ML111540044

Initial Exam 2011-301 Draft SRO Written Exam

ML111540044
Person / Time
Site:	Saint Lucie
Issue date:	04/18/2011
From:	NRC/RGN-II
To:	Florida Power & Light Co
References
50-335/11-301, 50-389/11-301
Download: ML111540044 (50)

Text

Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 KIA# 008G2.4.11 Importance Rating 4.2 Pressurizer Vapor Space Accident: Knowledge of abnormal condition procedures.

Proposed Question: SRO 76 Unit 1 is in Mode 3, with the Reactor Coolant System (RCS) at Shutdown Cooling entry conditions when the following was observed:

• Annunciator H-28, PZR RELIEF LINE TEMP HIGH goes into alarm and RCS pressure indicates 260 psia and slowly lowering.

• TIA-1 106, RELIEF VALVE, indicates 285°F and rising.

• Pressurizer level is 29% and slowly lowering.

1-AOP-01 .08, RCS Leakage Abnormal Operations has been entered. The safety function status checks are being assessed for 1-ONP-01.01, Plant Condition 1, Steam Generator Heat Removal LTOP Not In Effect.

18 minutes have now elapsed since the above actions were commenced.

The DRCO reports that Pressurizer (Pzr) Level is still lowering and RCS minimum subcooling is not being maintained.

Which ONE of the following states which procedure to implement and the required actions?

A. Remain in 1-AOP-01 .08 and implement Attachment 7, Adding Emergency Makeup to RCS section 2.0 Makeup using HPSI.

B. Remain in 1-AOP-01.08 and implement Attachment 7, Adding Emergency Makeup to RCS section 3.2 Makeup using LPSI Forced Injection.

C. Exit 1-AOP-01.08 and enter 1-ONP-01.01. Implement RCS Inventory Control success path 2 SI and initiate SI flow to restore Pzr level D. Exit 1-AOP-01.08 and enter 1-ONP-01.01. Implement RCS Inventory Control success path I CVCS and manually control Charging and Letdown to restore Pzr level.

Proposed Answer: C 151

Explanation (Optional):

A. Correct, RCS leakage is one of 6-8 AOPs that direct Safety Functions verified from applicable Low Mode ONP (SIAS blocked), every 15 minutes while carrying out the applicable steps of the optimal AOP.

B. Safety Functions are analyzed concurrently while implementing optimal AOP. If Safety Functions are NOT met then optimal AOP is exited and the Low Mode AOP is fully implemented.

C. Plausible, as the applicant must know which AOPs direct Safety Functions to be analyzed. Pressurizer Pressure and Level is NOT one of those AOP.

D. Incorrect optimal AOP and incorrect implementation strategy of Low Mode AOP.

Technical Reference(s): 1-AOP-O1.1O, Pressurizer (Attach if not previously provided)

Pressure and Level.

1-AOP-01.08, RCS Leakage Abnormal Operations 1-ONP-01.01, Plant Condition I Steam Generator Heat Removal LTOP Not in Effect Proposed references to be provided to applicants during examination:

Learning Objective: PSL OPS 0702858 Obj. 1, 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 41.10 43.5 45.13 Comments:

152

Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 K/A # 029G2.4.29 Importance Rating 4.4 ATWS: Knowledge of the emergency plan.

Proposed Question: SRO 77 Given the following conditions on Unit 1:

- The Unit was operating at 20% power performing a start up.

- The 1A1 Reactor Coolant Pump inadvertently tripped.

- At time 00:00, the 1AI Reactor Coolant Pump inadvertently tripped but no reactor trip occurred.

- At time 00:01 the RCOs attempted to trip the reactor from the RTGB but were unsuccessful.

- At time 00:08 the SNPO trips the plant by locally opening the Reactor Trip Circuit breakers.

1) For the given conditions, entry into the Emergency Plan _(1).

2) The Shift Manager shall ensure that (2)

A. 1) is NOT required

2) a 4 hr NRC Non-Routine Notification is made by 04:01 due to failure of the Reactor Protection System to automatically shutdown the reactor B. 1) is NOT required

2) a 4 hr NRC Non-Routine Notification is made by 04:08 due manual actuation of the Reactor Protection System C. 1) is required

2) a Site Area Emergency is declared by 00:16 due to the Failure of Rx Protection Emergency Action Level being met D. 1) is required

2) an Alert is declared by 00:23 due to the Failure of Rx Protection Emergency Action Level being met 153

Proposed Answer: C Explanation (Optional):

A. Incorrect. Part I is incorrect. E-Plan entry is required. (SS2). Part 2 is not correct. There is no such SPECIFIC Notification category (for failure of auto RPS actuation).

B. Incorrect. (See explanation in A).

C. Correct. Even though the reactor was tripped, the bases for the SAE states that credit cant be taken for a successful reactor trip if the manual actions that were taken were AWAY from the RTGB (or did NOT occur automatically). SAE must be declared within 15 minutes of the time of failure of the Auto trip AND manual actions taken from the RTGB were attempted.

D. Incorrect. An Alert would be declared if the reactor was Successfully tripped from the RTGB.

Technical Reference(s): EPIP-Ol Bases for SS2 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

Learning Objective: 0902701 Terminal Objective and (As available)

EO-10 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:

Comments:

154

Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 K/A# 040AA2.05 Importance Rating 4.5 Steam Line Rupture Excessive Heat Transfer: Ability to determine and interpret the following as they apply to the Steam Line Rupture: When ESFAS systems may be secured.

Proposed Question: SRO 78 Unit 1 has tripped from 100% power. The crew has entered 1-EOP-05, Excess Steam Demand with the following conditions:

• Pressurizer level is 31% and rising

• Rep CET is 420°F

• ThOt is 415°F

• Pressurizer pressure is 920 psia and rising

• IA SG is isolated lAW with Appendix R

• 1 B SG level is 22% narrow range rising with 200 gpm AFW flow.

• Rx Vessel level indicates 4-8 covered

• Containment pressure is 3.2 psig lowering

• Containment temperature is 122°F lowering

• ECCS total flow is 600 gpm

• Containment Spray total flow is 5800 gpm Based on the above conditions, which ONE of the following states the operation of Containment Spray (CS) and HPSI?

