTIONS REPORT fQr 2012 NRC SRQ REV 345 DAY SUBMITTAL Plausibility and Answer Analysis Reason answer is correct: OWP-RP, provides the directions to remove the SF/FF bistable from service to comply with T.S. 3.3.1 action 6 which requires the inoperable channel in the trip conditions within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> A. Correct.

B. Incorrect. Plausible because the procedure selection is correct for the failed card in the RPS system, but 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is the T. S. allowable time the inoperable channel maybe bypassed for surveillence testing of other channels C. Incorrect. Plausible because the procedure selection would apply to the steam generator steam pressure transmitter vice the steam generator steam flow transmitter which is in the ESFAS system, T. S. action time is correct D. Incorrect. Plausible because the procedure selection would apply to the steam generator steam pressure transmitter vice the steam generator steam flow transmitter which is in the ESFAS system AND the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is the T. S.

allowable time the inoperable channel maybe bypassed for suaveilence testing of other channels Tuesday, March 20, 2012 3:08:19 PM 27

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL 012 Reactor Protection System 01 2A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Erratic power supply operation (CFR: 41.5 /43.5 /45.3 /45.5)

Importance Rating: 3.1 3.2 Technical

Reference:

PATH-i, RPS text, AOP-025, Step #, Page #, Rev #

References to be provided: None Learning Objective: Operations Tests and Work Procedures, PP3-3 Obj. 2 & 3 Question Origin: New Comments:

Tier/Group: T2G1 SRO Justification: Assessing plant conditions (Normal, abnormal, or emergency) and the prescribing a procedure or section of a procedure to mitigate, recover or with which to proceed.

MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: A A A A A A A A A A Items Not Scrambled Origin: BANK Cog Level: C/A Difficulty:

Reference:

Ref. Provided: Key Words:

K/Al: 012A2.04 K/A2:

Tuesday, March 20, 2012 3:08:19 PM 28

QUESTIONS REPORT for 2012 NRC SRO REV3 4 DAY SUBMITTAL

87. 2012 NRC SRO 012 Given the following plant conditions:

- The plant was operating at 100%

- A LOCA has occurred

- Emergency Bus 1A-SA is deenergized

- All RCPs are operating

- CNMT pressure is 7 psig and increasing

- CSIP B tripped on overcurrent The following occurs:

- RVLIS indication is 58% and decreasing

- CNMT pressure increases to 11 psig Which ONE of the following completes the statement below?

Based on these conditions, the ESFAS system will start the Sequencer B in program (1) AND lAW FRP-C.2, Response to Degraded Core Cooling, the crew should stop RCP B only, then depressurize ALL intact SGs (2)

A. (1)B (2) at maximum rate B. (1)B (2) while maintaining Cooldown Rate <100°F/Hr C. (1)C (2) at maximum rate D (1)C (2) while maintaining Cooldown Rate <100°F/Hr Tuesday, March 20, 2012 3:08:20 PM 29

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL Plausibility and Answer Analysis Reason answer is correct: ESFAS system will run the sequencer on program C during safety injection. 100°F/Hr CDR is applicable to FRP-C.2 A. Incorrect. Plausible because A sequencer is running on program B for both SI and Loss of power. Max Rate in not used in FRP-C.2 but is in FRP-C. 1.

B. Incorrect. Plausible because A sequencer is running on program B for both SI and Loss of power. 100°F/Hr CDR is applicable to FRP-C.2 C. Incorrect. Plausible as the ESFAS system will run the sequencer on program C during safety injection, Max Rate in not used in FRP-C. 2 but is in FRP-C. I

0. Correct.

Tuesday, March 20, 2012 3:08:20 PM 30

QUESTIONS REPORT for2Ol2 NRC SRO REV345 DAY SUM1TTAL 013 Engineered Safety Features Actuation 01 3A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Rapid depressu rizatio n (CFR: 41.5 /43.5 /45.3 /45.13)

Importance Rating: 4.4 4.7 Technical

Reference:

Sequencer Student text page 9, Rev 4, EOP-FRP-C.2, Step 11, Page 18, Rev 17 References to be provided: None Learning Objective: FRP-C, Core Cooling Status Tree, EOP3-10 Obj. 4.h Safeguards Sequencer Obj. 3 Question Origin: New Comments: None Tier/Group: T2G1 SRO Justification: Based on the information provided the SRO must assess plant conditions then determine the strategy prescribed for the event lAW a section of an emergency procedure.

SRO guidance justification provided by the Region II NRC: Recalling what strategy or action is written into a plant procedure, including when the strategy or action is required MCS Time: I Points: 100 Version: 0 1 2 3 4 5 6 7 8 9 Answer: D D D D D D D D D D Items Not Scrambled Origin: NEW Cog Level: C/A Difficulty:

Reference:

Ref. Provided: Key Words: EARLY SUBMIT K/A 1: 013 A2.03 K/A 2:

Tuesday, March 20, 2012 3:08:20 PM 31

QUESTIONS REPORT for 2012 NRC SRO REV 3 4 AY SUBMITTAL

88. 2012 NRC SRO 013 Given the following plant conditions:

- The plant is in Mode 3

- The Motor Driven Auxiliary Feedwater (MDAFW) pumps are feeding the steam generators Which ONE of the following completes the statement below?

Shutting (1) would render BOTH MDAFW pumps inoperable AND lAW Tech Specs the plant must be in Mode 4 within (2) hours, if the valve could not be reopened?

