ML111540042
| ML111540042 | |
| 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: ML111540042 (150) | |
Text
Examination Outline Cross-reference: Level RD SRO Tier# 1 Group# 1 KIA# 007EA2.06 Importance Rating 4.3 Ability to determine or interpret the following as they apply to a reactor trip: Occurrence of a reactor trip.
Proposed Question: RD 1 On Unit 2, which ONE of the following is NOT a positive indication of a Reactor trip from 50%
power?
A. All Turbine Throttle and Governor valves indicate closed.
B. Core mimic CEA display amber lights are ALL illuminated.
C. Trip circuit breakers (TCBs) 1, 2, 4, 5, 6, 7 green light illuminated, TCB-3 and 8 white light illuminated.
D. All green lights illuminated on CEDMCS panel.
Proposed Answer: A Explanation (Optional):
A. Correct. All turbine valves closed is not positive indication of reactor trip B. Amber lights come from CEA rod drop contacts. All lights illuminated indicate all CEAs fully inserted.
C. Green light indicates TCB open. White light indicates TCB closed. TCB-3 and 8 closed would still result in all CEAs inserted.
D. Green lights indicate all CEAs inserted.
Technical Reference(s): Reactor trip event LP 0702822 (Attach if not previously provided)
CEDS text 0711405 Proposed references to be provided to applicants during examination:
Learning Objective: 0702822 obj. 01,02 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam 1
Question Cognitive Level: Memory or Fundamenta Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:
2
Examination Outline Cross-reference: Level RD SRO Tier# 1 Group# 1 K/A# 008AK2.02 Importance Rating 2.7 Knowledge of the interrelations between the Pressurizer Vapor Space Accident and the following: Sensors and detectors Proposed Question: RD 2 Given the following conditions:
- Unit 1 is at 45% power and stable.
- A 5 gpm break from the upper instrument tap of Pressurizer (Pzr) Level transmitter, LT-1 11 ox, occurs.
Assuming no operator action, which ONE of the following describes the response of LI-i ii OX?
LI-i Ii OX Channel X Pzr Level indication will begin to_(i)____ as a result of the iP cell element between the reference and variable leg sensing a (2)
A. i)lower
- 2) higher tXP due to VARIABLE leg pressure lowering B. 1)lower
- 2) lower 1P due to REFERENCE leg pressure lowering C. i)increase
- 2) lower iP due to REFERENCE leg pressure lowering D. i)increase
- 2) higher tiP due to VARIABLE leg pressure lowering 3
Proposed Answer: C Explanation (Optional):
A. Incorrect: Plausible if candidate confuses Pref and Pvar locations. t,P=Pref-Pvar. As Pref lowers due to loss of level (leakage) then tP lowers to 0. This will cause indicated level to go high. If Pvar lowers, the liP rises to max and causes indicated level to lower. Since the leak is on the controlling channel level controller, as indicated level rises, letdown flow will rise towards maximum (2 Chg pps running) based on + deviation from Pzr level setpoint, causing true Pzr level to lower.
B. Incorrect. See A explanation C. Correct. The leak is on the Ref leg so Pref lowers causing the sensed liP to lower which results in INDICATED level rising. Since the leak is on the controlling channel level controller, as indicated level rises, letdown flow will rise towards maximum (2 Chg pps running) based on + deviation from Pzr level setpoint, causing ACTUAL Pzr level to lower.
D. Incorrect. See A explanation Technical Reference(s): Instrumentation, Sensors & (Attach if not previously provided)
Detectors Fund. 0702193 p.19 Proposed references to be provided to applicants during examination:
Learning Objective: 0702193-9 & 12 (As available)
Question Source: Bank #
Modified Bank # ILT QID Used basic concept but modified 3818 stem & answers to better match K/A New Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 5 55.45 5 Comments:
4
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 KIA # 009EG2.4.4 Importance Rating 4.5 SBLOCA: Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
Proposed Question: RO 3 Unit 1 is cooling down for a refueling outage with the following conditions:
- RCS temperature is 470°F
- RCS pressure is 1580 psia
- Pressurizer level is 45%
Minutes later the following conditions are noted:
- Reactor cavity leakage recorder indicates off scale high
- Pressurizer level is lowering at a rate of 3% per minute with full Charging flow and Letdown isolated.
Which ONE of the following states the procedure implementation strategy for the above conditions?
Enter:
A. 1-ONP-01.01, Plant Condition 1 Steam Generator Heat Removal LTOP Not in Effect and monitor Safety Functions every 15 minutes lAW 1-AOP-01.08, RCS Leakage Abnormal Operations.
B. 1-ONP-01.02 Plant Condition 2 Steam Generator Heat Removal LTOP in Effect and monitor Safety Functions every 15 minutes lAW 1-AOP-01.08, RCS Leakage Abnormal Operations.
C. 1-AOP-01.08, RCS Leakage Abnormal Operations and monitor Safety Functions every 15 minutes lAW 1-ONP-01.01, Plant Condition I Steam Generator Heat Removal LTOP Not in Effect D. 1-AOP-01.08, RCS Leakage Abnormal Operations and monitor Safety Functions every 15 minutes lAW 1-ONP-01.02, Plant Condition 2 Steam Generator Heat Removal LTOP in Effect Proposed Answer: C 5
Explanation (Optional):
A. Safety functions are monitored from 1-ONP-01 .01 concurrently with imp lementing the 1-AOP-09.08.
B. Based on the stated conditions in the stem, LTOP is not in service, thus wrong procedure is referenced.
C. Correct, the AOP is implemented currently while using the ONP to monitor Safety Fucntions.
D. 1-ONP-01.02 is incorrect due to LTOP not in effect.
Technical Reference(s): 1-ONP-01.01, Plant Condition I (Attach if not previously provided)
Steam Generator Heat Removal LTOP Not in Effect.
LMONP Lesson plan 1-AOP-01.08, RCS Leakage 0702813 Abnormal Operations Proposed references to be provided to applicants during examination:
Learning Objective: 0702813 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 Comprehension or Analysis x 10 CFR Part 55 Content: 55.43 2 55.45 6 Comments:
6
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 KIA# 015AK2.07 Importance Rating 2.9 Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: RCP seals Proposed Question: RO 4 Unit I has tripped. On the trip a loss of the 1A1 6.9KV bus occurred. 1-EOP-02, Reactor Trip Recovery is in progress.
Which ONE of the following states the RCS pressure that is to be maintained and the reason why?
A. A minimum pressure of 1800 psia to ensure adequate subcooling is maintained.
B. A maximum pressure of 1850 psia to ensure the temperature of the RCP seal packages to less than 300°F.
C. A minimum pressure of 2225 psia to ensure the Pressurizer pressure control system functions properly.
D. A maximum pressure of 2300 psia to ensure PORVs remain closed and below the high Pressure alarm setpoint.
Proposed Answer: B 7
Explanation (Optional):
A. Minimum pressure is correct but the 1800 psia limit is to ensure adequate margin above SIAS se tpoint.
B. Correct C. 2225 psia would be correct if all RCPs were running. Due to loss of 1A1 6.9 KV bus two RCPs are off and pressure limit is 1800-1850 psia.
D. 2300 psia maximum pressure would be correct if all RCPs were running.
Technical Reference(s): 1 -EOP-02, Reactor Trip (Attach if not previously provided)
Recovery PSTG for 1-EOP-02 Proposed references to be provided to applicants during examination:
Learning Objective: LP 0702822 obj. 08 (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 7 55.45 7 Comments:
8
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 K/A# 022AA2.04 Importance Rating 2.9 Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Makeup: How long PZR level can be maintained within limits Proposed Question: RO 5 Unit 2 is in Mode 3. Due to Pressurizer level control problems, charging and letdown was secured at 2:15 pm. The following conditions are noted:
- RCS temperature is 532°F
- RCS pressure is 2250 psia
- RCP controlled bleedoff is 1.1 gpm per pump
- Pressurizer level is 33%
- Last RCS leak rate was .05 gpm.
