Text

Initial Exam 2012-301 Draft SRO Written Exam
	ML13225A132
Person / Time
Site:	Saint Lucie
Issue date:	08/08/2013
From:	; NRC/RGN-II
To:	; Florida Power & Light Co
References
	50-335/12-301, 50-389/12-301
	Download: ML13225A132 (50)
	v • d • e

Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 025AG2.4.3 Importance Rating 3.7 3.9 Loss of RHR System Ability to identify post-accident instrumentation.

Proposed Question: SRO 76 Given the following:

Unit 1 is cooling down and has just placed SDC in service using the 1B LPSI pump.

Pressurizer pressure and level started lowering rapidly and the 1B LPSI pump was stopped.

The RCS has heated up to 340°F.

Which ONE of the following states:

1) The Tech. Spec. ACCIDENT MONITORING INSTRUMENTATION that should be used to monitor Pressurizer level?

2) Based on the current conditions, the Tech. Spec. action that is applicable if ONE CHANNEL of that instrumentation is NOT operable / available AND is unable to be restored?

A. 1) Pressurizer level transmitter LT-1110X AND LT-1110Y.

2) Be in Hot Shutdown in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

B. 1) Pressurizer level transmitter LT-1103 AND LT-1104, LT-1105.

2) Be in Hot Shutdown in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

C. 1) Pressurizer level transmitter LT-1110X AND LT-1110Y.

2) Be in Hot Shutdown in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

D. 1) Pressurizer level transmitter LT-1103 AND LT-1104, LT-1105.

2) Be in Hot Shutdown in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Proposed Answer: A

Explanation (Optional):

A. Correct, based on the stem, the Unit is already in Hot standby so 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to be in Hot Shutdown is correct.

B. LT-1103 is the Pressruizer level cold cal and LT-1104, LT-1105 supply indication for the Hot Shutdown Panel and are UNIT 2 ONLY. Not accident monitoring.

C. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months incorrect.

D. Both parts incorrect Technical Reference(s): T.S. table 3.3-11 Accident (Attach if not previously provided) monitoring Instrumentation.

1-OSP-100.17 Accident Monitoring Instrumentation Monthly Channel Check.

Proposed references to be provided to applicants during examination:

Learning Objective: PSL OPS 0702417, Terminal (As available)

Objective.

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: 41.6 45.4 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 038EA2.16 Importance Rating 4.2 4.6 Steam Generator Tube Rupture: Action to be taken if S/G goes solid and water enters steam line.

Proposed Question: SRO 77 Unit 1 is combating a LARGE SGTR on the 1B SG. All Reactor Coolant Pumps have been stopped.

1-EOP-04, Steam Generator Tube Rupture is being implemented with the following conditions:

Pressurizer pressure is 900 psia Pressurizer level is offscale low 1B SG pressure indicates 650 psia 1B SG level indicates 95% Narrow Range and slowly rising.

1B SG has been isolated IAW Appendix R Which ONE of the following is the PREFFERED method of lowering the 1B SG level to within the Safety Function range?

A. Line up the 1B SG blowdown system to the Monitored Storage Tank (MST).

B. Reducing RCS pressure to less then the SG pressure (backflow).

C. Steaming the 1B SG to the condenser.

D. Steaming the 1B SG to the atmosphere.

Proposed Answer: B

Explanation (Optional):

Per CAUTION statement in EOP-04, the only time backflow should be allowed while in natural circulation is to prevent SG level from exceeding the indicating range. Per PSL-ENG-SEIS 046: 90% narrow range is the highest reliable and measurable level that can be accepted before SG level is considered off-scale high.

A. This is a viable means, and mentioned in the EOP to lower SG level, but not the preferred method.

B. Correct C. This is a viable means, and mentioned in the EOP to lower SG level, but not the preferred method.

D. This method is also mentioned in the EOP but listed as the LEAST preferred method.

Technical Reference(s): 1-EOP-04 SGTR step 30. (Attach if not previously provided)

PSL-ENG-SEIS-01-046 Proposed references to be provided to applicants during examination:

Learning Objective: PSL OPS 0702825-12 (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 X Comprehension or Analysis 10 CFR Part 55 Content: 43.5 45.13 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 040A2.02 Importance Rating 4.6 4.7 Ability to determine and interpret the following as they apply to the Steam Line Rupture: Conditions requiring a reactor trip Proposed Question: SRO 78 Unit 2 is performing a Reactor startup following a refueling outage. The Reactor is critical with a stable power level of 6%. A positive Moderator Temperature Coefficient (MTC) exists.

SBCS valve PCV-8802 fails to the full open position. Efforts to close the valve from the control room have failed.

RCS Tave is currently 515°F and lowering.

RCS pressure is 2220 psia and lowering.

Pressurizer level is 25% and lowering.

1) Which ONE of the following would be observed that requires a manual Reactor trip?

2) When the Reactor is tripped, which ONE of the following Tech. Spec action statement applies?

A. 1) 2 of 4 high startup rate channel pre-trips illuminated.

2) Restore Pressurizer level 27% to 68% within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

B. 1) 2 of 4 high startup rate channel pre-trips illuminated.

2) Restore RCS pressure to greater than 2225 psia within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

C. 1) RCS Tave.

2) Restore Pressurizer level 27% to 68% within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

D. 1) RCS Tave.

2) Restore RCS pressure to greater than 2225 psia within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Proposed Answer: C

Explanation (Optional):

A. If a NEGATIVE MTC was applicable, this would be a possible answer. A cooldown with a positive MTC would result in a negative startup rate not positive.

B. Both parts incorrect. DNB T.S. not applicable in Mode 3.

C. Correct, RCS Tave. 515°F and lowering, with conditions indicating temperature will not be able to be restored in 15 minutes would require the Unit to be placed in a condition for which the T.S. is not applicable i.e.. Mode 3. Pressurizer level is a Mode 3 T.S. to be restored to 27% within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

D. This would be correct if the Reactor was NOT tripped. DNB is not applicable for Mode 3 conditions.

Technical Reference(s): T.S. 3.1.1.5 Reactivity Control (Attach if not previously provided)

Systems.

T.S. 3.4.3 Reactor coolant system.

T.S. 3.2.5 DNB parameters Proposed references to be provided to applicants during examination:

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: 43.5 45.13 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 055G2.4.30 Importance Rating 2.7 4.1 Station Blackout: 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.

Proposed Question: SRO 79 Given the following:

At time 0020 both Units tripped due to a LOOP (loss of offsite power)

On the trip, both Unit 1 Diesel generators failed to start and ONE Unit 2 Diesel generator is running on its respective bus.

The E-Plan classification was made at time 0025

1) Which of the following states the basis for the classification and

2) The LATEST time the NRC must be notified A. 1) Station Blackout

2) Time 0125 B. 1) Station Blackout

2) Time 0120 C. 1) LOOP

2) Time 0125 D. 1) LOOP

2) Time 0120 Proposed Answer: A

Explanation (Optional):

Question was written based on knowledge of E-Plan for Blackout.