A. (1) FK-2051-1A1 SA, AFW FWA Regulator 1AF-49 (2) 6 B. (1) FK-2051-1A1 SA, AFW FWA Regulator 1AF-49 (2) 12 C (1) 1AF-55 SB, Aux FWA Isolation (2) 6 D. (1) 1AF-55 SB, Aux FW A Isolation (2) 12 Tuesday, March 20, 2012 3:08:20 PM 32

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL Plausibility and Answer Analysis Reason answer is correct: lAW Precaution and Limitation 16 of OP-137, Aux Feedwater System, shutting Motor-Driven AFW Pump Header Isolation Valves causes both pumps to be inoperable. Since 1AF-55 SB is the A SG MDAFW pump header isolation valve shutting this valve would then render both MDAFW pumps inoperable. TS 3.7.1.2 Action b states that with two auxiliary feedwater pumps inoperable be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Since the plant is in Mode 3 (Hot Standby) the 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to Hot Standby does not apply therefore the time required to be in Mode 4, Hot Shutdown is 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

A. Incorrect. Plausible if the candidate believes that shutting either the flow control valve or isolation valve will render the MDAFW pump inoperable. The second part of the answer is correct.

B. Incorrect. Plausible if the candidate believes that shutting either the flow control valve or isolation valve will render the MDAFW pump inoperable. The second part of the answer is plausible if the candiate applies the 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to Hot Shutdown to the time required to be in Hot Standby.

C. Correct.

0. Incorrect. The first part of the answer is correct. The second part of the answer is plausible if the candiate applies the 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to Hot Shutdown to the time required to be in Hot Standby.

Tuesday, March 20, 2012 3:08:20 PM 33

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL 061 Auxiliary I Emergency Feedwater (AFW) System 061G2.2.40 Ability to apply Technical Specifications for a system.

(CFR: 41.10 I 43.2 /43.5 / 45.3)

Importance Rating: 3.4 4.7 Technical

Reference:

OP-I 37 P&L #16, page 10 Rev. 30, TS 3.7.1.2 action b page 3/4 7-4 References to be provided: None Learning Objective: Auxiliary Feedwater Obj. S.c & 14 Question Origin: New Comments:

Tier/Group: T2GI SRO Justification: Assessing plant conditions (Normal, abnormal, or emergency) and the prescribing a procedure or section of a procedure to mitigate, recover or with which to proceed.

MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: C C C C C C C C C C Items Not Scrambled Origin: NEW Cog Level: FUNDAMENTAL Difficulty:

Reference:

Ref. Provided: Key Words:

K/Al: 061 G2.2.40 K/A 2:

Tuesday, March 20, 2012 3:08:20 PM 34

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMJTTAL

89. 2012 NRC SRO O4 Given the following plant conditions:

- The plant is operating at 100%

- The following annunciators are received in the Control Room:

ALB-002 6-1, SERV WTR SUPPLY HDR A LOW PRESS ALB-002 7-1, SERV WTR SUPPLY HDR B LOW PRESS ALB-002 7-2, SERV WTR PUMPS DISCHARGE LOW PRESS

- Ll-1931, Cooling Tower Basin Level, is lowering.

- P1-9302.1, NSW Disch Hdr Press, is lowering.

- Pl-9101A1 SA, ESW A Disch Press, is lowering.

- Pl-9101B1 SB, ESW B Disch Press, is lowering.

- Both ESW pumps automatically start and align to their respective header.

- PI-9101A1 SA, ESWA Disch Press stabilizes.

- Pl-9101B1 SB, ESW B Disch Press stabilizes.

- ALB-002-7-2 remains locked in and the Cooling Tower Basin Level continues to lower.

Which ONE of the following describes (1) the location of the leak, and (2) the action required?

A (1) Normal Service Water System (2) Trip the Reactor and go to PATH-i B. (1) Emergency Service Water System (2) Trip the Reactor and go to PATH-i C. (1) Normal Service Water System (2) Trip the Turbine and ensure NSW is aligned per AOP-022, Attachment 2 D. (1) Emergency Service Water System (2) Trip the Turbine and ensure ESW is aligned per AOP-022, Attachment I Tuesday, March 20, 2012 3:08:20 PM 35

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL Plausibility and Answer Analysis Reason answer is correct: Cooling Tower level decreasing indicates a leak on NSW.

Because suction cannot be maintained, and power is >P-10, the Reactor will be tripped is required.

A. Correct.

B. Incorrect. Plausible because ESW header pressure lowers prior to ESW pump start which indicates a leak in the system, but the header is automatically isolated from NSW when the associated ESW Pump starts.

C. Incorrect. Plausible because tripping the turbine is the action to be taken with reactor power below P-1O and to isolate NSW, Attachment 2 is performed.

D. Incorrect. Plausible because ESW header pressure lowers prior to ESW pump start which indicates a leak in the system, but the header is automatically isolated from NSW when the associated ESW Pump starts. Trip of the reactor is required due to power being above P-1O prior to tripping the turbine.

Tuesday, March 20, 2012 3:08:20 PM 36

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUSMITTAi 076 Service Water System (SWS) 076G2.1 .7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

(CFR: 41.5/43.5/45.12/45.13)

Importance Rating: 4.4 4.7 Technical

Reference:

AOP-022, Section 3.0, Steps 11, Page 12, Rev. 34 References to be provided: None Learning Objective: AOP-022, Loss of Service Water, AOP3-22 Obj. 6 Question Origin: OIT Development Bank 076 A2.02 Comments: None Tier/Group: T2GI SRO Justification: Based on the information provided the SRO must assess plant conditions then select a procedure to mitigate the event.