Assuming no auto or Operator actions, which ONE of the following states the EARLIEST time that the Pressurizer will be at the minimum Tech. Spec. limit?
A. 3:01 pm B. 3:31 pm C. 3:37 pm D. 3:46 pm Proposed Answer: D 9
Explanation (Optional):
NOTE: Pzr. Level 67.04 gall%, VCT 33.8 galI%. Tech Spec low level is 27%.
Based on the above conditions, Pressurizer level will reach Tech. Spec. limit in 90.39 minutes or 3:46 pm.
A. This is the time if applicant used VCT galI%
B. This is the time if applicant used Tech. Spec limit of 28%, which is Pzr. Level for heater cutout.
C. This is the time if applicant used .5 gpm RCS leak rate instead if .05 gpm.
D. Correct. 6% level change at 67.04 gal/%. Loss of RCS inventory of 402.24 gal. takes 91 minutes.
Technical Reference(s): Tech. Spec 3.4.3 Ammed. 11 (Attach if not previously provided) 2-OS P-01 .03, RCS Inventory Balance.
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702206 obj.12 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.43 5 55.45 13 Comments:
10
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 KIA# 025AK3.01 Importance Rating 3.1 Knowledge of the reasons for the following responses as they apply to the Loss of Residual Heat Removal System: Shift to alternate flowpath Proposed Question: RO 6 Unit 1 is on SDC in reduced inventory condition. The SDC system is aligned and operating in accordance with 1-NOP-01 .04, RCS Reduced Inventory And Mid-Loop Operation. The running LPSI pump trips.
Which ONE of the following states the action required and the reason for this action?
Start the:
A. 1A LPSI pump. V3483, 1A LOOP SDC return to IA LPSI pump relief has the potential to lift at a higher pressure than 1 B LPSI pump.
B. 1A LPSI pump. Due to suction piping arrangement, LPSI Pump lB will experience adverse suction conditions before LPSI Pump IA.
C. lB LPSI pump. V3468, lB LOOP SDC return to lB LPSI pump relief has the potential to lift at a higher pressure than IA LPSI pump.
D. 1 B LPSI pump. Due to suction piping arrangement, LPSI Pump IA will experience adverse suction conditions before LPSI Pump lB.
Proposed Answer: D Explanation (Optional):
Technical Reference(s): 1-NOP-Ol .04, RCS Reduced (Attach if not previously provided)
Inventory and Mid-Loop Operation.
l-NOP-03.05, Shutdown Cooling Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702801 Obj. 1 (As available) 11
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.45 6 55.45 13 Comments:
12
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 K/A# 026AA1.02 Importance Rating 3.2 Loss of component Cooling Water: Ability to operate and / or monitor the following as they apply to the Loss of component Cooling Water: Loads on the CCWS in the control room Proposed Question: RO 7 Unit 1 has entered 1-EOP-03, LOCA with the following conditions:
- RCS pressure 473 psia and slowly lowering
- RCS temperature 520°F and slowly lowering
- Pressurizer level off scale low
- Containment pressure 6.1 psig and slowly rising A total loss of Component Cooling Water (CCW) occurs. Which ONE of the following should be closely monitored as a result of the total loss of CCW?
A. Containment Spray pump seal coolers B. Letdown temperature C. RCP seal temperatures D. Containment pressure Proposed Answer: D 13
Explanation (Optional):
A. Containment pressure is below 10 psig Unit I CSAS setpoint. Containment Spray pumps will not be operating even though CCW was lost to the seal coolers. This would be viable on Unit 2 due to CSAS setpoint of 5.5 psig.
B. Letdown will be isolated due to LOCA. Letdown can be re-established later in the LOCA procedure, however Pressurizer level is off scale low.
C. RCP seal temperatures. This would be true if RCS subcooling criteria was met. Stated conditions require all RCPs to be stopped.
D. Correct. Containment temperature and pressure will rise. Also, Unit 1 has CCW to the Cooler motors whereas Unit 2 does not.
Technical Reference(s): 1-EOP-03 LOCA (Attach if not previously provided)
Lesson Text 0711209 Proposed references to be provided to applicants during examination: Steam tables Learning Objective: PSL OPS 0702209 Obj. 18 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.45 5 55.45 6 Corn ments:
14
Examination Outline Cross-reference: Level RO SRO Tier# I Group# 1 KIA# 027AK2.03 Importance Rating 2.6 Pressurizer Pressure Control System Knowledge of the interrelations between the Pressurizer Pressure Control Malfunctions and the following: Controllers and Positioners Proposed Question: RO 8 Given the following conditions on Uniti:
- The unit is operating at 100% power.
- PlC-i 11 OX, Pressurizer (Pzr) pressure controller is selected.
- Pzr pressure is being maintained at 2250 psia with Pzr Backup Heaters Bi, B2, and B5 ON with a 10% output to the Pzr Proportional Heaters.
The Output on PlC-I 11 OX begins to slowly drift HIGH due to a malfunction of PT-i ii OX.
Which ONE of the following describes the response of the OUTPUT on HIC1 100, Main Spray controller AND the effect on actual Pzr pressure?
(Assume no Operator actions)
HIC-1IOO output_(i)____
Actual Pzr pressure _(2)______
A. i)increases
- 2) rises B. I) increases
- 2) lowers C. i)decreases
- 2) lowers D. i)decreases
- 2) rises 15
Proposed Answer: B Explanation (Optional):
Applicant is required to know response of Pressurizer pressure controller output to sensor malfunctions including other controllers that receive output from them (namely Main Spray controller HIC-1 100).
A. Incorrect. 1st part is right but second part is wrong. Heaters go to minimum and de-energize while sprays open causing actual pressure to lower.
B. Correct. As PlC-ill OX drifts high, H IC-I 100 output increases (proportional heater output goes to minimum and sprays eventually begin to open). Because sprays open, actual pressure lowers.
C. Incorrect. 1st part wrong. 2 nd part right (see A).
D. Incorrect. Both parts wrong (output increases and pressure lowers).
Technical Reference(s): PSL OPS 0711206 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702206 obj 12 (As available)
PSL OPS 0702206 obj 18 Question Source: Bank # QID 1834 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: 55.45 7 Comments:
16
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 K/A # 029EK1 .05 Importance Rating 2.8 Knowledge of the operational implications of the following concepts as they apply to the ATWS: definition of negative temperature coefficient as applied to large PWR coolant systems Proposed Question: RO 9 Unit 1 has a loss of feedwater event at 100% power. The unit DID NOT TRIP when trip conditions were met.
For the initial onset of the event, which ONE of the following will be the MAJOR contributor of negative reactivity insertion?
The reactivity added by the increase in the:
A. fuel temperature. For the above event as the fuel temperature increases, this value becomes lower per °F.
B. fuel temperature. For the above event as the fuel temperature increases, this value becomes higher per °F.
C. moderator temperature. For the above event the core is under moderated resulting in this value becoming higher per °F.
D. moderator temperature. For the above event the core is over moderated resulting in this value becoming less per °F.
Proposed Answer: C 17
Explanation (Optional):
C. Correct Technical Reference(s): Lesson text 0711828 (Attach if not previously provided)
Handout NUC-GFP-RXT-004 Proposed references to be provided to applicants during examination:
Learning Objective: LP 0702107 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 x Comprehension or Analysis 10 CFR Part 55 Content: 55.45 3 Comments:
18
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 K/A # 038EG2.4.46 Importance Rating 4.2 Steam Gen. Tube Rupture: Ability to verify that the alarms are consistent with the plant conditions Proposed Question: RO 10 Unit I was operating at 100% power when the Steam Jet Air Ejector radiation monitor was trending up but has not reached the alarm setpoint. No other radiation monitors have an increasing trend. One minute later, a Turbine thrust bearing trip resulted in a Reactor trip.