The NRC must be notified no later than one hour after the event has been classified, not one hour after the event was initiated.

A. Correct answer Technical Reference(s): EPIP-01, Classification of (Attach if not previously provided)

Emergencies page 31 of 87 SAE SS1 Proposed references to be provided to applicants during examination:

Learning Objective: PSL 0902701-8 (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 Comprehension or Analysis X 10 CFR Part 55 Content: 43.5 45.11 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 056AA2.77 Importance Rating 4.1 4.4 Loss of Offsite Power: Ability to determine and interpret the following as they apply to the Loss of Offsite Power: Auxiliary feed pump (running)

Proposed Question: SRO 80 Unit 2 is at 100% power with the 2C Auxiliary Feedwater (AFW) Pump being out of service for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months At time 2230 the Unit tripped due to a Loss of Offsite power o The 2A Diesel generator automatically started and loaded on the bus o The 2B Diesel generator started but its output breaker failed to close At time 2231 2A and 2B Steam Generator (SG) narrow range levels indicated 17 and 20% respectively At time 2235 the 2B Diesel generator breaker was manually closed. 2A and 2B SG levels indicate 16 and 19% respectively.

1) Which ONE of the following states the Tech. Spec Action statement applicable for the 2C AFW pump?

2) Assuming NO further Operator actions, which of the following states the AFW status at time 2236?

A. 1) Restore the 2C AFW pump to operable status within 66 hours7.638889e-4 days 0.0183 hours 1.09127e-4 weeks 2.5113e-5 months .

2) The 2A AFW pump is running feeding the 2A SG. The 2B AFW pump is NOT running.

B. 1) Restore the 2C AFW pump to operable status within 66 hours7.638889e-4 days 0.0183 hours 1.09127e-4 weeks 2.5113e-5 months .

2) The 2A AFW pump is running feeding only the A SG. The 2B AFW pump is running but NOT feeding the 2B SG.

C. 1) Restore the 2C AFW pump to operable status within 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

2) The 2A AFW pump is running feeding the 2A SG. The 2B AFW pump is NOT running.

D. 1) Restore the 2C AFW pump to operable status within 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

2) The 2A AFW pump is running feeding only the A SG. The 2B AFW pump is running but NOT feeding the 2B SG.

Proposed Answer: A

Explanation (Optional):

A. T.S. action statement time correct (72 hr. action). 2B AFW not running is correct. 19% SG level starts the time delay for AFAS which is 210 seconds, so 2B AFW pump will not be running.

B. Not Correct. AFAS-1 2B AFW pump is not running.

C. T.S. action not correct.

D. T.S. action not correct and 2B AFW pump is not running.

Technical Reference(s): T.S. 3.7.1.2 (Attach if not previously provided)

LP 0711412 Proposed references to be provided to applicants during examination:

Learning Objective: PSL OPS 0702412-4 (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: 43.5 45.13 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 065AG2.1.7 Importance Rating 4.4 4.7 Loss of Instrument Air. Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

Proposed Question: SRO 81 Given the following conditions on Unit 2:

The Containment Atmosphere PARTICULATE radioactivity monitor has been out of service for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

1) If a loss of instrument air occurred after the unit was shutdown, which RCS leakage detection subsystems would be operable?

2) Based on that determination, what surveillances, if any, will be required to be performed to satisfy the RCS Leakage Detection system LCO per Ops Policy 503, Technical Specification Guidance?

A. 1) ONLY the Reactor Cavity Leakage Alarm is operable.

2) Perform an RCS leak rate OR a containment atmosphere grab sample analysis every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

B. 1) The Reactor Cavity Leakage Alarm AND the Containment Atmosphere GASEOUS Radioactivity monitor are operable.

2) Perform an RCS leak rate OR a containment atmosphere grab sample analysis every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

C. 1) ONLY the Reactor Cavity Leakage Alarm is operable.

2) Perform an RCS leak rate AND a containment atmosphere grab sample analysis every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D. 1) The Reactor Cavity Leakage Alarm AND the Containment Atmosphere GASEOUS Radioactivity monitor are operable.

2) Perform an RCS leak rate AND a containment atmosphere grab sample analysis every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Proposed Answer: A Explanation (Optional): With a loss of instrument air, the containment atmosphere radiation monitor (PIG) isolation valves (fail closed) and FR-07-3, the reactor cavity flow meter (air supplied bubbler) would be inoperable. The only operable RCS leak detection system would be the alarm (N-46) from LS-07-12 (powered from the EDGs). Per the TS and Ops Policy, an inventory balance OR containment atmosphere grab samples are all that is required - NOT BOTH.

A. Correct.

B. Incorrect. Part 1 is incorrect. Containment PIGS are not operable due to isolation valves being closed on loss of instrument air. Plausible if the candidate fails to recognize that instrument air is lost to the containment atmosphere rad monitor isol. valves. Part 2 is correct. Per the TS and Ops Policy, an inventory balance OR containment atmosphere grab samples are all that is required - NOT BOTH.

C. Incorrect. Part 1 is correct. Part 2 is incorrect. Per the TS and Ops Policy, an inventory balance OR containment atmosphere grab samples are all that is required - NOT BOTH.

D. Incorrect. Part 1 incorrect. Containment PIGS are not operable due to isolation valves being closed on loss of instrument air. Plausible if the candidate fails to recognize that instrument air is lost to the containment atmosphere rad monitor isol. valves. Part 2 is incorrect. Per the TS and Ops Policy, an inventory balance OR containment atmosphere grab samples are all that is required - NOT BOTH.

Technical Reference(s): Ops Policy 503, Unit 2 Tech (Attach if not previously Spec 3.4.6.1 provided) 0711600 Containment and Shield Bldg Proposed references to be provided to applicants during None examination:

Learning Objective: 0702413-14.a (As available)

Question Source: Bank # ILT 2049 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 10 55.43

Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 051AG2.1.20 Importance Rating 4.6 4.6 Loss of Condenser Vacuum. Ability to execute procedure steps.

Proposed Question: SRO 82 Unit 1 was operating at 100% power (1050 MW) when an influx of jellyfish occurred, causing a degradation of condenser vacuum.

At 0800, a down power is commenced at 1%/Min; condenser backpressure is 7.2 Hg.

Time Condenser Backpressure ( Hg A) MWe 0810 6.8 945 0820 6.6 840 0835 6.3 683 0850 6.1 525 Which ONE of the following states:

1) The procedural requirements of 1-AOP-12.01, Loss of Condenser Vacuum at time 0850?