SRO guidance justification provided by the Region II NRC: Assessing plant conditions (Normal, abnormal, or emergency) and the prescribing a procedure or section of a procedure to mitigate, recover or with which to proceed.

MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: A A A A A A A A A A Items Not Scrambled Origin: BANK Cog Level: C/A Difficulty:

Reference:

Ref. Provided: Key Words: EARLY SUBMIT K/Al: 076G2.l.7 K/A2:

Tuesday, March 20, 2012 3:08:20 PM 37

QUESTIONS REPORT for 2012 NRC SRQ RV 345 DY SUBMITTAL

90. 2OI2NRC SRO 015 Given the following plant conditions:

- The plant is operating at 100%

- The Compressed Air system (CAS) Control Panel is set for Air Compressor C in LEAD (Sequence 3)

- A Valve Shift failure is present on Air Dryer 1C-NNS

- Instrument Air Header pressure indicates 110 psig Which ONE of the following describes (1) the impact of this failure AND (2) the procedure the CRS will implement to address this failure?

A. (1) High Air Dryer AP may cause a Loss of Instrument Air.

(2) Bypass Air Dryer 1C-NNS lAW AOP-017, Loss of Instrument Air.

By (1) Instrument Air may have a higher than desired moisture content.

(2) Shift the CAS Control Panel to Air Compressor A in LEAD (Sequence 1) and isolate Air Dryer 1C-NNS lAW OP-151.01, Compressed Air.

C. (1) Instrument Air may have a higher than desired moisture content.

(2) Bypass Air Dryer 1C-NNS lAW AOP-017, Loss of Instrument Air.

D. (1) High Air Dryer AP may cause a Loss of Instrument Air.

(2) Shift the CAS Control Panel to Air Compressor A in LEAD (Sequence 1) and isolate Air Dryer 1C-NNS lAW OP-151.01, Compressed Air.

Tuesday, March 20, 2012 3:08:20 PM 38

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUM1TTAL Plausibility and Answer Analysis Reason answer is correct: The purpose of the Instrument Air dryers are to reduce the moisture content in the Instrument Air system. If a dryer has a valve shift error it will not longer function to remove the moisture from the air system. Therefore the moisture content of the Instrument Air system may increase. Precaution and Limitiation #7 states that if a valve shift failure occurs on Air Dryer 1C-NNS then Air Dryers 1A-NNS and 1B-NNS should be placed in service and the CAS Controller Sequence should be changed to Sequence 1 or Sequence 2 and Air Dryer 1C-NNS removed from service until corrective actions are performed.

A. Incorrect. Plausible because is the AOP-O1 7 is used to address air problems, but AOP-O1 7 entry is not neccessaiy.

B. Correct.

C. Incorrect. Plausible because the two air dryers are on each skid, but the CRS would not place other air dryer in se,vice on Air Compressor IC since it has a problem.

D. Incorrect. Plausible because is the AOPOI 7 is used to address air problems, but AOP-OI 7 entry is not necessary. Would not perform a manual valve shift either Tuesday, March 20, 2012 3:08:20 PM 39

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL 078 Instrument Air System (lAS) 078A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the lAS; 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 (CFR: 41.5 /43.5 /45.3 /45.13)

Importance Rating: 2.4 2.9 Technical

Reference:

OP-151.01, Precaution and Limitation #7, Page 8, Rev 66 References to be provided: None Learning Objective: Instrument and Service Air Obj. 4.b Question Origin: Bank Comments: 2006 HNP NRC SRO question 16 SRO level of knowledge based on requirement to select appropriate procedure.

Tier/Group: T2G1 SRO Justification: Assessing plant conditions (Normal, abnormal, or emergency) and the prescribing a procedure or section of a procedure to mitigate, recover or with which to proceed.

MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: BBBBBBBBBB Items Not Scrambled Origin: BANK Cog Level: C/A Difficulty:

Reference:

Ref. Provided: Key Words:

K/Al: 078A2.0l K/A2:

Tuesday, March 20, 2012 3:08:20 PM 40

QUESTIONS REPORT for ?012 NRC SRO REV 345 DAY SUBMITTAL

91. 2012 NRC SRO 016 Given the following plant conditions:

- The plant is operating at 48% power

- Control Bank D is at 150 steps An event occurs resulting in the following indications:

- RCS Tavg is approximately 572°F and lowering

- Reactor Power is lowering

- First Stage Pressure Transmitter PT-446 indicates 0 psig

- First Stage Pressure Transmitter PT-447 indicates 310 psig and stable

- Main Generator Load is 450 MWe and stable

- Control Bank D is inserting at 72 steps per minute Which ONE of the following describes (1) the procedure entry required to mitigate the event AND (2) the Tech Spec reason for the actions taken within the procedure?

A (1) AOP-001, Malfunction of Rod Control and Indication System (2) to prevent violating Rod Insertion limits B. (1) AOP-001, Malfunction of Rod Control and Indication System (2) to prevent an out of spec negative AFD C. (1) AOP-006, Turbine Generator Trouble (2) to prevent violating Rod Insertion limits D. (1) AOP-006, Turbine Generator Trouble (2) to prevent an out of spec negative AFD Tuesday, March 20, 2012 3:08:20 PM 41

QUESTIONS REPORT for 2012 NRC SRQ REV345 DAY SUBMITTAL Plausibility and Answer Analysis Reason answer is correct: Correct action and procedure. Action/Bases is lAW T.S.