A. HPSI should be throttled and CS should be stopped.

B. HPSI should be throttled and CS should continue to operate as stated.

C. HPSI should be stopped and CS should continue to operate as stated.

D. HPSI and CS should continue to operate as stated.

Proposed Answer: A 155

Explanation (Optional):

A. Correct. Above conditions meet HPSI throttling and CS termination B. CS termination met. Containment pressure and temperature meet termination criteria C. HPSI may be stopped if initial throttling does not stop Pressurizer level rise. CS termination is met D. Both incorrect.

Technical Reference(s): 1-EOP-05, Excess Steam (Attach if not previously provided)

Demand Proposed references to be provided to applicants during examination:

Learning Objective: LP 0702826 Obj. 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: 43.5 45.13 Comments:

156

Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 K/A # 054G2.4.30 Importance Rating 4.1 Loss of Main Feedwater: 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 Which ONE of the following would require notification to the State (SWO) AND the NRC?

A. Plant trip from 30% power with a total loss of all feedwater for 22 minutes.

B. Plant trip from 100% power with Main Steam Safety valve stuck open and fails to close.

C. Failure to meet RCS Heat Removal Safety Function for >15 minutes and entry into EOP-15.

D. A side LOOP with failure of A Emergency Diesel Generator to start.

Proposed Answer: C Explanation (Optional):

Failure of RCS heat removal is a result of total loss of all feedwater. This will result in E-Plan classification and notification of NRC and SWO. Other distractors do not meet notification requirements to SWO, i.e NO E-Plan call, but will result in notification to NRC.

Technical Reference(s): EPIP-08 Off-Site Notifications (Attach if not previously provided) and Protective Action Recommendations EPIP-Ol Classification of Emergencies Proposed references to be provided to applicants during examination:

Learning Objective: PSL 0902701 Obj. 10 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent) 157

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 45.11 Comments:

158

Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 KIA# 057AA2.16 Importance Rating 3.1 Loss of Vital AC Inst. Bus: Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus:

Normal and abnormal PZR level for various modes of plant operation Proposed Question: SRO 80 Unit 2 is operating at 100% power when a malfunction occurs resulting in numerous alarms and instrument failures, some of which are:

• Selected Pressurizer level LI-Ill OY indicates failed LOW

• PIA-22I2, Charging Hdr. Pressure indication on RTGB-205 indicates failed LOW

• Excore source range and Wide range NI on RTGB-204 indicates power lost

• TI-I 125 2B1 Cold Leg temperature indicates power lost

• P1-i 107-1 Pressurizer Pressure wide range indicates failed LOW Ten minutes later, with no Operator action, the following is observed:

• The Unit is at 100% power.

• Pressurizer level is 69%.

Which ONE of the following states:

1) the power supply that was lost.

2) the Technical Specification action.

A. l)I2OVVitalACbus2B

2) Restore Pressurizer level and A side heaters within 72 HOURS B I) 120V Vital AC bus 2B

2) Restore Pressurizer level within SIX HOURS and A side heaters within 72 HOURS C. 1) 120V AC Instrument bus 2-MB-I

2) Restore Pressurizer level and A side heaters within 72 HOURS D I) 12OVAC Instrument bus 2-MB-l

2) Restore Pressurizer level within SIX HOURS and A side heaters within 72 HOURS Proposed Answer: D 159

Explanation (Optional):

A. 120V Vital AC bus 2B is non safety bus that supplies mostly secondary side instrumentation. Pressurizer level will increase due to selected level controller failing low resulting in minimum letdown, starting of standby Charging pump. T.S. limit of<68%

places the Unit in a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> action statement. Failed low Pressurizer level (Y) will result in loss of A side heater bank. T.S. requires both banks operable or restore in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

B. Part I incorrect, part 2 incorrect C. Part 1 correct, part two incorrect.

D. Correct. 120V AC Instrument bus 2-MB-i supplies all of the referenced items.

Pressurizer level >68% places the unit is a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> action statement.

Technical Reference(s): 2-AOP-49.02 120V Instrument (Attach if not previously provided)

AC System (Class 1 E)

T.S. 3.4.3 Pressurizer Proposed references to be provided to applicants during examination:

Learning Objective: PSL OPS 0702863 Obj. 3 (As available)

PSL OPS 0702206 Obj. 18e LP 0902723 Obj. 1 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:

160

Examination Outline Cross-reference: Level RO SRO Tier#

Group#

KIA# 077AA2.03 Importance Rating 3.6 Generator Voltage and Electric Grid Disturbances: Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: Generator current outside the capability curve Proposed Question: SRO 81 Unit 2 is at 100% power Unit 1 is at 100% power with the following plant conditions:

• Main Generator is 60 MVARS in the Lag.

• Main Generator Gross MWs are 895.

• The Unit is only able to maintain 45 psig Hydrogen pressure.

• Outside air temperature is 85°F A loss of ONE of THREE Midway circuits resulted in a system disturbance adding 290 Leading MVARs.

0-AOP-53.04, Reduced Offsite Transmission Capacity was entered.

1) What equipment concern is there related to the added MVARS?

2) What action level is applicable based on the loss of ONE Midway circuit?

References provided A. 1) Rotor overheating

2) ACTION level 3.

B. 1) Rotor overheating

2) ACTION level 2.

C. 1) Stator overheating

2) ACTION level 3.

D. 1) Stator overheating

2) ACTION level 2.

161

Proposed Answer: D Explanation (Optional):

A. Rotor will not overheat on an under excited condition. Could be chosen if student misidentifies direction of MVAR shift on the capability curve. Loss of only one Midway circuits with both Units on line is Action level 2. Action level 1 would be applicable if only one Unit was on line.

B. Action level 2 correct. Rotor incorrect as stated above.

C. Stator correct as seen by line 2 between points B and C on curve. Action level 1 is not correct.

D. Correct.

Technical Reference(s): Generator Capability Curve. (Attach if not previously provided) 0AOP-53.O4 Reduced Offsite Transmission Capability Proposed references to be provided to applicants during examination: Generator Capability Curve.