2) At time 0853 Condenser Backpressure rose to 8.5 HgA. For this condition, assuming no Operator actions, an automatic Reactor trip will occur:

(References Provided)

A. 1) Continue the downpower until backpressure lowers to <5.9 inHgA.

2) immediately.

B. 1) Continue the downpower until backpressure lowers to <5.9 inHgA.

2) in 5 minutes.

C. 1) Stabilize reactor power at the current level.

2) immediately.

D. 1) Stabilize reactor power at the current level.

2) in 5 minutes.

Proposed Answer: B Explanation (Optional):

A. Incorrect. For the given conditions in part 2 the unit would be in the Restricted Operating region. An immediate automatic trip would ONLY occur if backpressure were to rise to

.8.859 HgA (prohibited operating region)

B. Correct. Attachment 4 of AOP-12.01 requires load to be reduced until backpressure is less than 5.9 HgA which is the dashed line on the figure. Part 2 is correct. Using 525 Mwe and 8.5 in HgA backpressure results in operating in the restricted operating region.

Operating in this will result in an automatic trip in 5 minutes.

C. Both parts incorrect. Power should be reduced until backpressure lowers to,5.9 HgA for the given backpressure.

D. Incorrect. First part incorrect.

Technical Reference(s): 1-AOP-12.01 Loss of (Attach if not previously Condenser Vacuum provided)

Proposed references to be provided to applicants during Attachment 4 of 1-examination: AOP-12.01 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 10 55.43 5 Comments: SRO ONLY basis (10CFR 55.43(b)(5): Using Attachment 4 (backpressure vs power data points), the SRO must determine if the unit is in an optimal condition or if other actions (e.g. a downpower) are required. For this case, the optimal operating region (per the AOP) is out of restricted Area but below the alarm line.

The SRO must assess plant conditions then select a section in the AOP and use it to recover.

Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # APE 059AA2.04 Importance Rating 3.2 3.5 Ability to determine and interpret the following as they apply to the Accidental Liquid Radwaste Release: The valve lineup for a release of radioactive liquid Proposed Question: SRO 83 Unit 1 is performing a Liquid Release of the 1A Waste Monitor Tank when the following alarm is received:

LIQUID WASTE RADWASTE LIQUID HIGHRAD HIGH N-37 Liquid release flow control valve, FCV-6627X indicates open and will not close from the RTGB.

Chemistry has reported that samples taken just offshore of the discharge canal were over 20 times the applicable concentrations specified in 10CFR20 part B.

IAW 1-AOP-06.02, Uncontrolled Release Of Radioactive Liquids which ONE of the following is a required SUBSEQUENT Operator action AND what are the reportability requirements per 10CFR50.72 and 10CFR50.73?

1) Stop the 1A Waste Monitor pump __(1)__.

2) Initiate an __(2)__.

A. 1) from the Liquid Waste Control panel, AND close FCV-6627X locally

2) LER within 60 days B. 1) locally AND lock closed V21462, Waste Monitor Pumps Discharge to Discharge Canal Isolation valve

2) LER within 60 days C. 1) locally AND lock closed V21462, Waste Monitor Pumps Discharge to Discharge Canal Isolation valve

2) Emergency Notification System (ENS) notification within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

D. 1) from the Liquid Waste Control panel, AND close FCV-6627X locally

2) Emergency Notification System (ENS) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Proposed Answer: B Explanation (Optional):

A. Incorrect. Part 1 incorrect FCV-6627X is remote operated valve only.

B. Correct. The Waste Monitor Pump control switch is located near the WMTs and V21462 is a manually operated valve located near the discharge piping (CCW pit). The reportablility criteria (60 day LER) has been met.

C. Incorrect. Part 1 correct.

D. Incorrect. Both parts incorrect.

Technical AP-0010721 (Attach if not Reference(s): previously provided) 1-AOP-06.02, Uncontrolled Release of Radioactive Liquids Proposed references to be provided to applicants during None examination:

Learning Objective: (As available)

Question Source: Bank #

Modified Bank # HLC20 (Note changes or attach (Q22) 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 5 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # APE 060AA2.02 Importance Rating 2.6 2.9 Ability to determine and interpret the following as they apply to the Accidental Gaseous Radwaste: The possible location of a radioactive gas leak with the assistance of PEO, health physics and chemistry personnel Proposed Question: SRO 84 The Waste Gas Surge Tank has been aligned to the Plant Vent for the past 180 days with the Waste Gas System taken out of service IAW 2-0530020, Waste Gas System Operation.

Unit 2 is at 100% power preparing to perform a VCT purge with Nitrogen in preparation for a refueling outage.

The SRO directed the Gas Surge Tank to be re-aligned to the 2A Gas Decay Tank for the VCT purging operation and the VCT purge to be started.

The VCT purge has been ongoing for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The SNPO reports the 2A Gas Decay Tank pressure has not changed. He also reports the 2B and 2C Gas Decay Tank pressures have not changed.

The RAB general area dose rates have not changed. (no Area Radiation Monitors are in alarm or increasing)

Which of the following should be performed?

1) Stop the VCT purge and:

2) the above condition is:

A. 1) Direct the SNPO to realign the Gas Surge Tank to the Plant Vent until a valve alignment check can be performed.

2) considered an UNPLANNED GAS RELEASE IAW C-200 ODCM.

B. 1) Direct the SNPO to realign the Gas Surge Tank to the Plant Vent until a valve alignment check can be performed.

2) NOT considered an UNPLANNED GAS RELEASE IAW C-200 ODCM.

C 1) Direct RP to perform a survey of the Waste Gas Decay Tank rooms and the SNPO to perform a valve alignment check.

2) considered an UNPLANNED GAS RELEASE IAW C-200 ODCM.

D. 1) Direct RP to perform a survey of the Waste Gas Decay Tank rooms and the SNPO to perform a valve alignment check.

2) NOT considered an UNPLANNED GAS RELEASE IAW C-200 ODCM.

Proposed Answer: D Explanation (Optional):

A. Incorrect. Alignment of the Gas Surge Tank to the plant vent cannot be authorized by the SRO. The Operations manager must authorize this lineup. The above condition is NOT considered an UNPLANNED release IAW C-200 Offsite Dose Manual. Gas Decay tank losses must be 2 psig per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for 9 consecutive shifts or 18 psig in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND losses were to the RAB, to be considered UNPLANNED RELEASE.

B. Incorrect.

C. Incorrect.

D. Correct. Appendix A, B and C of 2-0530020 Waste Gas System Operation, gives guidance for suspected leakage. NOT unplanned release as described earlier.

Technical Reference(s): 2-AOP-06.04, (Attach if not previously 2-0530020 provided) 2-AOP-06.03 C-200 Proposed references to be provided to applicants during examination:

Learning Objective: 0502019-09 (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 5 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # CA16 G2.4.50 Importance Rating 4.2 4.4 Excess RCS Leakage: Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

Proposed Question: SRO 85 Given the following conditions on Unit 2:

The unit is shutdown in Mode 3 with Reactor Coolant System (RCS) temperature at 532ºF and pressure at 2250 psia. .