While performing I -EOP-01, Standard Post Trip Actions which of the following ALARM would be used to verify WHICH Steam Generator has a possible tube leak?
A. Main Steam line radiation monitor.
B. Steam Jet Air Ejector radiation.
C. Steam Generator level.
D. Steam Generator blowdown radiation.
Proposed Answer: D 19
Explanation (Optional):
A. N 16 gamma is gone after the unit trip.
B. SJAE radiation will continue to show increasing trends but doe not identify which SG. This would be plausible if the affected SC MSIV was closed, SJAE trend would lower, helping to identify which SG had the tube leak, however the affected SG is not isolated in EOP-01.
C. The SG with the tube rupture would be the higher level but even with a double ended SGTR the leakage rate is -600 gpm. It is not possible to have a high SG level alarm while in EOP-01 strictly due to a tube rupture.
Increasing trend on level but not to the point of the high level alarm.
D. Correct. Blowdown radiation would alarm on the affected SC.
Technical Reference(s): 1-EOP-01, Standard Post Trip (Attach if not previously provided)
Actions Lesson text 0711825 Lesson text 0711410 Proposed references to be provided to applicants during examination:
Learning Objective: LP PSL OPS 0702825 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: 55.43 5 55.45 3,12 Comments:
20
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 K/A # CE/E05EK3.3 Importance Rating 3.8 Knowledge of the reasons for the following responses as they apply to the (Excess Steam Demand) Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.
Proposed Question: RO 11 Unit 1 has experienced an Excess Steam Demand event on the 1 B SG and has entered I -EOP 05, Excess Steam Demand with the following:
- 1A SG T Id is 500°F 0
- lB SG T ld is 240°F 0
- 1 B SG indicates 0 Wide Range
- 1A ADV is currently in automatic The US has directed you to stabilize RCS temperature. Which ONE of the following states how RCS temperature is controlled and the basis for this manipulation?
A. Maintain IA ADV in auto and adjust setpoint to 25 psia steam pressure.
This will maximize Safety Injection flow to regain Pressurizer level to within the RCS Inventory control safety function criteria.
B. Maintain IA ADV in auto and adjust setpoint to 25 psia steam pressure.
This will limit the RCS heatup which could result in exceeding the RCS subcooling limit.
C. Place IA ADV in manual, fully open, then adjust the auto setpoint to 25 psia steam pressure and place in automatic. This will maximize Safety Injection flow to regain Pressurizer level to within the RCS Inventory control safety function criteria.
D. Place 1A ADV in manual, fully open, then adjust the auto setpoint to 25 psia steam pressure and place in automatic. This will limit the RCS heatup which could result in exceeding the RCS subcooling limit.
Proposed Answer: D 21
Explanation (Optional):
A. Per OPS-539 the ADVs are to be opened in manual first, then palced in AUTO. This will facilitate the stabilization of RCS temperature faster. Maximizing SI flow in incorrect. This would result in the Pressurizer filling up causing excessive RCS pressure increase.
B. Maintaining in AUTO is not correct.
C. Increasing SI flow will result in RCS pressure increase and potential PTS concerns.
D. Correct.
Technical Reference(s): Lesson text 0711826 (Attach if not previously provided)
Ops policy OPS-539 1-EOP-05 ESD Proposed references to be provided to applicants during examination: Steam tables Learning Objective: LP 0702826 obj. 9, 14 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.45 6,13 Comments:
22
Examination Outline Cross-reference: Level RO SRO Tier# I Group# 1 K/A # CE/EO6EK1 .3 Importance Rating 3.2 Knowledge of the operational implications of the following concepts as they apply to the (Loss of Feedwater) Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Feedwater).
Proposed Question: RO 12 Unit I is at 45% power with the following conditions:
- IBAFW Pump is out of service.
The following alarm is received:
125V DC BUS lAB UV A-60 Shortly after the alarm, the I B Main Feedwater pump trips and cannot be restarted.
Which ONE of the following actions are taken in I -EOP-O1, Standard Post Trip Actions as a direct result of the above conditions?
A. Align the lAB DC bus to the IC or ID DC bus.
B. Align the lAB Battery Charger to the lAB DC bus.
C. Secure ALL RCPs.
D. Secure ONE RCP in EACH loop.
Proposed Answer: D 23
Explanation (Optional):
A. Plausible as the lAB DC bus CAN be lined to the C or D DC bus, but these are NON-VITAL DC busses and not directed on EOP-O1 B. Plausible as the lAB Battery Charger is normally on standby with the output breaker open, however this action is not performed in EOP-O1.
C. All RCPs are not required to be secured.
D. Correct Technical Reference(s): 1-EOP-Ol (Attach if not previously provided)
PSTG SPTA 1-22 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: 55.45 3 Comments:
24
Examination Outline Cross-reference: Level RO SRO Tier# I Group# I KIA# 055EK3.02 Importance Rating 4.3 Knowledge of the reasons for the following responses as the apply to the Station Blackout: Actions contained in EOP for loss of offsite and onsite power Proposed Question: RO 13 Given the following conditions:
- Unit 2 is in 2-EOP-1 0, Station Blackout receiving power via the Station Blackout Crosstie, to the 2AB 4.16KV bus to the 2A3 4.16KV bus from the IA Emergency Diesel Generator WHICH IS THE ONLY RUNNING UNIT 1 DIESEL.
Which ONE of the following states when / if the 2A Intake Cooling Water Pump can be started?
The 2A Intake Cooling Water pump can:
A. be started if Unit I has determined sufficient load capacity is available on the 1A Diesel Generator.
B. be started if Unit I has determined sufficient load capacity is available on the station blackout crosstie breaker.
C. NOT be started due to the potential for exceeding the station blackout crosstie breaker amperage.
D. NOT be stated due to the potential for exceeding the IA Diesel loading.
Proposed Answer: D 25
Explanation (Optional):
A. This would correct if BOTH Unit I Diesels were available.
B. This would be correct for any condition the crosstie breaker is closed EXCEPT when only one Diesel is supplying both units.
C. Plausible in that the procedure requires checking the amps on the AB bus frequently as equipment is restored.
D. Correct, ICW and COW pumps cannot be started if only one Diesel generator is supplying both units. The ICW pump is the largest load on the Diesel and has starting could result in an overload condition.
Technical Reference(s): 2-EOP-10. Station Blackout (Attach if not previously provided) 2-EOP-99, Appendices /
Figures / Tables / Data Sheets Appendix V PSTG SBO 2-40 Proposed references to be provided to applicants during examination:
Learning Objective: LP 0702830 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 x Comprehension or Analysis 10 CFR Part 55 Content: 55.45 6,13 26
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# I K/A# 056.AAI.07 Importance Rating 3.2 Ability to operate and / or monitor the following as they apply to the Loss of Offsite Power: Service water pump Proposed Question: RO 14 Unit 2 has the following Intake Cooling Water (ICW) system alignment at 100% power:
- 2A and 2B ICW pumps are running.
The 2C ICW pump was just started on the 2B ICW header for surveillance testing and the 28 ICW pump has yet to be stopped. A loss of offsite power occurs and both Diesel Generators start and load on the bus.
Which ONE of the following states the response of the 2C and 2B ICW pumps?
2B ICW Pump will:
A. automatically restart as the Diesel loads sequence on the bus.
2C ICW pump will NOT automatically restart and CANNOT be manually restarted.
B. NOT automatically restart but CAN be manually started.
2C ICW pump will automatically restart as the Diesel loads sequence on the bus.
C. NOT automatically restart and CANNOT be manually restarted.
2C ICW pump will automatically restart as the Diesel loads sequence on the bus.