Learning Objective: PSL OPS 0702860 Obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 41.5 43.5 45.5 45.7 45.8 Comments:

162

Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 K/A # 0024AG2.2.25 Importance Rating 4.2 Emergency Boration: Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

Proposed Question: SRO 82 Unit 1 is at 100% power with the IA Boric Acid Makeup pump out of service for shaft seal replacement. The IA and lB BAMTs are combined to meet the Technical Specification.

Which ONE of the following states the:

1) number of Technical Specification emergency boration flowpaths available and

2) bases for the specification A. 1) 3 flowpaths available

2) ensure sufficient shutdown margin to cooldown to 200°F AFTER xenon decay based on End Of Life conditions.

B. 1) 2 flowpaths available

2) ensure sufficient shutdown margin to cooldown to 200°F AFTER xenon decay based on End Of Life conditions.

C. 1) 3 flowpaths available

2) ensure sufficient shutdown margin to cooldown to 200° F AFTER xenon decay based on Beginning Of Life conditions.

D 1) 2 flowpaths available

2) ensure sufficient shutdown margin to cooldown to 200°F AFTER xenon decay based on Beginning Of Life conditions.

Proposed Answer: B Explanation (Optional):

A. Three flowpaths are not available due to 1A and I B BAMTs being combined to meet the specification. If the 1A BAM pump was NOT out of service OR If the two tanks were both in spec. this would be the correct answer.

B. Correct C. Available flow paths not correct and BOL conditions not correct D. BOL not correct 163

Technical Reference(s): T.S. 3.1.2.2 (Attach if not previously provided)

T.S. Bases 3/4.1 Proposed references to be provided to applicants during examination:

Learning Objective: LP 0902723 Obj, 2,3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 41.5 41.7 43.2 Comments:

164

Examination Outline Cross-reference: Level RO SRO Tier#

Group# 2 K/A # 037AG2.4.41 Importance Rating 3.6 Steam Generator Tube Leak: Knowledge of the emergency action level thresholds and classifications.

Proposed Question: SRO 83 Unit I is at 100% power. The Steam Jet Air Ejector and Blowdown monitors are in alarm. Two Charging Pumps are running and letdown is 58 gpm with Pressurizer level constant.

Which ONE of the following states the:

1) Current Emergency Action Level (EAL) and

2) What condition would result in escalation of this EAL A. 1) Notification of Unusual Event (NOUE)

2) The Unit trips and RCS pressure stabilizes at 1690 psia.

B. 1) Notification of Unusual Event (NOUE)

2) The Unit trips and RCS pressure stabilizes at 1550 psia.

C. 1)ALERT

2) The Unit trips and RCS pressure stabilizes at 1690 psia.

D. 1)ALERT

2) The Unit trips and RCS pressure stabilizes at 1550 psia.

Proposed Answer: B Explanation (Optional):

A. This would be the correct answer if stem stated Unit 2. (Unit 2 SIAS at 1736 psia.)

B. Correct. NOUE due to SGTL within Charging Pump capacity. Escalates to ALERT if actuation of ECCS (Unit 1 SIAS 1600 psia.)

C. Current EAL is NOUE. 1690 psia, no ECCS on Unit 1 D. Both incorrect.

Technical Reference(s): EPIP-Ol, Classification Of (Attach if not previously provided)

Emergencies Proposed references to be provided to applicants during examination:

165

Learning Objective: PSL 0902701 Obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 4t10 43.5 45.11 Comments:

166

Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 KIA# 069AA2.O1 Importance Rating 4.3 Loss of CTMT Integrity: Ability to determine and interpret the following as they apply to the Loss of Containment Integrity: Loss of containment integrity Proposed Question: SRO 84 Given the following conditions on Unit 1:

• OP 1-0010125A, Surveillance Data Sheets 8A, Valve Cycle Test Non Check Valve is -

being performed

• V5200 and V5203, RCS Hot Leg Sample Isolation valves have just been exercised

• V5200 EXCEEDED the max allowable closed stroke time.

• V5203 closed stroke time was satisfactory.

• V5200 and V5203 are in the CLOSED position.

1) With NO further operator action, is Containment Integrity being met?

2) Which ONE of the following can be performed to satisfy Tech Specs if Chemistry requests to obtain an RCS sample?

A. 1)YES.

2) With V5200 open, initiate 1-0010125A Surveillance Data Sheet 30, Unscheduled Surveillances to track the valve status.

B. 1)YES.

2) With V5200 open, station an Operator in the Control Room whose sole function is to close V5200 in an accident situation.

C. 1) NO. Enter Tech Spec LCO 3.6.3.1 Containment Isolation Valves and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, ensure V5200 remains closed and de-energized.

2) With V5200 energized and open, initiate 1-0010125A Surveillance Data Sheet 30, Unscheduled Surveillances to track the valve status.

D. 1) NO. Enter Tech Spec LCO 3.6.3.1 Containment Isolation Valves and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, ensure V5200 remains closed and de-energized.

2) With V5200 energized and open, station an Operator in the Control Room whose sole function is to close and de-energize V5200 in an accident situation.

167

Proposed Answer: D Explanation (Optional):

A. Incorrect. Containment Integrity would not be met if no other actions were taken (i.e. one of the 4hr actions listed in TS3.6.3.1). Part 2 is incorrect, lAW Ops Policy 503 section %.6.3, Data sheet 30 would be used to track an open CIS valve (that is inoprable), but a dedicated operator must be on station in order to close the valve in case of an emergency condition.

B. Incorrect. Part 1 is incorrect (see explanation in A). Part 2 is correct. The Cont. Integrity TS bases allows for CIS valves to be opened on an intermittent bases as long as a dedicated operator is stationed at the valves controls to take action to close the valve in case of an accident situation. lAW Ops Policy 503 section %.6.3, Data sheet 30 would be used to track an open CIS valve that is inoperable. This requirement is admin only not TS related.

C. Incorrect. Part I is correct but Part 2 is incorrect (See explanation in A).

D. Correct. Both parts are correct. An inoperable CIS valve is required to be repaired within 4hrs or maintained in an isolation condition and de-activated. The Cont. Integrity TS bases allows for CIS valves to be opened on an intermittent bases as long as a dedicated operator is stationed at the valves controls to take action to close the valve in case of an accident situation.