A CEDM housing leak has resulted in the following annunciator:

Rx CAVITY LEAKAGE HIGH N-46 The initial determination of the RCS leak rate should be done by: __(1)__.

The Tech Spec action that applies for this event is _(2)_.

A. 1) gross Charging and Letdown mismatch

2) be in COLD SHUTDOWN within 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months B. 1) observing FR-07-03, Reactor Cavity Leakage Flow

2) be in COLD SHUTDOWN within 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months C. 1) gross Charging and Letdown mismatch

2) reduce the leakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months D. 1) observing FR-07-03, Reactor Cavity Leakage Flow

2) reduce the leakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

Proposed Answer: A Explanation (Optional): The RCS leakage for this question is pressure boundary leakage. With the unit in Mode-3 (Hot Standby), additional time cant be taken for the LCO action of be in Hot Standby within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . The action that applies is to be in Cold Shutdown within 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

A. Correct. Compare the Chg/LD flow mismatch. The RCS leakage is pressure boundary so actions must begin immediately to comply with the TSAS.

B. Incorrect. Part 1 is partially correct in that starting a 2nd Chg pp is listed as an action to take in 2-AOP-01.08 but FR-07-03 is not mentioned in 2-AOP-01.08 for determining leak rates. Since the RCS leak is on the Pzr reference leg, it will be steam initially and then condense several minutes later (i.e. true leak rate wont be indicated initially). Part 2 is correct C. Incorrect. Part 1 is correct. Part 2 is incorrect. This is the TSAS for unidentified leakage.

D. Incorrect. Part 1 is partially correct. See B part 1. Part 2 is the TSAS for RCS unidentified leakage.

Technical Reference(s): 2-ARP N-46, RCS Leakage (Attach if not previously TS 3.4.6.2 provided) 0711600 Containment Bldg Proposed references to be provided to applicants during None examination:

Learning Objective: 0702600 (As available)

Question Source: Bank #

Modified Bank #

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 10 55.43 5 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 003G2.4.6 Importance Rating 3.7 4.7 Reactor Coolant Pump: Knowledge of EOP mitigation strategies Proposed Question: SRO 86 Unit 1 has experienced a LOCA with the following conditions:

At time 0006 the Unit tripped At time 0021 RCS pressure indicated 1580 psia and the crew entered 1-EOP-03, LOCA.

The current time is 0053.

Which ONE of the following states the procedural actions that are taken to ensure equipment reliability and maintainability of the RCPs.

A. Verify CCW to the RCPs and the alternate RCP bleedoff flow has been established.

B. Ensure CCW remains isolated by placing the four CCW Containment isolation valves To/From the RCPs to close.

C. Ensure the RCPs are off and remove the RCP breaker trip and close fuses.

D. Verifying RCP NPSH requirements are met in accordance with EOP-99 Figure 1A or 1B, RCS Pressure Temperature.

Proposed Answer: B Explanation (Optional):

A. Incorrect: This action is performed in other EOPs that have NOT received a VALID SIAS.

For invalid SIAS these actions are performed.

B. Correct. Stated conditions (1580 psia) indicates SIAS. Time of 0053 is 32 minutes after SIAS. EOP-03 states is if CCW lost for >30 minutes perform the actions as stated. Bases for these actions are defined in the PSTG for EOP-03 which states actions that are taken to ensure equipment reliability and maintainability of the RCPs.

C. Incorrect. This action is performed in EOP-04, SGTR to disable the RCPs associated with the isolated SG.

D. Incorrect. Verifying RCP NPSH is performed in other EOPs when the RCPs are operating.

Technical Reference(s): 1-EOP-03 LOCA (Attach if not previously 1-PSTG-03 LOCA provided)

Proposed references to be provided to applicants during None examination:

Learning Objective: 0702824-18 (As available)

Question Source: Bank #

Modified Bank # modified 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 10 55.43 5 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 006A2.13 Importance Rating 3.9 4.2 ECCS. Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Inadvertent SIS actuation Proposed Question: SRO 87 Given the following conditions on Unit 2:

The unit is operating at 90% power.

The AB bus is aligned to the B train.

The 2A Charging and 2B Charging pumps are operating. The 2C Charging pump is in Standby.

The following annunciator has just alarmed due to a relay failure in the SA ESFAS Actuation Cabinet:

SIAS CHANNEL A/B ACTUATION R-6 ONLY the Chg and Letdown systems were affected by the SIAS actuation signal.

Assume immediate Operator actions have been taken In accordance with 2-AOP-69.01, Inadvertent ESFAS Actuation.

_____(1)_____ control switch should be in AUTO.

This event, per AP 00010721, NRC Required Non-Routine Notifications and Reports, __(2)__.

A. 1) All three Charging pumps

2) is not reportable B. 1) All three Charging pumps

2) would require a 60 day LER C. 1) The 2B and 2C Charging pumps

2) is not reportable D. 1) The 2B and 2C Charging pumps

2) would require a 60 day LER

Proposed Answer: D Explanation (Optional): On Unit 2, the 2C Chg pump gets an SIAS auto start signal ONLY if it is aligned electrically to the same train that the non-running Chg pp (either A or B Chg pps) is AND the non-running Chg pps control switch is in STOP. The AOP provides guidance to secure Chg early (if letdown is isolated) to avoid an uncontrolled pressurizer level rise. This event would require notification even though the SIAS was inadvertent by definition but it DOES NOT meet the non-reportable conditions of 10CFR50.73 for a 60 day LER.

A. Incorrect.

B. Incorrect.

C. Incorrect.

D. Correct. Since no B SIAS occurred, the 2B Chg pp can be maintained in AUTO and not be running (due to SIAS). Since the 2C Chg pp is aligned electrically to the B train and the 2A Cgh pp is running (per the conditions in the stem, the 2C Chg pp would be in standby with the control switch in AUTO) it will not receive a SIAS auto start signal. Part 2 is the correct notification since the SIAS was inadvertent by definition and did not meet the non-reportable conditions of 10CFR50.73.

Technical Reference(s): 1-AOP-69.01 (Attach if not previously provided)

AP 0010721 Proposed references to be provided to applicants during examination:

Learning Objective: (As available)

Question Source: Bank #

Modified Bank #

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 5 55.43 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 061A2.05 Importance Rating 3.1 3.4 Auxiliary/Emergency Feedwater. Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Automatic control malfunction.

Proposed Question: SRO 88 Given the following conditions on Unit 1:

The unit is at 100% power The 1C Auxiliary Feedwater Pump (AFW) is out of service.

Time 10:00:00: a unit trip occurs.

10:03:00: both Steam Generators (SGs) NR levels were observed to be <15% on all safety channels.