D. automatically restart as the Diesel loads sequence on the bus.
2C ICW pump will NOT automatically restart but CAN be manually started.
Proposed Answer: D 27
Explanation (Optional):
A. Intake cooling water pumps are on Diesel load block 4, with a 9 second time delay. The CCW pumps will immediately restart upon diesel output breaker closure because their breakers do not open on a LOOP. They are on load block 1.
B. 2C lOW pump will not start.
C. Backwards. 2B starts not 2C D. Correct.
Technical Reference(s): Text 0711313 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702313 Obj, 4a (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: 55.45 5,6 Comments:
28
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# I KIA# 058AA1.02 Importance Rating 3.1 Ability to operate and I or monitor the following as they apply to the Loss of DC Power: Static inverter do input breaker, frequency meter, ac output breaker, and ground fault detector Proposed Question: RO 15 The 120 VDC input breaker spuriously opened and will not close on the 2C Instrument Inverter.
Which ONE of the following would be expected as a result of this malfunction?
2C Instrument bus:
A. Inverter trouble alarm only. The 480 VAC alternate source through the maintenance bypass bus will auto keep the Instrument bus energized.
B. Inverter trouble alarm only. The 120 VAC alternate source directly to the Instrument bus will autokeep the Instrument bus energized.
C. becomes de-energized. The Instrument bus should be re-energized by placing the 120 VAC manual bypass switch to the Bypass Source to Load position.
D. becomes de-energized. The Instrument bus should be re-energized by closing the 480 VAC MCC input breaker to the maintenance bypass bus.
Proposed Answer: C 29
Explanation (Optional):
A. Will receive trouble alarm but bus will be de-energized. The second part is true however this is a manual operation.
B. The alternate source first goes through the 480V maintenance bypass transformer. This is a manual operation.
C. Correct.
D. The 480 VAC MCC input breaker to the maintenance bypass bus is always maintained closed. The 120V manual breaker is the breaker manipulated.
Technical Reference(s): Lesson Text 0711503 (Attach if not previously provided) 2-AOP-49.02, 120V Instrument AC System (Class I E)
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702503 Obj. 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 x Comprehension or Analysis 10 CFR Part 55 Content: 55.45 5,6 Comments:
30
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 K/A# 062AA2.04 Importance Rating 2.5 Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: The normal values and upper limits for the temperatures of the components cooled by SWS Proposed Question: RO 16 Unit I is at 100% power with the IC ICW pump out of service. The IA ICW pump trips and cannot be restored.
Which ONE of the following will become the MOST LIMITING parameter for maintaining the current power level?
A. Main Generator cold gas temperature B. Turbine bearing oil temperature C. RCP seal temperatures D. Containment temperature Proposed Answer: A 31
Explanation (Optional):
A. Correct, generator cooling is the largest load on the Turbine Cooling Water system I Intake Cooling Water.
B. Plausible is that Turbine lube oil coolers are the second largest heat load.
C. RCP seal cooling is affected but Correct D. Both are acceptable, but distractor is plausible due to B has a higher CCW HX strainer DP and lower flow.
Technical Reference(s): 1-AOP-21 .03A, 1A Intake (Attach if not previously provided)
Cooling Water System Header Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702313 Obj. 17b (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: 55.45 13 Comments:
32
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 KIA# 065AG2.1.23 Importance Rating 4.3 Loss of Instrument Air I Ability to perform specific system and integrated plant procedures during all modes of plant operation.
Proposed Question: RO 17 Unit I is at 100% power when a large Instrument air leak occurs. The crew has implemented 1-AOP-1 8.01, Instrument Air Malfunction. If Instrument air continues to degrade, which ONE of the following states the HIGHEST pressure that requires the Unit to be manually tripped AND which procedure will be implemented AFTER 1-EOP-01 Standard Post Trip Actions?
A. 74 psig, 1-EOP-02, Reactor Trip Recovery B. 59 psig, 1-EOP-02, Reactor Trip Recovery C. 74 psig, 1-EOP-09, Loss of Offsite Power/Loss of Forced Circulation D. 59 psig, 1-EOP-09, Loss of Offsite Power/Loss of Forced Circulation Proposed Answer: D 33
Explanation (Optional):
A. 74 psig is pressure that requires evaluating a rapid downpower. Loss of air will result in loss of COW to the RCPs and loss of forced circulation.
B. 59 psig is correct for unit trip. 1-EOP-02 is not correct due to loss of RCPs C. 1-EOP-09 correct, 74 psig is not correct D. Correct Technical Reference(s): I -AOP-1 8, Instrument Air (Attach if not previously provided)
Malfunction Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702860 Obj. 2 (As available)
Question Source: Bank #
Modified Bank # 1548 (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: 55.45 2,6 Comments: Modified from bank to add AND which procedure will be implemented AFTER 1-EOP-01 Standard Post Trip Actions?
34
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 KIA# 077AK1.02 Importance Rating 3.3 Generator Voltage and Electric Grid Disturbances / Knowledge of the operational implications of the following concepts as they apply to Generator Voltage and Electric Grid Disturbances: Over-excitation Proposed Question: RO 18 Unit 1 is operating at 100% with the following:
- Main Generator Voltage regulator problems require the voltage regulator to be in the TEST mode.
A system disturbance results in switchyard voltage degrading to less than 230 KV and lowering.
Assuming no Operator actions, which ONE of the following states the protection circuit available for the above conditions?
A. Maximum Excitation Limiter (MXL) will automatically attempt to limit the excitation. The variable timer duration will vary inversely to the amount of over-excitation.
B. Over Excitation Protection (OXPK1) will disable the automatic adjuster follower circuit and pre-position the electronic DC adjuster to a setting corresponding to a safe excitation level.
C. Over Excitation Protection (OXPK2) will remove the AC regulator from service leaving the unit in DC regulator control and actuates an annunciator in the control room.
D. Over Excitation Protection (OXPK3) will trip the Turbine Generator by an Excitation Switchgear Trip PRI MARY LOCKOUT.
Proposed Answer: D 35
Explanation (Optional):
A. This would be the first protective circuit if the Voltage Regulator was in AUTO but because the voltage regulator is in TEST or manual this circuit is not available.
B. This would be the second protective circuit if the Voltage Regulator was in AUTO but because the voltage regulator is in TEST or manual this circuit is not available.
C. This would be the third protective circuit if the Voltage Regulator was in AUTO. This circuit places the voltage regulator in manual, however the regulator is already in manual.
D. Correct. The only protective circuit available for the above conditions.
Technical Reference(s): 1-AOP-53.01, Main Generator (Attach if not previously provided)
Lesson Text 0711307 Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702307 Obj. 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 x Comprehension or Analysis 10 CFR Part 55 Content: 55.45 8 Corn ments:
36
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 K/A# OOIAA2.04 Importance Rating 4.2 Ability to determine and interpret the following as they apply to the Continuous Rod Withdrawal: Reactor power and its trend Proposed Question: RO 19 Unit I is at 50% power with CEA group 7 at 118 withdrawn. CEA group 7 withdrew uncontrolled to the upper group stop. (Assume the Turbine load remains constant)
Actual reactor power will stabilize_____________ the initial power level and reactor coolant temperature will stabilize____________ the initial temperature.
A. at; at B. at; above C. above; at D. above; above Proposed Answer: B 37
Explanation (Optional):
A. Second part incorrect. Temperature rise due to steam flow constant. Rise in temperature adds negative reactivity.
B. Correct, rise in temperature adds negative reactivity offsetting positive reactivity from CEA withdraw.
C. Both parts incorrect. Power will initially rise but stream flow remaining constant will result in negative reactivity from temperature increase and power will return to original value.