Technical Reference(s): T.S. Bases 3/4.6.1.1 (Attach if not previously provided)

Containment Integrity Operations Department Policy OPS-503 Technical Specification Guidance Proposed references to be provided to applicants during examination:

Learning Objective: LP 0902723 Obj. I (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:

168

Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 KIA# CAl 1AA2.1 Importance Rating 3.3 RCS Overcooling PTS: Ability to determine and interpret the following as they apply to the (RCS Overcooling) Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Proposed Question: SRO 85 Unit I has tripped with a Loss of Offsite power. The Crew is about to exit 1-EOP-01, Standard Post Trip Actions with the following indications.

• Pressurizer pressure is 850 psia and rising

• ECCS flow is 720 gpm and lowering

• Pressurizer level is 15% and rising

• CET is 338°F and Th t is 330°F slowly lowering 0

• IA SG is 30 psia and stable

• I B SG is 620 psia and lowering

• IA SG level is 5% Wide range with 0 AFW flow

• 1 B SC level is 10% Narrow range and rising with 220 gpm AFW flow

• Containment pressure is 0 psig

• Reactor vessel level indicates 4-8 covered

• Secondary surveys are yet to be taken Which procedure should be implemented and which action should be taken?

A. 1-EOP-15, Functional Recovery. Stop the cooldown to lower subcooling.

B. 1-EOP-15, Functional Recovery. Depressurize the RCS to increase SI flow.

C. 1-EOP-05, Excess Steam Demand. Stop the cooldown to lower subcooling.

D. 1-EOP-05, Excess Steam Demand. Depressurize the RCS to increase SI flow.

Proposed Answer: C 169

Explanation (Optional):

A. Based on given conditions there is only a single event occurring (ESD). EOP-15 is entered for: a dual event, unable to diagnose or unable to maintain Safety functions, none of which the stated conditions indicate. Stopping the cooldown is correct as the RCS is approaching maximum subcooling (200°F).

B. EOP-1 5 is not correct. Depressurizing the RCS will increase SI flow which will increase the cooldown.

C. Correct. Based on the above conditons there is only a single event occurring. Stopping the cooldown is correct as the RCS is approaching maximum subcooling.

D. Depressurizing the RCS will increase SI flow which will increase the cooldown.

Technical Reference(s): 1-EOP-05, Excess Steam (Attach if not previously provided)

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

Learning Objective: LP 0702826 Obj. 5,11,12,15 (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:

170

Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A # 003G2.2.40 Importance Rating 4.7 Reactor Coolant Pump: Ability to apply Technical Specifications for a system.

Proposed Question: SRO 86 Unit 2 is in Mode 5 making preparations to enter Mode 4.

Which ONE of the following will meet the MINIMUM Technical Specification requirements for RCS loops operable for Mode 4 and what are the bases for this minimum requirement?

A. Reactor Coolant Pumps 2A1 and 2A2 operable and its associated SG.

Based on one RCP and associated SG capable of removing decay heat but single failure criteria require two pumps to be operable.

B. Reactor Coolant Pumps 2A1 and 2B2 operable and their associated SGs.

Based on one RCP and associated SG capable of removing decay heat but single failure criteria require two pumps to be operable.

C. Reactor Coolant Pumps 2A1 and 2A2 operable and its associated SG.

Based on one RCP providing adequate flow to ensure mixing for boron concentration reductions but single failure criteria require two pumps to be operable.

D. Reactor Coolant Pumps 2A1 and 2B2 operable and their associated SGs.

Based on one RCP providing adequate flow to ensure mixing for boron concentration reductions but single failure criteria require two pumps to be operable.

Proposed Answer: B Explanation (Optional):

A. 2A1 and 2A2 do not constitute two loops.

B. Correct C. 2A1 and 2A2 do not constitute two loops. Single failure criteria is not applicable for boron concentration reductions.

D. Single failure criteria is not applicable for boron concentration reductions.

171

Technical Reference(s): T.S 3.4.1.3 and associated (Attach if not previously provided) bases.

Proposed references to be provided to applicants during examination:

Learning Objective: LP 0902723 Obj. 2, 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 41.10 43.2 43.5 45.3 Comments:

172

Examination Outline Cross-reference: Level RO SRO Tier# 2 Group#

1 KIA# 008A2.03 Importance Rating 3.2 008 component cooling Water System (CCWS) Ability to (a) predict the impacts of the following malfunctions or operations on the ccws, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High/low ccw temperature Proposed Question: SRO 87 Unit 2 is at 100% power. The following alarm annunciates:

2A12B CCW HX TEMP HIGH s-I 3 It has been determined the 2A CCW HX is the alarming HX.

1) Which procedure directs the mitigating actions.

2) Actions to be taken within that procedure.

A. 1) Implement 2-AOP-1 4.01, Component Cooling Water Abnormal operations.

2) Place the pump control switch for HPSI Pump 2A on RTGB-206 in STOP.

B. 1) Implement 2-AOP-21 .03A, 2A Intake Cooling Water System Header

2) Place the pump control switch for HPSI Pump 2A on RTGB-206 in STOP.

C. I) Implement 2-AOP-14.01, Component Cooling Water Abnormal Operations.

2) Fail TCV-14-4A CCW HX Outlet OPEN.

D. 1) Implement 2-AOP-21 .03A, 2A Intake Cooling Water System Header

2) Fail TCV-14-4A CCW HX Outlet OPEN.

173

Proposed Answer: D Explanation (Optional):

A. 2-AOP-14.01 gives guidance for loss / degraded CCW. Placing HPSI 2A to STOP is direction for loss of COW HX.

B. 2-AOP-21 .03A, is correct but Placing HPSI 2A to STOP is direction for loss of COW HX C. Fail TOy-i 4-4A CCW HX Outlet OPEN guidance is in 2-AOP-21 .03A D. Correct Technical Reference(s): 2-AOP-21 .03A (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

Learning Objective: PSL OPS 0702862 Obj. 1, 3b (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: 41.5 43.5 45.3 45.13 Comments:

174

Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A # 013G2.2.44 Importance Rating 4.4 Engineered Safety Features Actuation: Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

Proposed Question: SRO 88 Unit 2 is at 100% power with the following:

Unit 2 AFAS-1 Feedwater Header Pressure Pl-09-9C on the 2A SG failed low 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ago and the T.S. action statement has been implemented.