10:07:15: prior to any Operator actions, the RCO reports that ONLY AFAS-2 has actuated.

10:12:00: the crew exited 1-EOP-01 SPTAs Which ONE of the following states why AFAS-1 did not actuate and what procedure would be entered?

1) AFAS-1 did not actuate due to a malfunction of the ____.

2) The crew should enter 1-EOP-02 Post Trip recovery AND use the guidance in ____.

A. 1) time delay relay failure.

2)1-AOP-09.02 Auxiliary Feedwater to manually actuate AFAS-1 B. 1) AFAS-1 lockout relay actuation.

2)1-AOP-09.02 Auxiliary Feedwater to manually actuate AFAS-1 C. 1) time delay relay failure.

2)1-NOP-09.02 Auxiliary Feedwater System Operation and cross-tie the AFW headers to feed both SGs with the 1B AFW pump.

D. 1) AFAS-1 lockout relay actuation.

2)1-NOP-09.02 Auxiliary Feedwater System Operation and cross-tie the AFW headers to feed both SGs with the 1B AFW pump.

Proposed Answer: A Explanation (Optional):

A. Correct. The time delay failed on AFAS-1. Both AFAS-1 & 2 shouldve worked. There are no rupture ID factors. The AFAS lockout relay only affects cycling components. AOP-09.02 DOES have guidance for manually actuating AFAS if it shouldve actuated but didnt.

B. Incorrect. The AFAS lockout relay only affects cycling components. For this question, NONE of the A train AFW components responded. Part 2 is true.

C. Incorrect. Part 1 is not correct. NOP-09.02 does have guidance to cross-tie AFW but only under NORMAL conditions. There is a caution about not opening the AFW header cross-tie valves as this will render both AFW headers inoperable (TSAS 3.0.3 applies).

D. Incorrect. Part 1 is true but part 2 is false.

Technical Reference(s): Ops Policy 521 (Attach if not previously provided) 1-AOP-09.02, Auxiliary Feedwater Proposed references to be provided to applicants during examination:

Learning Objective: 0702412 Obj. 3b, 4b (As available)

Question Source: Bank # X .

Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam HLC20 (Q90)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments: Changed Distractor C&D, Made the correct answer be A.

Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 062 G2.2.3 Importance Rating 3.8 3.9 AC Electrical Distribution. (multi-unit license) Knowledge of the design, procedural and operational differences between units.

Proposed Question: SRO 89 Given the following conditions:

A 120 Vital AC Instrument Bus has just de-energized due to an internal fault in its inverter.

The affected instrument bus has been aligned to a shared maintenance bypass bus via the maintenance bypass bus transfer switch located on the Instrument Bus Transfer Panel.

For the actions that were taken, this event has occurred on __(!)__.

For the current conditions, the Tech Spec Action is __(2)__.

(Assume Mode 1)

A. 1)Unit 2

2) with the instrument inverter not connected to its associated DC bus, re-energize the Instrument bus from its associated inverter and DC bus within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months B. 1) Unit 2

2) complete; the instrument bus may remain in the current alignment indefinitely C. 1) Unit 1

2) with one instrument inverter not connected to its associated DC bus, re-energize the Instrument bus from its associated inverter and DC bus within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months D. 1) Unit 1

2) complete; the instrument bus may remain in the current alignment indefinitely

Proposed Answer: C Explanation (Optional): Unit 1 has a maintenance bypass bus (shared between two instrument busses) and transfer switch. Unit 2s instrument busses have their own isolimeters for use when the inverter must be taken OOS.

A. Incorrect. Part 1 wrong. Part 2 correct (see explanation in C).

B. Incorrect. Part 1 wrong. Part 2 wrong.

C. Correct. Even though Unit 1 TSs dont have a specific TSAS for restoring the inverter and re-aligning the instrument bus to the inverter and DC bus, Unit 2 does and per OPS Policy 503, Unit 1 applies the Unit 2 requirement of 24 hrs to restore the inverter to operable status.

D. Incorrect. Part 1 correct. Part 2 wrong.

Technical Reference(s): TS 3.8.2.1 (Attach if not previously provided)

NOP-49.05 Proposed references to be provided to applicants during examination:

Learning Objective: 0702503-9, 13, 6b (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 5,6,7,10 55.43 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 073A2.02 Importance Rating 2.7 3.2 Process Radiation Monitoring. 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: SRO 90 The following Unit 1 Control Room Outside Air Intake (CROAI) Radiation Monitor has failed high:

RIS-26-84, North CROAI Train SA Which ONE of the following states the response of the CROAI Intake ducts?

1) ____ CROAI intake duct(s) isolate(s).

2) The required actions would be to enter ____.

A. 1) BOTH the North and South

2) 1- NOP-25.07, Control Room Ventilation System Infrequent Operations section to align and operate the Control Room Ventilation system in the recirculation mode.

B. 1) ONLY the North

2) 1- NOP-25.07, Control Room Ventilation System Infrequent Operations section to align and operate the Control Room Ventilation system in the recirculation mode.

C. 1) BOTH the North and South

2) 1-AOP-25.02 Ventilation Systems Attachment 4, Control Room Ventilation Recirculation Mode and ensure the CROAI system recirculation mode alignment exists D 1) ONLY the North

2) 1-AOP-25.02 Ventilation Systems Attachment 4, Control Room Ventilation Recirculation Mode and ensure the CROAI system recirculation mode alignment exists

Proposed Answer: C Explanation (Optional): The CROAI rad monitors are arranged in the following manner: one SA channel and one SB channel in the North intake and one SA channel and one SB channel in the South intake. The TS minimum operable channel requirement is for at least one channel (either SA or SB) in EACH intake to be operable. An SA channel rad monitor in alarm will cause the A CROAI train to go on recirc (The SA train valves close in each intake duct).1-AOP-25.02 contains guidance for responding to a valid rad alarm causing CR recirc actuation (attachment 4). In this case, with only 1 detector failed in one intake duct, the minimum equipment operability LCO is met. The AOP would be used to verify the correct lineup for recirculation mode. The control room would stay on recirc until the failed detector was jumpered out by I&C.

A. Incorrect. The first part is true (refer to explanation above). This is the action to take with one below the minimum operable channel requirement of required detectors (i.e. manually operate and maintain the control room on recirc).

B. Incorrect. Part 1 wrong. An SA channel rad monitor in alarm will cause the A train to go on recirc and cause the SA train isolation valves to close in each intake duct. Part 2 is wrong.

(see A explanation).