(3.1.3.6/Rods above the insertion limits)

A. Correct.

B. Incorrect. Plausible because input is the Turbine 1st stage pressure and the procedure is correct, but the T. S. action is incorrect. AFD limit is not applicable below 50% power.

C. Incorrect. Plausible because input is the Turbine 1st stage pressure and AOP-006 addresses problems on the Turbine, T. S. action is correct for this condition.

D. Incorrect. Plausible because input is the Turbine 1st stage pressure and AOP-006 addresses problems on the Turbine, but the T. S. action is incorrect. AFD is not applicable below 50% power.

016 Non-Nuclear Instrumentation System (NNIS) 016A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the NNIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure (CFR: 41.5 / 43.5 / 45.3 I 45.5)

Importance Rating: 2.5 2.6 Technical

Reference:

Procedure, Step #, Page #, Rev #

References to be provided: None Learning Objective: AOP-001, Malfunction of Rod Control and Indication, AOP3-1 Obj. 6 & 1 Question Origin: Bank OIT Development Bank 001 AA2.05 I Comments: Original K/A was 016A2.04 but was replaced on 11-15-2011 using random selection by Richard Baldwin at Archie Luckys request. (Unable to write a question to at the SRO level to the original K/A).

Tier/Group: T2G2 SRO Justification: Assessing plant conditions (Normal, abnormal, or emergency) and the prescribing a procedure or section of a procedure to mitigate, recover or with which to proceed.

Tuesday, March 20, 2012 3:08:20 PM 42

QUESTIONS REPORT for 2Q12 NRC SRO REV 345 DAY SUBMITTAL MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: A A A A A A A A A A Items Not Scrambled Origin: BANK Cog Level: C/A Difficulty:

Reference:

Ref. Provided: Key Words:

KIA1: 016A2.01 K/A2:

Tuesday, March 20, 2012 3:08:20 PM 43

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL

92. 2012 NRC SRO 017 Given the following plant conditions:

- The crew is performing FRP-C.1, Response to Inadequate Core Cooling

- All RCP5 are stopped

- NO CSIP5 or RHR Pumps are available

- NO source of SG feedwater is available

- ALL SC NR levels are OFF-SCALE low Current Plant Conditions:

- Core Exit TCs are reading 1250 F

- RVLIS Full Range is 27%

- The crew has depressurized intact SGs to 130 psig and were unsuccessful in reducing RCS temperature Which ONE of the following (1) identifies the actions the CRS should take for procedure implementation AND (2) the action to mitigate this event?

A. (1) Transition to SACRG-1, Severe Accident Control Room Guideline Initial Response; (2) Start one RCP B. (1) Transition to SACRG-1, Severe Accident Control Room Guideline Initial Response; (2) Open PRZ PORV5 and Block Valves C. (1) Remain in FRP-C.1; (2) Start one RCP D (1) Remain in FRP-C.1; (2) Open PRZ PORVs and Block Valves Tuesday, March 20, 2012 3:08:20 PM 44

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL Plausibility and Answer Analysis Reason answer is correct: As noted above without an available loop RCP start will not be performed. RNO is to open primary vent paths and re-affempt secondary depressu rization to initiate accumulator injection.

A. Incorrect, transition to SACRG-1 is a flowpath provided by the procedure but it is only implemented after additional actions are taken to attempt to restore core cooling.

B. Incorrect, transition to SACRG-1 is a flowpath provided by the procedure but it is only implemented after additional actions are taken to attempt to restore core cooling.

C. Incorrect. RCP will not be started because SG level must be >25% to permit RCP start based on the concern for creep rupture failure of the SG U-tubes.

Plausible because no other method of core cooling has succeeded and starting an RCP would initiate forced circulation of any remaining RCS fluid.

D. Correct.

Tuesday, March 20, 2012 3:08:20 PM 45

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL EPE 074 Inadequate Core Cooling 068G2.4.6 Knowledge of EOP mitigation strategies.

(CFR: 41.10/43.5/45.13)

Importance Rating: 3.7 4.7 Technical

Reference:

FRP-C.1, Step 19, 20, Page 28, 30, Rev 17 References to be provided: None Learning Objective: LPEOP3.10, Core Cooling Status Tree, Obj. l.a Question Origin: Bank OIT Development Bank 017 A2.02 Comments: Rick Baldwin replaced K/A on 11/14/2011 at HNP request. Exam team was unable to write a SRO level question on original K/A which was 068 (Liquid Radwaste System) G2.4.6 Tier/Group: T2G2 SRO Justification: Assessing plant conditions (Normal, abnormal, or emergency) and the prescribing a procedure or section of a procedure to mitigate, recover or with which to proceed.

MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: D D D D D D D D D D Items Not Scrambled Origin: BANK Cog Level: C/A Difficulty:

Reference:

Ref. Provided: Key Words:

K/Al: 068G2.4.6 K/A2:

Tuesday, March 20, 2012 3:08:20 PM 46

QUESTIONS REPORT for 2012 NRC SRQ RV 3 45 DAY SUBMITTAL

93. 2O12NRCSROO18 Given the following plant conditions:

- The plant is operating at 100% power

- Operators are aligning a Waste Gas release lAW OP-i 20.07, Waste Gas System

- The total concentration for the WGDT to be released is above the value for waiving the requirement to check the stability class

- The weather is degrading due to a temperature inversion

- ERFIS indicated Stability Class B when the permit was prepared but now indicates Stability Class E.