2A SG Pl-09-9B Feedwater Header Pressure drifted to 500 psia. The operator bypasses channel B AFAS-1 for Pl-09-9B.

Which ONE of the following describes the configuration of AFAS-1 when the Operator bypasses Pl-09-9B?

PIC-09-9C was in the:

A. tripped condition prior to placing Pl-09-9B in bypass. AFAS-1 is now in a 1 out of 2 condition.

B. tripped condition prior to placing Pl-09-9B in bypass. AFAS-1 is now in a 2 out of 3 condition.

C. bypassed condition prior to placing Pl-09-9B in bypass. PT-09-9C is now in the tripped condition. AFAS-1 is now in a 1 out of 2 of condition.

D. bypassed condition prior to placing Pl-09-9B in bypass. Pl-09-9C is now in the tripped condition. AFAS-1 is now in a 2 out of 3 condition.

Proposed Answer: C 175

Explanation (Optional):

A. PT-09-9C was in bypass not tripped. Action statement in T.S. requires PT-09-9C to be placed in the bypass conditions no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Stem of question stated that T.S.

action statement has been implemented. Applicant must know the T.S action statement requirements.

B. PT-09-9C was not in tripped condition. 2 out of 3 is not correct C. Correct D. 2 out of 3 is not correct Technical Reference(s): PSL OPS SYS 412 (Attach if not previously provided)

T.S. 3.3.3 Table 3.3-3 Proposed references to be provided to applicants during examination:

Learning Objective: PSL OPS 0702412 Obj. 4, 12 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 41.5 43.5 45.12 Comments:

176

Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KIA# 039A2.03 Importance Rating 3.7 Main and Reheat Steam: Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Indications and alarms for main steam and area radiation monitors (during SGTR)

Proposed Question: SRO 89 Unit 2 confirmed a Steam Generator tube leak of 0.15 gallons per minute at time 0220.

Assuming the leak remains constant as the down power progresses, which ONE of the following radiation monitors:

1) will trend lower in relationship to the initial reading as the unit is down powered, hQJh_

réason why AND

2) Which ONE of the following procedures will be implemented anwhich T.S. ACTION statement, if any, applies.

A. 1) Condenser Air Ejectordpto decreasing steam flow

2) 2-GOP-I 23, Turbine Shutdown-Full Load to Zero Load.LNo_app[icable action as the primary to secondary leakage has not exceeded Tech.

Specs.

B. 1) Condenser Air Ejector due to decreasing steam flow

2) 2-AOP-22.0I, Rapid Downpower. T.S. ACTION required is to be in at least Mode 3 no later than 0820.

C. I) Main Steam Line due to decreasing levels of N 16

2) 2-AOP-22.01, Rapid Downpower. T.S. ACTION required is to be in at least Mode 3 no later than 0820.

D. 1) Main Steam Line due to decreasing levels of N 16

2) 2-GOP-123, Turbine Shutdown-Full Load to Zero Load. No applicable action as the primary to secondary leakage has not exceeded Tech.

Specs.

Proposed Answer: C 177

Explanation (Optional):

A. Steam flow does not decrease through the SJAE monitor during the downpower. 0.15 gpm is 216 gallons per day leakage which exceeds the 150 gpd T.S. limit. 2-GOP-123 would be entered for a non emergency plant shutdown.

B. N16 is not detected by the SJAE due to the short half life C. Correct, N 16 levels are power dependant. >75 gpd leak rate requires a rapid downpower.

T.S. limit exceeded. Action statement: be in Mode 3, Hot Standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

D. Steam flow is decreasing but N 16 is power dependant Technical Reference(s): T.S. 3.4.6.2 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

Learning Objective: PSL OPS 0702825 Obj. 3,4 (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: 41.5 43.5 45.3 45.13 Comments:

178

Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# I KIA# 061A2.05 Importance Rating 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 90 Given the following conditions on Unit 1:

• The unit is at 100% power

• The I C Auxiliary Feedwater Pump (AFW) is out of service.

- At time 10:00:00, a unit trip occurs.

- At time 10:03:00, both Steam Generators Narrow Range levels were observed to be

<15% on all safety channels.

- At timel0:07:15, prior to any Operator actions, the RCO reports that the 1 B AFW train has just actuated on AFAS-2 but AFAS-1 has not actuated.

- At time 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) AFAS-1 reset lockout relay 2)1-AOP-09.02 Auxiliary Feedwater to manually actuate AFAS-1 B. I) time delay relay 2)1-AOP-09.02 Auxiliary Feedwaterto manually actuate AFAS-1 C. 1) AFAS-1 reset lockout relay 2)1-NOP-09.02 Auxiliary Feedwater System Operation to manually operate 1A AFW train components D. 1) time delay relay 2)1-NOP-09.02 Auxiliary Feedwater System Operation to operate 1A AFW train components 179

Proposed Answer: B Explanation (Optional):

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

B. Correct. The time delay failed on AFAS-1. Both AFAS-1 & 2 shouldve worked. There are no rupture ID factors. The AFAS reset lockout relay only affects cycling components.

AOP-09.02 DOES have guidance for manually actuating AFAS if it shouldve actuated but didnt. NOPO9.02 DOES NOT have that guidance. It only has guidance for manually starting components.

C. Incorrect. Neither part is true (See A & B).

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

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

Learning Objective: PSL OPS 0702412 Obj. 3b, 4b (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 Corn rnents:

180

Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 KIA# 016A2.02 Importance Rating 3.2 Non-nuclear Instrumentation: 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: Loss of power supply Proposed Question: SRO 91 Unit 1 is at 100% power when the power supply to Channel A ESFAS cabinet has failed (de energized).

Which ONE of the following states the ESFAS RAS actuation logic and the Technical Specifications associated with RWT level Channel A, LT-07-2A?