D. See all of the above.
Technical Reference(s): Lesson Text 071110 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: NUC-GFPRXT-005 Obj. 2 (As available)
Question Source: Bank # NRC GFE QID P1054 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: 55.43 5 55.45 3,13 Comments:
38
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 KIA# 028AA1.01 Importance Rating 3.8 Pressurizer Level Malfunction / Ability to operate and / or monitor the following as they apply to the Pressurizer Level Control Malfunctions: PZR level reactor protection bistables (NOTE: per discussion w/chief examiner this K/A will focus on Pzr. Level and link to CVCS due to PSL RPS has no Pzr. Level protection bistables)
Proposed Question: RO 20 The Unit is at 100% power. Pressurizer level Channel X is selected.
- Pressurizer low / low level alarmed at 28% indicated level (actual level is 63%)
- Letdown flow is 29 gpm.
- All 480V heater supply contactors are open.
Which ONE of the following states the UNIT that has experienced the failure, the number of Charging pumps running and the Operator actions?
A. Unit 1. Three Charging pumps are running. Select Channel Y LOW LEVEL CUTOUT switch.
B. Unit 1. Two Charging pumps are running. Select LEVEL on the Backup Interlock Bypass keyswitch.
C. Unit 2. Three Charging pumps are running. Select Channel Y LOW LEVEL CUTOUT switch.
D. Unit 2. Two Charging pumps are running. Shift to Select LEVEL on the Backup Interlock Bypass keyswitch.
Proposed Answer: A 39
Explanation (Optional):
Unit I has Low level cutout switch, Unit 2 has Backup interlock bypass key switch. Unit 1 Low Low Low level alarms is 28%, Unit 2 is 27% level. Unit 1 low level starts first and second backup Charging pumps. Unit 2 only starts one backup Charging pump.
Technical Reference(s): Lesson Text 0711206 (Attach if not previously provided) 1 (2)-AOP-01 .10 Pressurizer Pressure and Level Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702206 Obj. 18e (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: 55.45 5,6 Comments:
40
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 KIA# 051AK3.01 Importance Rating 2.8 Knowledge of the reasons for the following responses as they apply to the Loss of Condenser Vacuum: Loss of steam dump capability upon loss of condenser vacuum Proposed Question: RO 21 Unit 1 is in Mode 3 with following:
- Steam Bypass Control System (SBCS) controllers are in AUTOMATIC controlling RCS Tave at 532° F.
- A problem with the Steam Jet Air Ejectors (SJAE) results in condenser backpressure going to 15 Hg absolute.
- The SJAE problem is resolved and condenser backpressure is now 5.5 Hg absolute.
- A cooldown to 500°F using SBCS is desired.
Which ONE of the following states:
- 1) The status of the SBCS when the SJAE problem is resolved
- 2) The operation of the SBCS to cooldown to 500°F A. 1) SBCS valves are closed until the Vacuum interlock pushbutton is depressed
- 2) Place the SBCS valve permissive interlock switch to Manual. Place HIC-8801 in manual and open PCV-8801 to obtain the desired cooldown rate.
B. 1) SBCS valve(s) are modulating to control RCS Tave at 532°F
- 2) Place the SBCS valve permissive interlock switch to Manual. Place HIC-8801 in manual and open PCV-8801 to obtain the desired cooldown rate.
C. 1) SBCS valves are closed until the Vacuum interlock pushbutton is depressed
- 2) Place master controller PIC-8010 in manual and adjust the controller thumbwheel to modulate open PCV-8801 to obtain the desired cooldown rate.
D. 1) SBCS valve(s) are modulating to control RCS Tave at 532°F
- 2) Place master controller PIC-8010 in manual and adjust the controller thumbwheel to modulate open PCV-8801 to obtain the desired cooldown rate.
Proposed Answer: B 41
Explanation (Optional):
A. Part 1 is not correct. If all SBCS valves are in automatic when vacuum regained vacuum interlock pushbutton is not required to be depressed and valves will modulate open as demand requires.
Part 2 is correct. Cooling down to 500°F (about 690 psia) requires the valve permissive interlock to be placed in manual or the SBCS valves will close at 806 psia.
B. Correct C. Both parts incorrect. Part 1: incorrect as stated above. Part 2: PIC-8010 controller is not adjustable.
D. Part 1 correct. Part 2 incorrect as stated above.
Technical Reference(s): Lesson text PSL OPS SYS 406 (Attach if not previously provided)
TXT.
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702406 Obj. 5 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.45 6,13 Comments:
42
Examination Outline Cross-reference: Level RO SRO Tier# I Group# 2 KIA# 059AG2.1.30 Importance Rating 4.4 Accidental Liquid RadWaste I Ability to locate and operate components, including local controls Proposed Question: RO 22 Unit I is performing a Liquid Release of the IA Waste Monitor Tank when the following alarm is received:
LIQUID WASTE RAD HIGH N-37 Liquid release flow control valve, FCV-6627X indicates open and will not close from the RTGB.
lAW 1-AOP-06.02, Uncontrolled Release Of Radioactive Liquids which ONE of the following is a required SUBSEQUENT Operator action?
A. At the IA Waste Monitor Tank, stop the IA Waste Monitor pump AND lock closed V21462, Waste Monitor Pumps Discharge to Discharge Canal Isolation valve.
B. At the IA Waste Monitor Storage Tank, close FCV-6627X AND lock closed V21462, Waste Monitor Pumps Discharge to Discharge Canal Isolation valve.
C. From the Liquid Waste Control panel, close FCV-6627X AND at the Waste Monitor Storage Tanks, stop the Waste Monitor pump associated with the liquid release.
D. From the Liquid Waste Control panel, stop the IA Waste Monitor pump AND lock closed V21462, Waste Monitor Pumps Discharge to Discharge Canal Isolation valve.
Proposed Answer: A 43
Explanation (Optional):
A. Correct B. FCV-6627X does not have local controls at the Waste Monitor Tank.
C. FCV-6627X has indication only at the local control panel.
D. The Waste Monitor pump can be stopped at the local panel but V21462 cannot be closed.
Technical Reference(s): 1-AOP-06.02, Uncontrolled (Attach if not previously provided)
Release of Radioactive Liquids.
Proposed references to be provided to applicants during examination:
Learning Objective: LP 0702861 Obj. 6 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.45 7 Comments:
44
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 KIA# O6OAK1.O1 Importance Rating 2.5 Knowledge of the operational implications of the following concepts as they apply to Accidental Gaseous Radwaste Release:
Types of radiation, their units of intensity and the location of sources of radiation in a nuclear reactor power plant Proposed Question: RO 23 The following conditions exist:
- New Fuel is being loaded into the Unit 1 Fuel Handling Building.
- A new fuel assembly is dropped from the New Fuel Hoist and several fuel pins are ruptured.
Which ONE of the following describes the response of the Fuel Handling Building Effluent AND Area radiation monitors?
of the radiation monitors would be in alarm due to A. NEITHER; the low energy level of Alpha radiation B. NEITHER; the type of detectors used does not sense Alpha radiation C. BOTH; the release of Beta radiation from Iodine and Xenon D. BOTH; the release of Beta radiation from Rubidium, Tellurium and Cesium 45
Proposed Answer: B Explanation (Optional):
A. Incorrrect. The FHB process and area rad monitors only detect gamma and beta radiation. IF New Fuel cladding is breached, Uranium Oxide pellets will be exposed to the atmosphere (approx 5 mR alpha type radiation hazard). However, there are no permanently installed alpha radiation detectors in the Fuel Handling Bldg.
B. Correct. There are no permanently installed alpha radiation detectors in the Fuel Handling Bldg. The FHB process and area rad monitors only detect gamma and beta radiation.
C. Incorrect. The FHB process and area rad monitors only detect gamma and beta radiation. However, new fuel only poses an alpha radiation exposure hazard D. Incorrect. The FHB process and area rad monitors only detect gamma and beta radiation. However, new fuel only poses an alpha radiation exposure hazard.