Which ONE of the following describes (1)the impact of the stability change on the planned release AND (2) lAW OPS-NGGC-1 000, Fleet Conduct Of Operations, who is responsible to review and sign the Batch Gaseous Effluent Permit to authorize the release?

A. (1) The release is on hold until a new permit with the current stability class is issued.

(2) The CRS B (1) The release is on hold until it is predicted that the Stability Class will be a Stability Class C in the next 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

(2) The CRS C. (1) The release is on hold until a new permit with the current stability class is issued.

(2) The Shift Manager D. (1) The release is on hold until it is predicted that the Stability Class will be a Stability Class C in the next 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

(2) The Shift Manager Tuesday, March 20, 2012 3:08:20 PM 47

QUESTIONS REPORT for 2012 NRC SRQ REV 345 DAY SUBMITTAL Plausibility and Answer Analysis Reason answer is correct: OP-i 20.07 gives Stability Class A, B, and C as one of the ERFIS required Stability classes to release to the environment A. Incorrect. Plausible because any release requires an accurate permit but the stability class can change within those listed in the procedure, during the release. The second part is correct.

B. Correct.

C. Incorrect. Plausible because any release requires an accurate permit but the stability class can change within those listed in the procedure, during the release. The second part is plausible because per OP-120.07 the Shift Manager could approve the release (but this question asks who approves the release lAW OPS-NNGC-1000).

D. Incorrect. The first part is correct. The second part is plausible because per OP-120.07 the Shift Manager could approve the release (but this question asks who approves the release lAW OPS-NNGC-1000).

Tuesday, March 20, 2012 3:08:20 PM 48

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL 071 Waste Gas Disposal System (WGDS) 071A2.08 Ability to (a) predict the impacts of the following malfunctions or operations on the Waste Gas Disposal System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Meteorological changes (CFR: 41.5/43.5/45.3 / 45.13)

Importance Rating: 2.5 2.8 Technical

Reference:

OP-120.07, Page 165, Rev. 54, OPS-NGGC-1000, CRS Responsibilities #16, Page 22, Rev. 6 References to be provided: None Learning Objective: Liquid Waste Processing Student Text, Obj 4 Question Origin: New Comments:

Tier/Group: T2G2 SRO Justification: Fuel handling facilities and procedures: Refuel floor SRO responsibilities MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: BBBBBBBBBB Items Not Scrambled Origin: NEW Cog Level: FUNDAMENTAL Difficulty:

Reference:

OP-120.07 Ref. Provided: NONE Key Words:

K/Al: 071 A2.08 K/A 2:

Tuesday, March 20, 2012 3:08:20 PM 49

QUESTIONS REPORT for 2012 NRC SRO REV 345 W\Y SUMLTTAL

94. 2012 NRC SRO 019 Given the following plant conditions:

- The plant was in Mode 6 with refueling in progress Current plant conditions are:

- Fuel movement has stopped due to a problem with the gripper tube top limit switch on the Manipulator

- The Main Control Room has been informed that initial troubleshooting is in progress on the Manipulator

- The troubleshooting team desires to operate TS-3, Bridge Left Interlock Bypass, in order to move the bridge while the gripper tube is not at the top limit lAW FHP-020, Refueling Operations, which ONE of the following identifies (1) the individual required to approval this action AND (2) if required, the individual that must concur with this approval?

A. (1) The CRS must approve (2) NO concurrence is required.

B. (1) The CRS must approve (2) with concurrence of of the SM.

C. (1) The SRO-Fuel Handling must approve (2) NO concurrence is required.

Dv (1) The SRO-Fuel Handling must approve (2) with the concurrence of the SM.

Tuesday, March 20, 2012 3:08:20 PM 50

QUESTIONS REPORT for Q12 NRC SRQ REV 345 DAY SUBMLTTAL Plausibility and Answer Analysis Reason answer is correct: FHP-020 Rev. 37 P & L 26 reads: Bypassing of fuel handling equipment interlocks which are not specified in approved procedures shall require permission of the SRO-Fuel Handling and concurrence of the SM.

A. Incorrect. Plausible because the CRS does give permission for normal plant evolutions.

B. Incorrect. Plausible because the SM only needs to concur with bypassing the interlock. Plausible because the CRS does give permission for normal plant evolutions.

C. Incorrect. Plausible because concurrence is required from SM per FHP-020, not approval.

D. Correct.

2.1 Conduct of Operations G2.1.41 Knowledge of the refueling process.

(CFR: 41.2 /41.10 /43.6 /45.13)

Importance Rating: 2.8 3.7 Technical

Reference:

FHP-020, P&L 26, page 11, Rev. 44 References to be provided: None Learning Objective: LP-FHS Obj. 6 (answer on page 26 of Lesson plan)

Question Origin: Bank CIT Development G2.1.41 Comments: 2009A NRC SRO Tier/Group: T3 SRO Justification: Fuel handling facilities and procedures: Refuel floor SRO responsibilities Tuesday, March 20, 2012 3:08:20 PM 51

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: D D D D D D D D D D Items Not Scrambled Origin: BANK Cog Level: C/A Difficulty:

Reference:

FHP-020 Ref. Provided: NONE Key Words:

KJA1: G2.1.41 KIA2:

Tuesday, March 20, 2012 3:08:20 PM 52

QUESTIONS REPORT fQr 1Q12 NRC SRQ RV 345 DAY SUBMITTAL

95. 2OI2NRC SRO 020 Which ONE of the following completes the statement below?