RAS is in a:

A. I out of 3 logic. If RWT level Channel A LT-07-2A operability can not be restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, 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 />.

B. 2 out of 3 logic. If RWT level Channel A LT-07-2A operability can not be restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, 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 />.

C. 1 out of 3 logic. If RWT level Channel A LT-07-2A operability can not be restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, then place the inoperable channel in the tripped condition.

D. 2 out of 3 logic. If RWT level Channel A LT-07-2A operability can not be restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, then place the inoperable channel in the tripped condition.

Proposed Answer: B Explanation (Optional):

A. RAS (and CSAS) is energize to actuate. If this was any other ESFAS channel 1 out of 3 logic would be correct in that other ESFAS channels are de-energize to actuate.

B. Correct. Logic is 2 out of 3 due to RAS is a de-energize to actuate channel. Applicable T.S. action 13 Table 3.3-3 C. This is T.S. action lOa Table 3.3-3 related to Containment pressure High-High ESFAS channel.

D. Logic incorrect and T.S. action incorrect.

181

Technical Reference(s): Tech Spec 3.3.2.1, Table (Attach if not previously provided) 3.3-3 Action I 3a Proposed references to be provided to applicants during examination:

Learning Objective: PSL OPS ADM 703 LPC Obj. 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: 41.5 43.5 45.3 45.5 Comments:

182

Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 K/A # 035G2.4.47 Importance Rating 4.2 Steam Generator: Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

Proposed Question: SRO 92 Unit 1 is at 100% power. The crew has entered 1-AOP-08.02, Steam Generator Tube Leak.

and has been logging the following secondary radiation monitor readings every 15 minutes.

0120 0135 0150 0205 Blowdown A S/G 490 cpm A S/G 980 cpm A S/G 1420 cpm A SIG 9620 cpm B S/C 120 cpm B S/G 125 cpm B S/C 138 cpm B S/G 140 cpm Air Ejector 60 cpm 410 cpm 720 cpm 6340 cpm lAW 1-AOP-08.02, Steam Generator Tube Leak, based on the above readings, which ONE of the following states when a rapid down power is required to begin and when is the Unit required to be in Mode 3?

(references provided, Chemistry daily report)

Start a rapid downpower no later than:

A. 0135 and be in Mode 3 no later than 0750.

B. 0120 and be in Mode 3 no later than 0750.

C. 0120 and be in Mode 3 no later than 0335.

D. 0135 and be in Mode 3 no later than 0335.

Proposed Answer: D 183

Explanation (Optional):

A. 0135 is correct in that the leakage indicates >75 gpd. 0750 is the T.S limit if >150 gpd leakage exceeded. (6 hrs to HSB)

B. Readings indicate 30 gpd which requires RMS monitoring at 15 minute intervals but does not meet the downpower requirements C. Readings indicate 30 gpd which does not meet the downpower requirements.

D. Correct. 0135 >75 gpd, procedure requires HSB within next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Technical Reference(s): 1-AOP-08.02, Steam (Attach if not previously provided)

Generator Tube Leak.

T.S. 3.4.6.2 RCS Leakage Unit 1 Daily Chemistry Report Proposed references to be provided to applicants during examination: Unit 1 Daily Chemistry Report Learning Objective: PSL OPS ADM 703 Obj.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: 41.10 43.5 45.12 Comments:

184

Examination Outline Cross-reference: Level RO SRO Tier# 2 Group#

2 KIA# 075A2.02 Importance Rating 2.7 Circulating Water: Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of circulating water pumps Proposed Question: SRO 93 Unit I is at 95 % power. The Unit is performing a down power due to fouling of the intake canal with the following:

• Intake temperature is 80°F.

• Discharge canal temperature is 109°F.

• Discharge canal level is 12.9 feet.

During the down power the crew tripped the 1A1 Circulating Water pump. lAW 1-AOP-21.01, Circulating Water System, which ONE of the following parameters would FIRST be exceeded and who is required to be notified?

A. Discharge canal temperature. Notify Chemistry.

B. Discharge canal temperature. Notify Environmental Compliance Supervisor.

C. liT between intake and discharge temperature. Notify Chemistry.

D. /IT between intake and discharge temperature. Notify Environmental Compliance Supervisor.

Proposed Answer: C Explanation (Optional):

A. Intake temperature will not change but a two degree rise in discharge temperature will result in exceeding the 30°F liT between intake and discharge temperature. This two degree rise will be less than the 113°F limit for the discharge canal.

B. Environmental Compliance Supervisor is only required to be notified if the discharge canal level rises to 15.5 feet.

C. Correct. A two degree rise in discharge temperature will result in exceeding the 30°F liT between intake and discharge temperature. This condition requires Chemistry to be notified.

D. Both statements incorrect.

185

Technical Reference(s): 1-AOP-21.01, Circulating (Attach if not previously provided)

Water System Proposed references to be provided to applicants during examination:

Learning Objective: PSL OPS 0702860 Obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 41.5 43.5 45.3 45.13 Comments:

186

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

1 KIA# 2.1.40 Importance Rating 3.9 Knowledge of refueling administrative requirements. (SRO)

Proposed Question: SRO 94 In accordance with 3200090, Refueling Operations, during Fuel movement, which ONE of the following states the responsibilities and the SRO required locations including the location of the designated Refueling Supervisor.

A. One SRO or Refueling SRO shall be in the Spent Fuel Pool to supervise fuel movement. A separate SRO designated as the Refueling Supervisor shall be in the area designated as the Refueling Center, controlling all refueling operations.

B. One SRO or Refueling SRO shall be in the Spent Fuel Pool to supervise fuel movement. A separate SRO designated as the Refueling Supervisor controlling all refueling operations, shall be on the refueling machine.

C. One SRO shall be on the refueling machine. A separate SRO designated as the Refueling Supervisor controlling all refueling operations, shall be in the area designated as the Refueling Center.

D. One SRO designated as the Refueling Supervisor controlling all refueling operations, shall be on the refueling machine. A separate SRO shall be in the area designated as the Refueling Center.

Proposed Answer: B Explanation (Optional):

The SRO designated as the Refueling Supervisor is required to be stationed on the refueling machine. Another SRO or Refueling SRO is required to be in the Spent Fuel pool to supervise fuel movement.