C. Correct. Part 1 correct. Part 2 correct. The AOP would be used verify the correct line up for recirculation mode.

D. Incorrect. Part 1 wrong (see A explanation). Part 2 correct (see C explanation).

Technical Reference(s): TS 3.3.3.1 Table 3.3.6 (Attach if not previously AOP-25.02 provided) 1-NOP-25.07 0711410 Unit1 RMS Proposed references to be provided to applicants during examination:

Learning Objective: 0702410-5,10 (As available)

Question Source: Bank #

Modified Bank # See attahed 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 5 55.43 5 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 014A2.04 Importance Rating 3.4 3.9 Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Misaligned rod Proposed Question: SRO 91 Unit 1 is at 100% power. All CEAs were at 136 when CEA 56 slipped, indicating 115 on the CEAPDS.

Efforts to re-align CEA 56 have been ongoing for 60 minutes, but CEA 56 still indicates 115.

Which ONE of the following states:

1) CEA 56 position indication on the DCS.

2) The procedure requirements of 1-AOP-66.01, Dropped or Misaligned CEA Abnormal Operations A. 1) DCS would indicate 136

2) Continue efforts to re-align CEA 56 while concurrently reducing power to 70% IAW 1-AOP-22.01, Rapid Downpower B 1) DCS would indicate 136

2) Suspend efforts to re-align CEA 56 and reduce power to 70% IAW 1-AOP-22.01, Rapid Downpower C. 1) DCS would indicate 115

2) Continue efforts to re-align CEA 56 while concurrently reducing power to 70% IAW 1-AOP-22.01, Rapid Downpower D. 1) DCS would indicate 115

2) Suspend efforts to re-align CEA 56 and reduce power to 70% IAW 1-AOP-22.01, Rapid Downpower Proposed Answer: B

Explanation (Optional):

A. First part correct, DCS is pulse count system. Because the CEA slipped the DCS only recognizes the UEL position. Second part incorrect. The maximum time to re-align IAW the COLR curve is 60 minutes. IAW Attachment 3 of 1-AOP-22.01, efforts must be stopped to re-align and perform a rapid downpower to 70%.

B. Correct C. Both parts incorrect D. First part incorrect, second part correct Technical Reference(s): T.S. 3.1.3.1 Movable Control (Attach if not previously provided)

Assemblies 1-AOP-66.01, Dropped or Misaligned CEA Abnormal Operations, Attachment 1 Proposed references to be provided to applicants during examination:

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:

41.5 / 43.5 / 45.3 / 45.13 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 028A2.02 Importance Rating 3.5 3.9 Hydrogen Recombiner and Purge Control System (HRPS) Malfunctions or operations on the HRPS; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: LOCA condition and related concern over hydrogen.

Proposed Question: SRO 92 Unit 1 has entered 1-EOP-03, LOCA with the following conditions:

Containment pressure is 12 psig.

All Containment coolers and Containment Spray pumps are operating.

Containment Hydrogen concentration is 4.5%

The Technical Support Center (TSC) is fully manned and plant conditions have been communicated to the TSC.

Which ONE of the following states the status of the Containment Temperature & Pressure Safety function AND when should the H2 purge system or Hydrogen Recombiners be placed in service?

1) Containment Temperature & Pressure Safety function is:

2) The H2 purge system or Hydrogen Recombiners should be placed in service:

A. 1) MET

2) only as directed by the Technical Support Center.

B. 1) MET

2) when the Unit Supervisor deems it necessary based on the Containment Hydrogen concentration.

C. 1) NOT MET

2) only as directed by the Technical Support Center.

D. 1) NOT MET

2) when the Unit Supervisor deems it necessary based on the Containment Hydrogen concentration.

Proposed Answer: C

Explanation (Optional):

NOTE: The 4.5% Hydrogen Concentration is plausible because In EOP-15, Functional Recovery, if Hydrogen Concentration is >3.5% the Safety Function for Containment Temperature and Pressure will be met if the TSC is notified. EOP-15 does not mention or require Hydrogen Purge OR Recombiners to be placed in service.

A. Safety Function is not met due to Hydrogen Concentration >3.5%. (If EOP-15, the Safety Function would be met at >3.5% IF the TSC is notified).

B. The Unit Supervisor cannot direct the Purge or Recombiner be placed in service without TSC guidance / concurrence. (step 48 in EOP-03)

C. Correct D. The Unit Supervisor cannot direct the Purge or Recombiner be placed in service without TSC guidance / concurrence. (step 48 in EOP-03)

Technical Reference(s): 1-EOP-03, LOCA (Attach if not previously provided)

PSL OPS 0711824 Proposed references to be provided to applicants during examination:

Learning Objective: 0702824-19 (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:

41.5 / 43.5 / 45.3 / 45.13 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 071G2.1.27 Importance Rating 3.9 4.0 Waste gas disposal : Knowledge of system purpose and or function Proposed Question: SRO 93 Which ONE of the following states:

1) The Tech Spec bases for the quantity of radioactivity for each Waste Gas Decay Tank?

2) The Tech Spec LCO for Oxygen concentration (by volume) in the Waste Gas Decay tank if Hydrogen concentration exceeds 4% (by volume).

A. 1) The number of curies of noble gas is limited for each tank based on limiting the dose rates in the RAB to acceptable levels.

2) Maximum of 2% Oxygen.

B. 1) The number of curies of noble gas is limited for each tank based on limiting the dose rates in the RAB to acceptable levels.

2) Maximum of 4% Oxygen.

C. 1) The number of curies of noble gas is limited for each tank based on limiting the dose at the exclusion boundary in the event of an uncontrolled release.

2) Maximum of 2% Oxygen.

D. 1) The number of curies of noble gas is limited for each tank based on limiting the dose at the exclusion boundary in the event of an uncontrolled release.

2) Maximum of 4% Oxygen.

Proposed Answer: C

Explanation (Optional):

A. First part not correct but plausible in that UFSAR section 15.7.4.1.1.2 states an uncontrolled release would be detected by the area radiation monitor in the area of the tanks (RAB).

Second part incorrect. Oxygen limited to 2% with Hydrogen at >4%.

B. First part not correct. Second part correct C. Correct D. First part correct. Second part incorrect Technical Reference(s): T.S. 3.11.2.5 and 3.11.2.6 (Attach if not previously provided)

T.S. Bases 3/4.11.2.5 and 3/4.11.2.6 Gas Storage Tanks Proposed references to be provided to applicants during examination:

Learning Objective: PSL OPS ADM 703-A.1 (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: 41.7 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #

K/A # G2.1.31 Importance Rating 4.6 4.3 Conduct of Operations: Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

Proposed Question: SRO 94 Unit 2 has tripped due to a LOOP. The 2A Diesel Generator did not start but the 2B Diesel Generator started and loaded on the 2B3 4.16KV bus.

1) Prior to formal implementation of 2-EOP-01, Standard Post Trip Actions which of the following would be expected for operation of the Atmospheric Dump valves?

2) Which of the following actions is the Unit Supervisor ALLOWED to take while implementing 2-EOP-01?

A. 1) One ADV on the A side operated in AUTO / AUTO from the PACB and one ADV on the B side operated in AUTO / AUTO from RTGB 202.