The Technical Specification basis for the PRZ Code safety valves is that the combined relief capacity of all the PRZ Code safeties is greater than the maximum surge rate assuming (1) AND (2)

A. (1) a complete loss of load directly resulting in a reactor trip from the turbine trip; (2) no operation of the PRZ PORVs or the steam dumps By (1) a complete loss of load with no reactor trip until the second trip setpoint is reached; (2) no operation of the PRZ PORV5 or the steam dumps C. (1) a complete loss of load directly resulting in a reactor trip from the turbine trip; (2) no operation of the PRZ PORVs, steam dumps operate as designed D. (1) a complete loss of load with no reactor trip until the second trip setpoint is reached; (2) no operation of the PRZ PORVs, steam dumps operate as designed Tuesday, March 20, 2012 3:08:20 PM 53

QUESTIONS REPORT for 2Q12 NRC SRQ RV 345 DAY SUBMITTAL Plausibility and Answer Analysis Reason answer is correct: In Modes 1, 2, 3, all code safeties must have lift settings of 2485 =1- 1% The combined relief capacity of all of these valves is greater than the maximum surge rate resulting from a complete loss-of-load assuming no reactor trip until the second Reactor Trip System trip setpoint is reached (i.e., no credit is taken for a direct Reactor trip on the loss-of-load) and also assuming no operation of the power-operated relief valves or steam dump valves.

A. Incorrect, no credit is given for the loss of load. But plausible since a reactor trip signal will be generated and the POR V/steam dump basis is correct.

B. Correct.

C. Incorrect. Since no credit is given for the loss of load reactor trip and basis does not assume that both the PORVs AND the steam dumps fail though plausible since this would be a more conseivative assumption D. Incorrect. Since the basis does not assume that both the PORVs and the steam dumps fail though plausible since this would be a more conservative assumption.

Tuesday, March 20, 2012 3:08:20 PM 54

QUESTIONS REPORT for 2012 NRC SRQ RV 3 45 DAY SUBMLTTAL 2.2 Equipment Control G2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

(CFR: 41.5 / 41.7 / 43.2)

Importance Rating: 3.2 4.2 Technical

Reference:

TS 3.4.2 Basis References to be provided: None Learning Objective: PZRPC obj 12 Question Origin: Bank OIT Development G2.2.25 Comments: 2008 NRC SRO Tier/Group: T3 SRO Justification: Knowledge of tech spec bases that is required to analyze tech spec required actions and terminology MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: BBBBBBBBBB Items Not Scrambled Origin: BANK Cog Level: FUNDAMENTAL Difficulty:

Reference:

TS 3.4.2 BASIS Ref. Provided: NONE Key Words:

KJA 1: G2.2.25 KJA 2:

Tuesday, March 20, 2012 3:08:20 PM 55

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL

96. 2O12NRC SRO 021 Given the following plant conditions:

- The plant is operating at 100% power.

- The low flow input from AH-1 A-SB to annunciator ALB-29/3-2, CONTAINMENT FAN COOLERS AH-1 LOW FLOW OIL, is failed causing the annunciator to be lit when conditions are not valid.

- Repair of the failed low flow input is not expected to occur for at least one month.

- To enable this annunciator to function for AH-1 B-SB low flow and the overload condition on either fan, leads will be lifted to disable the annunciator input from the AH-1 A-SB low flow output.

lAW OPS-NGGC-1000, Fleet Conduct of Operations, the annuciator should be flagged (1) lAW OPS-NGGC-1 308, Plant Status Control, (2) tags should be placed on the lifted leads.

A. (1) blue (2) Equipment Control B. (1) blue (2) Off Normal C. (1)yellow (2) Equipment Control D (1) yellow (2) Off Normal Tuesday, March 20, 2012 3:08:20 PM 56

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL Plausibility and Answer Analysis Reason answer is correct: Per OPS-NGGC-1 000 a yellow flag or coded will be used when one or more inputs to a multiple input annunciator are disabled. Per OPS-NGGC-1308 a plant status control tag (off normal) will be used to identify a component is in an Off Normal Position.

A. Incorrect. Part I is plausible because blue is used for annunciators that are disabled or removed vrom service. Part 2 is plausible because guidance for equipment control tags is contained in OPS-NGGC-1308.

B. Incorrect. Part I is plausible because blue is used for annunciators that are disabled or removed vrom service. Part 2 is correct.

C. Incorrect. Part I is correct. Part 2 is plausible because guidance for equipment control tags is contained in OPS-NGGC-1308.

D. Correct.

2.2 Equipment Control G2.2.43 Knowledge of the process used to track inoperable alarms.

(CFR: 41.10 / 43.5 I 45.13)

Importance Rating: 3.0 3.3 Technical

Reference:

OPS-NGGC-1 000 page 90, Rev. 6 OPS-NGGC-1308 page 8, Rev. 3 References to be provided: None Learning Objective: PP-LP-2.0/3.0/5.0, RO obj 3.k Question Origin: Bank Previous 2011 NRC SRO question 20 Comments: Modified distractor from Caution to Equipment Control tag Tier/Group: T3 SRO Justification: Knowledge of administrative process for tracking inoperable annunciators.

Tuesday, March 20, 2012 3:08:20 PM 57

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL Given the fo cling plant condhions;

- Th plant is opea:ir-g a: 1OJ% power.

- The ow ftw irpu: frcn AH-i A-SB ro annunciator ALB-23-2, CONTAIlAENT FAN COOLERS Al-Li LD: FLOW Ot, a faied causing tne annuncacr :o be Ii:

when cccdifions ae not vad.

- Repair of the failed low flow input is no: expected to ocour for at Ieas ore month.