Technical Reference(s): 3200090, Refueling (Attach if not previously provided)

Operations Proposed references to be provided to applicants during examination:

Learning Objective: (As available) 187

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:

188

Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 2 KIA# 2.2.15 Importance Rating 4.3 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc. (SRO)

Proposed Question: SRO 95 Unit 1 is operating at 100% power. The following annunciator has alarmed 10 times in the past eight hours.

DEH RETURN PRESS HIGH D-46 Investigation has determined pressure switch P5-22-i 18 is defective.

The annunciator has been declared Out-of-Service at 0100 on 1/14/11. It is now 0200, 1/21/11.

Which ONE of the following states:

1. The procedure used to track the configuration of the Out-of-Service annunciator on 1/14/11

2. The procedure used to track the configuration of the Out-of-Service annunciator on 1/21/11 A. 1) ADM-09.03, Administrative Control of Defeated Annunciators

2) ADM-1 7.18, Temporary System Alteration.

B. 1) ADM-1 7.18, Temporary System Alteration.

2) ADM-09.03, Administrative Control of Defeated Annunciators C. 1) ADM-1 7.18, Temporary System Alteration.

2) ADM-1 7.18, Temporary System Alteration.

D. 1) ADM-09.03, Administrative Control of Defeated Annunciators

2) ADM-09.03, Administrative Control of Defeated Annunciators 189

Proposed Answer: A Explanation (Optional):

A. Correct, Annunciator is considered a nuisance alarm lAW ADM-09.03 and can only be used for up to 7 days for tracking. The procedure is then exited to ADM-1 7.18 for further tracking.

B. Backwards C. Plausible, if the annunciator was not defeated and declared OOS ADM-1 7.18 would be applicable.

D. Plausible if applicant does not know the time constraints of ADM-09.03 Technical Reference(s): ADM-09.03 Administrative (Attach if not previously provided)

Control of Defeated Annunciators ADM-1 7.18, Temporary System Alteration.

Proposed references to be provided to applicants during examination:

Learning Objective: PSL OPS 0902711 Obj. 4 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 41.10 43.3 45.13 Comments:

190

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

2 K/A# 2.2.21 Importance Rating 4.1 Knowledge of pre- and post-maintenance operability requirements.

Proposed Question: SRO 96 Unit 1 is at 100% power The 1A Emergency Diesel Generator (EDG) is to be taken out of service for pre-planned maintenance (lube oil filter change) and to repair a minor oil leak on the lube oil filter.

1) In accordance with 1-OSP-59.OIA, 1A Emergency Diesel Generator Monthly Surveillance which ONE of the following states the equipment required to be verified operable prior to removing the 1A Diesel from service?

2) In accordance with ADM-78.01, Post Maintenance Testing which ONE of the flowing states the Post Maintenance Testing required to return the Diesel to service?

A. 1) The I B and IC AFW pumps. Off site power source. Gravity feeds and the RWT to the Charging pumps.

2) Local Idle start, synchronization and load test and external leakage check.

B. 1) The 18 and 1 C AFW pumps. Off site power source. Gravity feeds and the RWT to the Charging pumps.

2) External leakage check ONLY.

C. I) The 1 B EDG and IC AFW pump. BAM pumps and Emergency borate valve.

2) Local Idle start, synchronization and load test and external leakage check.

D. 1) The 1 B EDG and IC AFW pump. 8AM pumps and Emergency borate valve.

2) External leakage check ONLY.

Proposed Answer: A 191

Explanation (Optional):

The BAM pumps and emergency borate valve are powered from the A side and the gravity feeds are powered from the B side. B side operability checks are required.

Operability check of the I B EDG is required for certain conditions of inoperability of the 1A EDG, but not for pre-planned maintenance. Technical Specifications require the 10 AFW pump to be verified operable however procedure 1-OSP-59.01A, 1A Emergency Diesel Generator Monthly Surveillance requires C and B to be operable.

Technical Reference(s): ADM-78.O1, Post Maintenance (Attach if not previously provided)

Testing 1-OSP-59.O1A, 1A Emergency Diesel Generator Monthly Surveillance 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 43.2 Comments:

192

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

3 KIA# 2.3.13 Importance Rating 3.8 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Proposed Question: SRO 97 Unit 1 is performing a resin transfer of the 1 B Waste Ion Exchanger to the Spent Resin Tank using 1 -NOP-06. 10, Radioactive Resin Transfer / Replacement For 1 B Waste Ion Exchanger.

The Control Room has been notified of this evolution.

During the transfer an Area Radiation monitor alarm RE-26-20, North wall of VCT hallway goes into HIGH-HIGH alarm. The Control Room has determined it to be a valid alarm.

Which ONE of the following actions should be taken?

A. Inform the Control Room this is expected for the resin transfer.

B. Announce evacuation of the affected area.

C. Stop the resin transfer and flush the transfer piping until radiation levels equal background level.

D. Stop the resin transfer and verify the valve lineup.

Proposed Answer: B Explanation (Optional):

A. This would be correct if the radiation alarm monitor / alarm was in the area of the resin transfer piping. (Ref. step 6.2.1 of 1-NOP-06.10). Applicant is required to have knowledge of piping arrangement for resin transfer.

B. Correct. RE-26-20 is not near resin transfer piping and is not related to resin transfer.

C. This is performed later in the procedure when the transfer is complete.

D. Plausible. If expected results are not obtained, common practice is to verify correct valve lineup.

193

Technical Reference(s): 1-NOP-06.10, Radioactive (Attach if not previously provided)

Resin Transfer I Replacement For I B Waste Ion Exchanger.

1 -AOP-26.02, Area Radiation Monitors Proposed references to be provided to applicants during examination:

Learning Objective: PSL OPS 0702861 Obj. 3 (As available)

Question Source: Bank # QID 3954 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: 41.12 43.4 45.9 45.10 Comments: Replaced original distractor B: Direct HP to perform a survey of the area to determine if the resin transfer was the cause of the HIGH HIGH alarm with D Stop the resin transfer and verify the valve lineup. Changed the correct answer C to B.