2) Approach the control board to visually determine if the ADV configuration is correct.

B. 1) One ADV on the A side operated in AUTO / AUTO from the PACB and one ADV on the B side operated in AUTO / AUTO from RTGB 202.

2) Perform a peer check while the RCO is lining up the ADVs.

C. 1) One ADV on the A side operated in MANUAL / MANUAL from RTGB 202 and one ADV on the B side operated in AUTO / AUTO from RTGB 202.

2) Approach the control board to visually determine if the ADV configuration is correct.

D. 1) One ADV on the A side operated in MANUAL / MANUAL from RTGB 202 and one ADV on the B side operated in AUTO / AUTO from RTGB 202.

2) Perform a peer check while the RCO is lining up the ADVs.

Proposed Answer: A

Explanation (Optional):

A. Correct. With the given conditions, one ADV on the A side is powered from the B diesel from the PACB and one ADV on the B side is powered from the B diesel from RTGB 202. Per Ops policy 521, the US is allowed to approach the RTGB when necessary to get a closer look at indications needed to make decisions. Unit Supervisors are not allowed to perform peer checks when they have the watch. They CAN perform peer checks if they are an extra operator.

Technical Reference(s): PSL OPS 0711304 (Attach if not previously provided)

OPS 521 Emergency Operating Procedure Implementation Proposed references to be provided to applicants during examination:

Learning Objective: PSL OPS 0702304-5 (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: 41.10 45.12 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #

K/A # G2.2.11 Importance Rating 2.3 3.3 Equipment Control: Knowledge of the process for controlling temporary design changes.

Proposed Question: SRO 95 Unit 1 is in Mode 3, Normal operating temperature and pressure.

The solenoid vent valve failed open causing HCV-14-1, CCW to the RCPs to close.

1-NOP-01.02, Reactor Coolant Pump Operation section 5.2, Local Restoration of CCW to RCPs is being performed to re-open HCV-14-1.

Which ONE of the following states ALL the actions necessary to control this process PRIOR TO the solenoid vent valve repair?

A. Perform an operability test of HCV-14-1 per OP-1-0010125A, Surveillance Data Sheets once HCV-14-1 is opened.

B. Document temporary hose connection IAW ADM-17.18, Temporary Modifications.

C. Document temporary hose connection IAW ADM-17.18, Temporary Modifications AND follow the Tech. Spec. actions due to HCV-14-1 not closing in the event a SIAS were to occur.

D. Document temporary hose connection IAW ADM-17.18, Temporary Modifications AND once HCV-14-1 is opened perform operability test per OP-1-0010125A, Surveillance Data Sheets.

Proposed Answer: C

Explanation (Optional):

A. OP-1-0010125A, Surveillance Data Sheets (stroke timing the valve closed) is performed AFTER HCV-14-1 is returned to normal operation. (Step 5.2.D of procedure).

B. Partially Correct, however the valve will not close on SIAS due to unable to vent through failed solenoid. (normally fail closed valve on loss of air)

C. Correct. Because the solenoid vent failed, the valve is unable to be closed on SIAS. The Tech. Spec. actions are applicable.

D. Valve stroke testing is not performed until AFTER valve returned to service.

Technical Reference(s): 1-NOP-01.02, ;Reactor Coolant (Attach if not previously provided)

Pump Operation Proposed references to be provided to applicants during examination:

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:

41.10 / 43.3 / 45.13 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #

K/A # G2.2.20 Importance Rating 2.6 3.8 Equipment Control: Knowledge of the process for managing troubleshooting activities.

Proposed Question: SRO 96 Unit 1 is in Mode 6 performing a core re-load.

An underload condition occurred while attempting to lower a spent fuel bundle into the core.

As Refueling Supervisor, which ONE of the following would you direct to troubleshoot this condition?

A. Conduct the troubleshooting process as described in 1-NOP-67.04, Refueling Machine Operation.

B. Initiate a NPWO IAW ADM-0010432 Control of Plant Work Orders for the equipment vendor to conduct an alignment check of the Refueling Machine.

C. Contact Mechanical Maintenance and the equipment vendor and perform 0-GMP-21 Troubleshooting Process D. Implement NAP-412, Operational Decision Making and gather an Operational Decision Making team to determine the course of action.

Proposed Answer: A

Explanation (Optional):

A. Correct, Attachment 1 of 1-NOP-67.04, Refueling Machine Operation is specifically written to correct an underload condition.

B. Because the guidance is provided for this condition, in a FRG approved procedure, the NPWO process is not required however the NPWO procedure does address the troubleshooting process, normally for equipment that has been removed from service.

C. Same reason as B D. Plausible, as this process could be performed if Attachment 1 of 1-NOP-67.04 is not successful and other courses of action, outside of procedure guidance are contemplated.

Attachment 1 will be performed.

Technical Reference(s): 1-NOP-67.04, Refueling (Attach if not previously provided)

Machine Operation ADM-0010432 Control of Plant Work Orders 0-GMP-21 Troubleshooting Process NAP-412, Operational Decision Making Proposed references to be provided to applicants during examination:

Learning Objective: PSL OPS 0702211-13 (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 X Comprehension or Analysis 10 CFR Part 55 Content:

41.10 / 43.5 / 45.13 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #

K/A # G2.3.12 Importance Rating 3.2 3.7 Radiation Control: 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.

Proposed Question: SRO 97 Unit 1 performed a down power and manually tripped the Unit at 0700 on August 6, 2012 in preparation for a refueling outage.

Which ONE of the following states:

1) The EARLIEST time that Tech. Specs state fuel movement within the reactor pressure vessel can be performed.

2) The Tech. Spec basis for this time A. 1) 0700 August 9, 2012

2) fuel handling accident analysis assumes the radioactive decay of the short lived fission products.

B. 1) 0700 August 9, 2012

2) fuel handling accident analysis assumes 99% of the assumed gas gap activity released to have decayed.

C. 1) 0700 August 13, 2012

2) fuel handling accident analysis assumes the radioactive decay of the short lived fission products D. 1) 0700 August 13, 2012

2) fuel handling accident analysis assumes 99% of the assumed gas gap activity released to have decayed.

Proposed Answer: A

Explanation (Optional):

(NOTE: Justification for SRO level and K/A/ match: Last NRC SRO exam, Q-97, has exact same K/A. Question asked minimum level in reactor vessel to move fuel and the basis for this minimum level. Although this question is different it has the same flavor.)

A. Correct, B. The basis for the stated time is incorrect. This basis (an incorrect variation) is for the minimum water level to move spent fuel assuming a fuel handling accident.

C. Seven (7) days is incorrect. Seven days is the T.S. surveillance time for verification of Containment isolation if moving recently irradiated fuel. (T.S. 3.9.9)

D. Both incorrect as reasons previously stated.

Technical Reference(s): T.S. bases attachment 11 of (Attach if not previously provided)

ADM-25.04 section 3/4.9.