- To enable this anrurdaor :o fnobon forA-l-1 B-SB low fw and the overload condition on either fan, leads il ce lifed to disable the annunciator in out from the AF-1 A-S3 ow flow output.

LAW C2S_NGGC_iOO. fleet Conouct of Op-eratiors. he anruciator should be flagged in .

lAW OPS-NGGC-3D. Plan: Szais Coryrol, 12i - :ags sicuic be placed or The ned eads.

A. (1) blue i: Caut on B. 11) blue

12) or Nc.mal

c. iyelow 12, Cauton Df fl)yellow 121 Cft Nc.mal Tuesday, March 20, 2012 3:08:20 PM 58 MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: DDDDDDDDDD Items Not Scrambled

QUESTIONS REPORT for 2012 NRC SQ V 345 DAY SUBMITTAL

97. 2OI2NRC SRO 022 Given the following plant conditions:

- The plant is in Mode 6 with core offload in progress

- A fuel assembly has just been unlatched in the Containment upender

- The Fuel Handling SRO has reported that Refueling Cavity Level is rapidly lowering

- The MCR crew has entered and is implementing AOP-031, Loss of Refueling Cavity Integrity

- The CRS has directed the fuel assembly be returned to the Reactor Vessel Prior to relatching the assembly, the following occurs:

- ALL CNMT Ventilation Isolation radiation monitors have just gone into alarm

- HP reports radiation levels on the manipulator crane of 162 mR/hr and increasing Which ONE of the following describes the required action(s) the Refueling SRO must direct lAW AOP-031?

A. Place the fuel assembly in the Reactor Vessel and evacuate ONLY unnecessary personnel B. Leave the fuel assembly in the upender and evacuate ONLY unnecessary personnel C. Place the fuel assembly in the Reactor Vessel and then evacuate ALL personnel Dv Leave the fuel assembly in the upender and evacuate ALL personnel Tuesday, March 20, 2012 3:08:20 PM 59

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL Plausibility and Answer Analysis Reason answer is correct: Leave the fuel assembly in the upender and evacuate ALL personnel due to radiation levels greater than 150 mR/hr. From AOP-031: NOTE CNMT Ventilation Isolation radiation monitors are set to alarm at less than or equal to 150 mR/hr for fuel movement.

A. Incorrect. Plausible because unnecessa,y personnel would be evacuated while others stored the fuel assembly if radiation level was less than 150 mR/hr.

B. Incorrect. Plausible because the fuel should be left in the upender due to radiation levels being greater than 150 mR/hr BUT all personnel should be evacuated.

C. Incorrect. Plausible because unnecessa,y personnel would be evacuated while others stored the fuel assembly if radiation level was less than 150 mR/hr but with radiation level greater 150 mR/hr ALL personnel should be evacuated prior to storing the fuel assembly.

0. Correct.

Tuesday, March 20, 2012 3:08:20 PM 60

QUESTIONS REPORT for 2Q12 NRC SRO REV 345 DAY SUBMITTAL 2.3 Radiation Control G2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

(CFR: 41.12 /45.9 /45.10)

Importance Rating: 3.2 3.7 Technical

Reference:

AOP-031, Step 6 RNO, Page 35, Rev. 17 References to be provided: None Learning Objective: LPAOP3-31, Loss of Refueling Cavity Integrity, Obj 4 Question Origin: Bank OIT Development Bank G2.3.14 2 Comments:

Tier/Group: T3 SRO Justification: Refuel floor SRO responsibilities MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: DDDDDDDDDD Items Not Scrambled Origin: BANK Cog Level: C/A Difficulty:

Reference:

AOP-03 I Ref. Provided: NONE Key Words:

K/Al: G2.3.12 KIA2:

Tuesday, March 20, 2012 3:08:20 PM 61

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL

98. 2012 NRC SRO 023 Given the following plant conditions:

- The plant was operating at 100%

- A Reactor Trip and SI have occurred due to a LOCA

- The crew has implemented PATH-i Which ONE of the choices below completes the following statement?

During initial response for this event, Control Room Ventilation is required to be verified aligned for (1) to limit the exposure Control Room personnel receive to a maximum dose of (2) whole body.

A (1) Emergency Recirculation (2) 5.0 rem B. (1) Emergency Recirculation (2) 2.0 rem C. (1) Post Accident Operation (2) 5.0 rem D. (1) Post Accident Operation (2) 2.0 rem Tuesday, March 20, 2012 3:08:20 PM 62

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL Plausibility and Answer Analysis Reason answer is correct: Path-i Guide attachment 6 step 18 requires the Control room ventilation be verified in Emergency recirculation. T.S. 3.7.6 bases state the OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body or its equivalent.

A. Correct.

B. Incorrect. Plausible due to the correct Progress energy administrative limt for DOS-NGGC-0005 with the correct mode of operation for control room ventilation system C. Incorrect. Plausible due to correct exposure limit per T. S. 3.7.6 bases, but the post accident mode is incorrect because this alignment is recommended by the Plant Staff following emergency recirculation alginment in order to open emergency outside air intakes.

D. Incorrect. Plausible due to the correct Progress energy administrative limt for DOS-NGGC-0005, but the post accident mode is incorrect because this alignment is recommended by the Plant Staff following emergency recirculation alginment in order to open emergency outside air intakes.