194

Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 3 KIA# 2.3.4 Importance Rating 3.7 Knowledge of radiation exposure limits under normal or emergency conditions.

Proposed Question: SRO 98 Unit I has experienced a Large Break LOCA with fuel failure. RAS has just actuated.

In an attempt to exit the safeguards room an Operator slipped and it appears his leg is broke.

His injuries are not life threatening but he cannot exit this area without assistance. The general dose in this area is 20 RIHr What is the MAXIMUM time the Emergency Response individual has to rescue the injured Operator without exceeding the exposure limits (Total Dose) and who is required to authorize this rescue?

A. 15 minutes, Emergency Coordinator B. 30 minutes, Emergency Coordinator C. 15 minutes, TSC HP Supervisor D. 30 minutes, TSC HP Supervisor Proposed Answer: B Explanation (Optional):

A. 15 minutes (5 REM) is maximum time without exceeding TEDE exposure limit (5 REM) for Performance of actions that would not directly mitigate the event, minimize escalation, or minimize effluent releases.

B. Correct, 30 minutes is 10 REM (limit 10 REM for rescue of a person from a non-life threatening situation). This rescue attempt would be considered a re-entry which is authorized by the EC.

C. TSC HP Supervisor is the individual that determines need to dispense Potassium Iodine (Ki) 195

Technical Reference(s): EPIP-02, Duties And (Attach if not previously provided)

Responsibilities Of The Emergency Coordinator Attachment 5, Proposed references to be provided to applicants during examination:

Learning Objective: PSL 0902701 Obj. 13 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 4t12 43.4 45.10 Comments:

196

Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 4 KIA# 2.4.16 Importance Rating 4.4 Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe acddent management guidelines.

Proposed Question: SRO 99 Unit 1 is in 1-EOP-15, Functional Recovery.

Based on the below Safety Function Status Check Sheet, which ONE of the following states the continued procedure implementation?

SAFETY FUNCTION SUCCESS PATH time 0015 0030 0045 Reactivity control RC-l CEA Insertion X X X RC-2 Boration via CVCS RC-3 Boration via SIAS Maint. Of Vital Aux DC MVA DC I Batteries/Charger X X X Maint. Of Vital Aux AC MVA AC 1 Startup Transformers MVA AC -2 EDGs

- X X X MVA AC 3 Unit Crosstie RCS Inventory Control ICi CVCS IC2 Safety Injection 0 0 0 RCS Pressure Control PC 1 Subcooled Controlled PC 2 PORVs / Pzr Vent PC 3 Saturated Control X 0 0 RCS & Core Heat HR 1 S/G Without SIAS HR -2 S/G With SIAS 0 0 0 HR 3 Once Through Cooling Containment Isol Cl I Automatic / Manual Isol 0 X 0 Cntmt Press & Temp CTPC I Normal Cntmt Fans CTPC 2 Cntmt Coolers CTPC -3 Cntmt Spray X X X Cntmt Comb Gas CCGC 1 Hydrogen <3.5% X X X CCGC 2 Hydrogen >3.5%

0 Not Met X Met 197

A. At time 0015 implement Severe Accident Management Guidelines and continue implementing 1-EOP-15.

B. At time 0030 exit 1-EOP-15 and implement Severe Accident Management Guidelines.

C. At time 0045 exit 1-EOP-15 and implement Severe Accident Management Guidelines.

D. At time 0045 implement Severe Accident Management Guidelines and continue implementing 1-EOP-15.

Proposed Answer: D Explanation (Optional):

A. At 0015 the first indication of failure of success path to meet Safety Functions. 15 minutes is the guideline to regain Safety Function or the Success path is not working.

B. EOP-15 is implemented concurrently with SAMGS.

C. At 0045 conditions are degrading as indicated by continued loss of Safety Functions and additional loss of Containment Isolation safety function. Even though conditions are degrading EOP-15 is not exited but implemented concurrently with SAMGS D. At 0045 conditions indicate EOP-15 is not mitigating the event and SAMGS should be implemented CONCURRENTLY with EOP-15.

Technical Reference(s): CEN-152 Rev. 5.4 (Attach if not previously provided)

LP 0802009 Proposed references to be provided to applicants during examination:

Learning Objective: 0802009 Obj 2 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 41.10 43.5 45.13 Comments:

198

Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 4 KIA# 2.4.44 Importance Rating 4.4 Knowledge of emergency plan protective action recommendations.

Proposed Question: SRO 100 Unit 1 has declared a General Emergency. In addition, a LOOP is occurring. Off-Site Dose Calculations are being performed. The following meteorological data has been collected:

• 10 Meter wind direction is 170

• 57.9 Meter wind direction is 168 The following IA Main Steam Line monitor readings were taken:

• Reading prior to event: 5x1 0.2 mr/hr

• Current reading 3x10 1 mr/hr

1) Which ONE of the following sectors will be included in the protective action recommendations?

2) Determine if a release is occurring Wind Sectors Wind Sectors Wind Sectors From Affected From Affected From Affected 348-11 HLK 123-146 PQR 236-258 CDE 11-33 JKL 146-168 QRA 258-281 DEE 33-56 KLM 168-191 RAB 281-303 EFG 56-78 LMN 191-213 ABC 303-326 FGH 78-101 MNP 213-236 BCD 326-348 GHU 101-1 23 NPQ There is no 0 sector There is no I sector A. 1)QRAB

2) A release IS occurring B. 1)RAB

2) A release IS occurring C 1)QRAB

2) A release IS NOT occurring D. 1)RAB

2) A release IS NOT occurring 199

Proposed Answer: B Explanation (Optional):

A. If applicant used 57.9 meter wind direction this would be the correct answer. Directions are to use the 10 meter wind direction. A release is defined as 10 times above pre transient values, thus a release IS occurring.

B. Correct C. Both parts incorrect D. Part 2 incorrect Technical Reference(s): EPIP-08, Off-Site Notifications (Attach if not previously provided)

And Protective Action Recommendations EPIP-09, Off-Site Dose Calculations Proposed references to be provided to applicants during examination:

Learning Objective: PSL 0902701 Obj. 7 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 41.10 41.12 43.5 45.11 Comments:

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