Technical Reference(s): 0711411 Table 5 (Attach if not previously provided) 0702832 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: 41.8 I 41.10 I 45.3)
Comments:
46
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 K/A# 069AK3.01 Importance Rating 3.8 Knowledge of the reasons for the following responses as they apply to the Loss of Containment Integrity: Guidance contained in EOP for loss of containment integrity.
Proposed Question: RO 24 Unit 1 is implementing 1-EOP-15, Functional Recovery with the following:
- A Loss of Offsite Power (LOOP) has occurred.
- IA Steam Generator (SG) has experienced a Steam Generator Tube Rupture (SGTR).
- 18 SG has an Excess Steam Demand outside the Containment upstream of the Main Steam Isolation valves.
- 1 B SG pressure is 454 psia.
- Neither SG has been isolated.
Which ONE of the following states:
- 1) When the Containment Isolation Safety Function will be met?
- 2) Bases for meeting the Safety Function A. 1) When 1 -EOP-99 Appendix R, Steam Generator Isolation is complete on the 1 B SG AND the IA SG is capable of being steamed ONLY to the condenser.
- 2) Steaming to the condenser contains the radiological effluents.
B. 1) When 1-EOP-99 Appendix R, Steam Generator Isolation is complete on theiB SG AND the IA SG is capable of being steamed to the condenser OR the atmosphere.
- 2) The 1A SG is the least affected SG and has the capability to remove heat by steaming to atmosphere or condenser.
C. 1) When 1-EOP-99 Appendix R, Steam Generator Isolation is complete on BOTH SGs AND Once Through Cooling is initiated.
- 2) Both SGs are considered faulted and should be isolated.
D. 1) When 1-EOP-99 Appendix R, Steam Generator Isolation is complete on the 1A SG AND the 1 B SG has blown dry.
47
Proposed Answer: B Explanation (Optional):
A. In this case the most affected SC is the ESD SC, 1 B. To meet the safety function the most affected SC must be isolated lAW 1-EOP-99 Appendix R, Steam Cenerator Isolation. The EOP does NOT require the SC with the tube rupture to steam to the condenser to meet the containment isolation safety function.
B. Correct C. CEN-152 mentions OTC as a last resort but our EOP specifies OTC only if both SCs are not capable of RCS heat removal, i.e. total loss of feedwater.
D. D. 1-EOP-99 Appendix R, Steam Cenerator Isolation will be performed on the I B (most affected) True statement that RCS cooldown cannot be controlled until 1 B SC blown dry, but this is not a criteria to meet containment isolation safety function.
Technical Reference(s): 1-EOP-15, Functional (Attach if not previously provided)
Recovery CEN152 page no. FR/Cl 1-5 Proposed references to be provided to applicants during examination:
Learning Objective: LP 0702828 Obj. 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: 55.45 6,13 Comments:
48
Examination Outline Cross-reference: Level RO SRO Tier# I Group# 2 K/A # 074EK1 .04 Importance Rating 3.7 Knowledge of the operational implications of the following concepts as they apply to the Inadequate Core Cooling : Use of steam tables, including subcooled, saturated, and superheated regions Proposed Question: RO 25 Given the following conditions on Unit 2:
- Safety injection flow does NOT meet Figure 2
- The crew is performing actions contained in 2-EOP-15, Functional Recovery Plant conditions are now:
- RCS THOt temperatures are 51 9°F constant.
- RCS Tcold temperatures are 512°F constant.
- RCS pressure indication is 870 psia.
Which ONE of the following states the status of RCS subcooling and Natural Circulation?
A. RCS is 9°F subcooled, Single phase Natural Circulation is NOT met.
B. RCS is 11°F superheat, Two phase Natural Circulation IS met.
C. RCS is 9°F subcooled, Single phase Natural Circulation IS met.
D. RCS is 11°F superheat, Two phase Natural Circulation is NOT met.
Proposed Answer: D Explanation (Optional):
A. Subcooling incorrect (must use REP CET not TH t).
0 B. Two phase incorrect due to SI flow not meeting figure 2.
C. RCS subcooling must be calculated using Rep CET due to no RCPs running (SIAS requires stopping RCPs)
D. Correct based on SI flow not meeting Figure 2 49
Technical Reference(s): Steam tables (Attach if not previously provided)
Lesson plan 0702828 Proposed references to be provided to applicants during examination: Stm. Tables Learning Objective: LP 0702828 Obj. 8 (As available)
Question Source: Bank # 2005 Minor changes to meet St. Lucie Callaway plant specifics.
NRC exam 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: 55.45 3 Comments:
50
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 KIA# CA13AK2.2 Importance Rating 3.4 Knowledge of the interrelations between the (Natural Circulation Operations) and the following: Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
Proposed Question: RO 26 Unit 1 is performing a natural circulation cooldown in accordance with 1-EOP-03 using the ADVs with the following conditions:
- RCS pressure is 140 psia and lowering.
- Rep CET temperature is 335°F and constant.
- Hot leg temperature is 325°F and constant.
- Cold leg temperature is 320°F and lowering.
- Reactor Vessel Head temperature (QSPDS Pg. 211) is 353°F and constant.
Which ONE of the following states the required actions?
Throttle:
A. open the ADVs further and close SE-02-03.
B. open the ADVs further and open SE-02-04.
C. closed the ADVs and close SE-02-03.
D. closed the ADVs and open SE-02-04.
Proposed Answer: A 51
Explanation (Optional):
A. Correct, subcooling is not met, therefore cooldown and stop depressurization by closing the aux spray valve.
B. This implies RCS pressure is too high and temperature is to high.
C. This implies temperature and pressure are to low.
D. This implies temperature is too low and RCS pressure is too high.
Technical Reference(s): 1-AOP-O1.13, Natural (Attach if not previously provided)
Circulation Cooldown Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702858 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: 55.45 7 Comments:
52
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 K/A# CA11AAI.2 Importance Rating 3.2 Ability to operate and I or monitor the following as they apply to the (RCS Overcooling) Operating behavior characteristics of the facility Proposed Question: RO 27 Unit 2 was tripped from 100% power due to a 200 gpm RCS leak. 2-EOP-03, LOCA is being implemented.
The following conditions exist:
- A Loss of offiste power has occurred
- Cooldown is in progress using the ADVs in AUTO/MANUAL
- RCS Th t is 498° F 0
- Auxiliary Feedwater was throttled after AFAS actuation
- SIAS has just occurrred Following SIAS actuation, which ONE of the following states the Operator actions that must be performed to prevent a cooldown in excess of 2-EOP-03 guidelines?
A. Throttle closed AFW header valves to both SGs.
B. Lower ADV controller output.
C. Reduce ECCS flow by throttling HPSI valves.
D. Close the MSIVs.
Proposed Answer: A 53
Explanation (Optional):
A. Correct. SIAS will open the Diesel output breakers and re-sequence the loading. The previously throttled AFW valves will go full open and must be throttled back to prevent excessive cooldown.
B. ADV position will not change C. Because SIAS has just occurred (1720 psia) ECCS flow is still above shutoff head of HPSI pumps (1250 psia).
D. MSIVs are procedurally directed to be closed on a LOOP to protect the main condenser only.
Technical Reference(s): PSL OPS SYS 412 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: LP 0702412 Obj. 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: 55.45 6,13 Comments:
54
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KIA# 003A4.02 Importance Rating 2.9 Reactor Coolant Pump: Ability to manually operate and/or monitor in the control room: RCP motor parameters.
Proposed Question: RO 28 Unit 1 is at 100% power. The Containment Instrument Air Compressors are out of service. MV-18-1, Instrument air Containment isolation valve closes and cannot be re-opened. Which ONE of the following Reactor Coolant Pump motor indications would be expected?