Tuesday, March 20, 2012 3:08:20 PM 63

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL 2.3 Radiation Control G2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

(CFR: 41.12/43.4/45.10)

Importance Rating: RO 3.4 SRO 3.8 Technical

Reference:

Path-i Guide, Attachment 6, Step 18, Page 82, Rev 33 References to be provided: None Learning Objective: Control Room Area Ventilation Student text, Obj 5 Question Origin: Modified Comments: New Tier/Group: T3 SRO Justification: Knowledge of tech spec bases that is required to analyze tech spec required actions and terminology MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: A A A A A A A A A A Items Not Scrambled Origin: NEW Cog Level: C/A Difficulty:

Reference:

PATH- I GUIDE Ref. Provided: NONE Key Words:

K/Al: G2.3.14 K/A 2:

Tuesday, March 20, 2012 3:08:20 PM 64

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL

99. 2012 NRC SRO 024 Which ONE of the following events requires 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> notification to the NRC lAW AP-617, Reportability Determination And Notification?

A An action which deviates from Technical Specifications must be performed B. An inadvertent Safety Injection results in ECCS discharge into the RCS C. A confirmed violation of the Fitness For Duty Program by a Progress Energy employee D. An individual is injured on site which requires the individual to be hospitalized Plausibility and Answer Analysis Reason answer is correct: Actions that deviate from Tech Specs are classifiable events, so a report to the NRC is due in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> A. Correct.

B. Incorrect. Plausible because T.S. safety limit violations is a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> report, inadvertent ECCS injection is a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> report C. Incorrect. Plausible because FFD is for a NRC employee is a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> report, Progress Energy employees FFD is a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> report D. Incorrect. Plausible because a work place incident is reportable if 3 or more personnel are hospitalized, only 1 individual is not reportable Tuesday, March 20, 2012 3:08:20 PM 65

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUMlTTAL 2.4 Emergency Procedures / Plan G2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

(CFR: 41.10 / 43.5 / 45.11)

Importance Rating: 2.7 4.5 Technical

Reference:

AP-617 page 12, Attachment 1, Rev 27 References to be provided: None Learning Objective: LPPP2-17, Routine and Emergency Reporting, Obj 4 Question Origin: Bank CIT Development G2.4.30 2 Comments: 2009A Audit SRO Tier/Group: T3 SRO Justification: The SRO must know reporting requirements for Technical Specification deviations.

MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: A A A A A A A A A A Items Not Scrambled Origin: BANK Cog Level: FUNDAMENTAL Difficulty:

Reference:

AP-617 Ref. Provided: NONE Key Words:

K/Al: G2.4.30 KIA2:

Tuesday, March 20, 2012 3:08:20 PM 66

QUESTIONS REPORT for 2012 NRC SRO REV 345 UAY SUMlTTAL 100. 2012 NRC SRO 025 Given the following plant conditions:

- The plant is in Mode 5

- RCP B is in service

- Safety Bus 1 B-SB is de-energized for a Bus Outage

- Breaker 104, AUX BUS 1 D TO EMERGENCY BUS A-SA trips open

- EDG A starts, but Breaker 106, DIESEL GEN A-SA fails to close Which ONE of the following completes the statement below?

Given the above conditions the CRS will enter (1) to trip the RCP B AND (2)

Procedure Titles:

EOP-EPP-001, Loss Of AC Power To 1A-SA And lB-SB Buses AOP-025, Loss of One Emergency AC Bus (6.9kV) Or One Emergency DC Bus (125V)

A. (1) AOP-025 (2) remain in AOP-025 B (1)AOP-025 (2) REFER to EOP-EPP-001 C. (1) EOP-EPP-001 (2) remain in EOP-EPP-001 D. (1) EOP-EPP-001 (2) REFER to AOP-025 Tuesday, March 20, 2012 3:08:21 PM 67

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL Plausibility and Answer Analysis Reason answer is correct: During the loss of power to both safety busses with the plant in cold shutdown conditions (Mode 5) AOP-025 provides the direction to correct the loss of power.

EOP-EPP-001 gives guidance to restore power back to the affected safety bus A. Incorrect. Plausible because the entry conditions for AOP-025 are met, but for this condition the procedure directs the operator to refer to EOP-EPP-OO1 for guidance to restore emergency AC power.

B. Correct.

C. Incorrect. Plausible because the entry conditions for EOP-EPP-OO1 are met, but for this condition the procedure is not applicable.

D. Incorrect. Plausible because the entry conditions for EOP-EPP--OO1 are met, but for this condition the procedure is not applicable. When EOP-EPP-OO1 is applicable AOP-025 is the procedure step in effect if power is restored to prior to implementing the EOP mitigating strategy.

Tuesday, March 20, 2012 3:08:21 PM 68

QUESTIONS REPORT for 2012 NRC SRO REV 345 DAY SUBMITTAL 2.4 Emergency Procedures I Plan G2.4.8 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

(CFR: 41.10 /43.5 /45.13)

Importance Rating: 3.8 4.5 Technical

Reference:

EOP Users Guide, Step 5.1.3, Page 11, Rev 36 and AOP-025, Step 3.0.2 RNO c, Page Rev 30.

References to be provided: None Learning Objective: LPEOP3-19, EOP Users Guide, Obj 1.b Question Origin: New Comments:

Tier/Group: T3 SRO Justification: SRO only requires assement of plant conditions and determination of procedural actions required for mitigating those events MCS Time: 1 Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9 Answer: B B B B B B B B B B Items Not Scrambled Origin: NEW Cog Level: C/A Difficulty:

Reference:

Ref. Provided: Key Words:

KJA 1: G2.4.8 K/A 2:

Tuesday, March 20, 2012 3:08:21 PM 69