T.S. 3.9.3 Proposed references to be provided to applicants during examination:

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:

41.12 / 45.9 / 45.10 Comments:

Tier # 3 Group #

K/A # G2.3.15 Importance Rating 2.9 3.1 Radiation Control: Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Proposed Question: SRO 98 Unit 2 is at 100% power. At 0030 on April 3, 2012 the Unit 2, 2B SG, RM-80 for the Main Steam Line radiation monitor was not communicating with the PC-11 in the Control Room.

At time1300 on April 3, 2012, the RM-23P was installed locally for the 2B Main Steam Line monitor IAW 2-NOP-26.01, Radiation Monitors The Tech. Spec. Action Statement for the Main Steam line monitor:

A. was NOT met because the RM-23P was not installed within the Tech. Spec. Action statement time requirements.

B. NOT met because the RM-23P is not powered from a Vital bus, thus it would not be available in the event of a LOOP / SGTR.

C. is met because the RM-23P was installed within the Tech Spec Action statement time requirement AND the RM-23P meets the preplanned alternate method of monitoring.

D. is met because the RM-23P was installed within the Tech Spec Action statement time requirement AND the RM-23P meets the operability requirements so NO preplanned alternate method of monitoring is required.

Proposed Answer: C

Explanation (Optional): T.S action statement for Main Steam Line radiation monitor out of service is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or initiate a preplanned alternate method of monitoring. Because the RM-80 is not communicating with the PC-11 in the Control Room, no indication or alarms will be available from the MS Rad. monitor to the Control room. The actual radiation monitor is still available. Installing the RM-23P to the remote RM-80 junction box located in the Turbine switchgear room allows local readings to be taken of MS line radiation. This satisfies the T.S.

requirement for preplanned alternate method of monitoring the MS line radiation.

(Ref: OPS-503, Operations Dept. Policy, T.S. guidance, section 3/4.3.3 page 9 of 37).

Given the information in the stem, the monitor was out of service for 121/2 hours, less than the 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action statement. A & B incorrect.

D is not correct in that installing the RM-23P locally does not comply with the original design criteria in that the Control Room will not receive readings or alarms associated with the MS line radiation.

Only Local readings are available which will satisfy the preplanned alternate method of monitoring the MS line radiation.

Technical Reference(s): T.S. 3.3.3.1 Action 27 (Attach if not previously provided)

PSL OPS 0711411 2-NOP-26.01, Radiation Monitors Proposed references to be provided to applicants during examination:

Learning Objective: PSL OPS 0702411-9 (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:

41.12 / 43.4 / 45.9 Comments:

Tier # 3 Group #

K/A # G2.4.12 Importance Rating 4.0 4.3 Emergency Procedures / Plan: Knowledge of general operating crew responsibilities during emergency operations.

Proposed Question: SRO 99 At time 0021, Unit 2 evacuated the Control Room due to a fire. 2-ONP-100.02, Control Room Inaccessibility is in progress.

At time 0034 critical actions from all Appendices are reported complete.

Which ONE of the following states the responsibilities of:

1) Shift Manager (SM)

2) RCO A A. 1) Report to Unit 1 Control Room and classify the event as Alert

2) Establish communications with the HSP from the AFW area and perform actions as directed by the US.

B. 1) Report to Unit 1 Control Room and classify the event as Site Area Emergency

2) Establish communications with the HSP from the AFW area and perform actions as directed by the US.

C. 1) Report to Unit 1 Control Room and classify the event as Alert

2) Establish communications with the SM and monitor plant parameters on the HSP.

D. 1) Report to Unit 1 Control Room and classify the event as Site Area Emergency

2) Establish communications with the SM and monitor plant parameters on the HSP.

Proposed Answer: C

Explanation (Optional):

Because the critical actions from the Appendices are complete before the required 15 minutes the E-Plan classification is Alert. If >15 minutes the classification is SAE. (Ref. page 11 NOTE under step 6.1, Operator Actions)

RCO A mans the HSP and establishes communications with the SM. RCO B is stationed at the AFW area and establishes communications with the HSP.

Technical Reference(s): 2-ONP-100.02, Control Room (Attach if not previously provided)

Inaccessibility PSL OPS 0702864 Proposed references to be provided to applicants during examination:

Learning Objective: PSL OPS 0702864-B.1.b (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

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

41.10 / 45.12 Comments:

Examination Outline Cross-reference: Level RO SRO Tier # 3 Group #

K/A # G2.4.46 Importance Rating 4.2 4.2 Emergency Procedures / Plans: Ability to verify that the alarms are consistent with the plant conditions.

Proposed Question: SRO 100 Unit 1 has completed 1-EOP-01, Standard Post Trip Actions.

The Unit supervisor is analyzing Chart 1, Diagnostic Flow Chart, to determine the subsequent EOP to enter.

The following indications and alarms are observed:

Containment pressure is 0.1 psig.

RCS pressure is 1580 psia and rising.

1B SG Blowdown monitor and Air Ejector radiation monitor alarms are in.

Main Steam Line radiation monitors are NOT in alarm.

A Steam Safety valve was open and has reseated on the 1A SG. 1A SG pressure lowered to 580 psia and is now 700 psia and rising.

1B SG pressure is 800 psia and stable.

RCS Thot is 513°F and rising.

1) Which of the following states the SG that is the MOST AFFECTED?

2) What EOP will be implemented after 1-EOP-01?

A. 1) 1A SG

2) 1-EOP-04, SGTR.

B. 1) 1A SG

2) 1-EOP-15, Functional Recovery.

C. 1) 1B SG

2) 1-EOP-04, SGTR.

D. 1) 1B SG

2) 1-EOP-15, Functional Recovery.

Proposed Answer: B

Explanation (Optional):

NOTE: Chart 1, diagnostic flow chart analyzes Steam Plant Activity above alarm setpoints or rising. Main Steam line monitors NOT in alarm is expected for the given conditions in that when the reactor is tripped N16 is gone. Ops Policy OPS-521 section 1.M.2, states a SG with a previously stuck open MSSV is considered faulted until the MSSV is gagged OR the SG is isolated IAW Appendix R.

For duel events, ESD and SGTR, the most affected SG is always the SG with the ESD.

(Ref. CAUTION statement on page 95 of 1-EOP-15)

Until MSSV is gagged, the 1A SG is considered the most faulted. This event is a duel event due to 1B SG secondary activity and 1A SG MSSV.

Technical Reference(s): 1-EOP-15, Functional Recovery (Attach if not previously provided)

OPS-521 EOP Implementation Proposed references to be provided to applicants during examination:

Learning Objective: 0702828-7A (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:

41.10 / 43.5 / 45.3 / 45.12 Comments:

ML13225A132

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