A. Increasing Upper I Lower oil reservoir levels.
B. Increasing motor stator temperatures.
C. Decreasing CCW flow to motor oil coolers.
D. Decreasing Upper I Lower oil reservoir levels.
Proposed Answer: D 55
Explanation (Optional):
A. Oil reservoir indication fails low due to bubbler level system.
B. CCW cools the air leaving the RCP not entering the RCP. COW is NOT lost to RCP motors on Unit 1.
C. This would be true on Unit 2 due to two CCW isolation valves located in Containment, failing closed on loss of Instrument air. Unit I does not have CCW isolation valves in Containment, thus no loss of CCW.
D. Correct Technical Reference(s): 1-AOP-1 8.01, Instrument Air (Attach if not previously provided)
Malfunction PSL OPS 0702202 Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702202 Obj. 19d (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.45 5,8 Comments:
56
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KIA# 004K3.04 Importance Rating 3.7 Chemical and Volume Control : Knowledge of the effect that a loss or malfunction of the CVCS will have on the following: RCPS Proposed Question: RO 29 Unit 1 is in Mode 5. RCS level is 30 feet 6 inches with RCP seal injection in service. Two Charging pumps are in service with the 1A LPSI pump filling the RCS.
The Charging Loop isolation valves are as follows:
- SE-02-01, IB1 Loop Charging Isol is OPEN
- SE-02-02, 1A2 Loop Charging Isol is CLOSED A short circuit causes SE-02-01, 1 B1 Loop Charging Isol to fail closed.
Which ONE of the following states the effect of SE-02-01 closing on the RCP seals?
Seal injection flow has:
A. decreased which could cause contaminants to enter the seal cartridge as the RCS level is raised.
B. decreased which could result in the seal cavity not filling completely.
C. increased which could result in excessive vapor seal leakoff flow.
D. increased which could result in extreme seal damage.
Proposed Answer: D Explanation (Optional):
A. This is a true statement but not for the stated condition. Both Charging loop isolation valves being closed results in increase seal injection flow, not decreased flow.
B. Flow increases not decreases. If actual flow decreased, this would be true.
C. If applicant did not understand where seal injection enters the RCP they could believe vapor seal lea koff to increase.
D. Correct.
57
Technical Reference(s): 1-NOP-02.02, Charging and (Attach if not previously provided)
Letdown Rev. 43 Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702202 Obj. 3g (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: 55.45 7,8 Comments:
58
Examination Outline Cross-reference: Level RD SRO Tier# 2 Group# 1 K/A# 004K5.30 Importance Rating 3.8 Chemical and Volume control : Knowledge of the operational implications of the following concepts as they apply to the CVCS:
Relationship between temperature and pressure in cvcs components during solid plant operation Proposed Question: RO 30 Unit 1 is on SDC. The Pressurizer is being cooled and has just gone solid. RCS pressure is 75 psia.
A loss of SDC occurs.
Assuming NO Operator actions, which ONE of the following states:
- 1) How Letdown valve controller will be configured for solid plant operations and
- 2) How Letdown valves will respond to the loss of SDC?
A. 1) PIC-2201, Ltdn Pressure controller will be in AUTO.
- 2) Letdown pressure control valves PCV-2201P and PCV-2201Q will OPEN.
B. 1) PIC-2201, Ltdn Pressure controller will be in AUTO.
- 2) Letdown pressure control valves PCV-2201 P and PCV-2201 Q will CLOSE.
C. 1) HIC-1100, Pzr Level Ltdn Cntl Vlv will be in AUTO.
- 2) Letdown level control valves LCV-21 lop and LCV-21 1OQ will OPEN.
D. 1) HIC-1 100, Pzr Level Ltdn Cntl Vlv will be in AUTO.
- 2) Letdown level control valves LCV-21 lOP and LCV-21 1OQ will CLOSE.
Proposed Answer: A 59
Explanation (Optional):
A. Correct, RCS heatup will result in pressure increase and PCVs opening in response to increase pressure.
B. Plausible due to normal operation the PCVs close to increase pressure in the Letdown heat exchanger.
C. Level control valves are in manual and full open for this configuration.
D. Level control valves are in manual and full open for this configuration.
Technical Reference(s): 1-GOP-305, Reactor Plant (Attach if not previously provided)
Cooldown Hot Standby To Cold Shutdown. Appendix F Proposed references to be provided to applicants during examination:
Learning Objective: LP 0702205 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: 55.45 7 Comments:
60
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KIA# 005A4.01 Importance Rating 3.6 Residual Heat Removal: Ability to manually operate and/or monitor in the control room: Controls and indication for RHR pumps Proposed Question: RO 31 Unit 1 has just placed 1A LPSI pump on SDC with the following:
- RCS temperature is 320°F
- RCS pressure is 262 psia
- HCV-3657 SDC TEMP CONTROL is open 100%
- FCV-3306 SDC RETURN FLOW is being throttled closed from 100% and is open 25%
Instrument air to the RAB is lost due to a ruptured air header line.
Which ONE of the following states the expected response?
LPSI amps will:
A. increase, RCS temperature will decrease.
B. decrease, RCS temperature will increase.
C. increase, RCS temperature will increase.
D. not change, RCS temperature will not change.
Proposed Answer: B Explanation (Optional):
NOTE: HCV 3657 fails closed on loss of Instrument air, FCV-3306 fails open on loss of Instrument air. (Not applicable on Unit 2 as these valves are MOVs)
A. Amps (flow) will not significantly change due to FCV-3306 goes full open and HCV-3657 goes full closed. This will result in no SDC flow going through the SDC heat exchanger resulting in increasing RCS temperature. (note: this would be true if Unit 2 question due to Unit 2 valves are MOVs and loss of air has no affect)
B. Correct, going from one valve at 100% open and another at 25% open to one valve at 100% and the other fully closed will decrease amps. All LPSI flow is now isolated from the SDC heat exchanger and RCS temperature will increase.
C. Little or no change to LPSI amps D. This would be correct if student thought both valves failed open on loss of air.
61
Technical Reference(s): PSL OPS 0711207 (Attach if not previously provided) 1-NOP-03.05, Shutdown Cooling Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702207 Obj. 24.f (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: 55.45 5,8 Comments:
62
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# I KIA# 006A1.05 Importance Rating 2.9 Emergency Core Cooling: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: CCW flow (establish flow to RHR heat exchanger prior to placing in service)
Proposed Question: RO 32 Unit I is experiencing a Large Break LOCA and is implementing I-EOP-15, Functional Recovery with the following:
- RWT level is 8 feet.
- All ECCS pumps are available Due to equipment problems, RAS preparation steps are unable to be performed.
Which ONE of the following states the possible effects of not being able to perform the RAS preparation steps?
A. Containment cooling may be jeopardized.
B. Containment sump PH limit may be jeopardized.
C. HPSI Pumps NPSH may be jeopardized.
D. LPSI Pumps may not stop on RAS.
Proposed Answer: C Explanation (Optional):
A. Portions of Containment Spray, after the SDC heat exchanger (cooled by CCW), is manually aligned to the suction of the HPSI pumps to ensure NPSH after RAS.
Containment spray flow I cooling is not jeopardized, thus Containment cooling is not jeopardized.
B. Plausible as the NAOH is injected via the Containment Spray system.
C. Correct, portions Containment spray is directed through the SDC Hx, cooled by CCW, to the suction of the HPSI pumps to ensure HPSI pump NPSH (note: this alignment is only performed on Unit 1)
D. LPSI pumps are placed in the STOP position AFTER RAS. Plausible if the applicant believes LPSI pumps are placed in STOP just before RAS.
63
Technical Reference(s): 1-EOP-15, Functiona Recovery (Attach if not previously provided)
Lesson text 0711207 Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702207 Obj. 5b, 12d (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: 55.45 5 Comments:
64
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# I KIA# 007G2.4.6 Importance Rating 3.7 Pressurizer Relief/Quench Tank: Knowledge of EOP mitigation strategies Proposed Question: RO 33 Unit 1 has tripped from 100% power due to a Main Generator Lockout. A few minutes after the trip, the RCO noticed:
- Quench Tank pressure is 58 psig
- Pressurizer level is 41% and rising
- Pressurizer pressure is 1800 psia and lowering
- RCS temperature is 530°F Which ONE of the following contingency actions would the crew be expected to take while in EOP-01, Standard Post Trip Actions?
A. Trip one RCP in each loop.
B. Stop the running Charging pumps.
C. Close PORV block valves.
D. Energize Pressurizer heaters.
Proposed Answer: C 65
Explanation (Optional):
A. All RCPs required to be stopped when SIAS has actuated at 1600 psia.
B. Stopping Charging pumps with lowering subcooling would aggravate the event.
C. Correct, <2300 psia close/isolate PORVs.
A. With given RCS pressure, SIAS will have resulted in Pressurizer heaters lockout Technical Reference(s): 1-EOP-01, Standard Post Trip (Attach if not previously provided)
Actions Proposed references to be provided to applicants during examination:
Learning Objective: 0702822-05 (As available)
Question Source: Bank # 2008 NRC Exam 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: 41.10 43.5 45.13 Comments:
66
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KIA# 008K2.02 Importance Rating 3.0 Knowledge of bus power supplies to the following: CCW pump, including emergency backup Proposed Question: RO 34 Unit 1 is at 100% power. The IA Component Cooling water (CCW) pump is to be removed from service. The 1C CCW is to be aligned to replace the 1A CCW pump.
Which ONE of the following states the MINIMUM electrical lineup required to meet the Technical Specification requirements for the 2C CCW pump?
A. ONLY the lAB 4.16 KV bus aligned to the 1A3 4.16KV bus.
B. The lAB 4.16 KV bus aligned to the 1A3 4.16KV bus and the lAB 480V bus aligned to the 1A2 480V bus.
C. The lAB 4.16 KV bus aligned to the 1A3 4.16KV bus, lAB 480V bus aligned to the 1A2 480V bus and the lAB DC bus aligned to the IA DC bus.
D. lAB 4.16 KV bus aligned to the 1A3 4.16KV bus, lAB 480V bus aligned to the 1A2 480V bus, lAB DC bus aligned to the 1A DC bus. 1A Emergency Diesel Generator operable.
Proposed Answer: C Explanation (Optional):
A. Aligning the lAB 4.16 KV bus to the 1A3 is required but NOT the minimum to meet T.S.
B. Both alignments required but NOT minimum to meet T.S.
C. Correct D. IA Emergency Diesel Generator operable is NOT required to declare the IC CCW operable. This would be true if the I B CCW was not operable.
Technical Reference(s): 1-AOP-14.01 CCW Abnormal (Attach if not previously provided)
Operations Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702862 Obj. 3 (As available) 67
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:
68
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KIA# 010K6.01 Importance Rating 2.7 Pressurizer Pressure Control: Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: Pressure detection systems Proposed Question: RO 35 Unit I is operating at 50% power. The Pressurizer was placed on recirculation lAW 1-GOP-I 01, Reactor Operating Guidelines During Steady State and Scheduled Load Changes.
PlC-I I OOX is selected for Pressure control. PT-il OOX fails HIGH.
Assuming NO Operator action, which ONE of the following states the response of the Proportional and Backup heaters?
Proportional heaters:
A. at MINIMUM output, Backup heaters are de-energized.
B. are de-energized. Backup heaters are de-energized.
C. at MINIMUM output. Backup heaters stay at the position prior to the failure.
D. are de-energized. Backup heaters stay at the position prior to the failure.
Proposed Answer: C 69
Explanation (Optional):
A. MINIMUM output is correct but the BU heaters remain energized B. This would be the correct answer if Unit 2 question. On Unit 2, all heaters are de energized at 2340 psia. Unit I does not have this feature.
C. Correct D. Unit I proportional heaters do not de-energize, they go to minimum output.
Technical Reference(s): Lesson Text 0711206 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: 0702206 Ob]. 18f (As available)
Question Source: Bank # 1834 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: 41.7 45.7 Comments:
70
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KJA# 012A1.O1 Importance Rating 2.9 Reactor Protection: Ability to predict and/or monitor Changes in parameters (to prevent exceeding design limits) associated with operating the RPS controls including: Trip setpoint adjustment.
Proposed Question: RO 36 Given the following indications on Unit 1 during an up power.
- Channel D Variable High Power (VHP) reset pushbutton has just been depressed.
- Channel D liT Power indicate 57%
- Channel D Nuclear Power indicates 55%
Assuming no Operator actions, which ONE of the following states the power level at which Channel D will trip?
A. 66.61%
B. 64.61%
C. 61%
D. 59%
Proposed Answer: A 71
Explanation (Optional):
Depressing the VHP reset pushbutton resets the VHP trip setpointto 9.61% above current value. (highest of Nuc. Or AT Power)
A. Correct.
B. This is the pre-trip setpoint. (7.61% above)
C. This would be correct if the reset pushbutton has NOT been depressed. Pushbutton reset light illuminates at 4% below trip setpoint. In this case 4% from AT Power.
D. 4% from nuclear.
Technical Reference(s): LP 0711404 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702404 Obj. 4a (As available)
Question Source: Bank #
Modified Bank # QID 2476 (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: 41.5 45.5 Comments:
72
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KIA# 012G2.4.2 Importance Rating 4.5 Reactor Protection: Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
Proposed Question: RO 37 Unit I is performing a startup with the following:
- Reactor power is 10%
- Turbine is latched
- SBCS is in service
- RPS Channel A Startup rate has failed high and is yet to be bypassed.
- Both SG pressures are 900 psia Which ONE of the following will result in the crew entering 1-EOP-01, Standard Post Trip Actions?
A. Startup rate spikes to 1.6 DPM on the B channel.
B. DEH pump trips and the backup will not start.
C. HCV-08-1A, A MISV fails closed. A SC pressure increases to 950 psia.
D. MB Instrument bus becomes de-energized.
Proposed Answer: D 73
Explanation (Optional):
A. SUR trip is 2.49 DPM, bypassed above 15% power B. Loss of load is bypassed at <11% power C. ASGT is 70 psid SGs delta D. Correct, loss of Instrument bus with SUR yet to be bypassed results in 2/4 logic and plant trip.
Technical Reference(s): LP 0711404 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: LP PSL OPS 0702404 Obj. 4 (As available)
Question Source: Bank #
Modified Bank # QID 492 (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: 41.7 45.7 45.8 Comments:
74
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KIA# 013A2.01 Importance Rating 4.6 Engineered Safety Features Actuation: Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: LOCA Proposed Question: RO 38 Unit 1 is experiencing a Loss of Coolant Accident (LOCA) and has entered 1-EOP-03, LOCA with the following conditions:
- Pressurizer pressure is 1580 psia and lowering
- Containment pressure is 5.5 psig and rising
- Containment radiation is 8 R/hr and rising
- ONLY SIAS has actuated Which ONE of the following states response of the Engineered Safety Feature Actuation System (ESFAS) and the expected Operator actions?
A. The ESFAS system is responding as expected. Verify proper operation of pumps and valves.
B. The ESFAS system is responding as expected. Manually actuate CIAS AND CSAS in anticipation of imminent automatic actuation.
C. CIAS should have actuated automatically. Manually actuate CIAS.
D. CIAS and CSAS should have actuated automatically. Manually actuate CIAS and CSAS.
Proposed Answer: C Explanation (Optional):
A. If SIAS was the only expected ESFAS, this would be the correct answer. Operators are to verify proper operation of pumps and valves on SIAS actuation.
B. At PSL Operators are NOT permitted to manually actuate ANY ESFAS signal in anticipation of upcoming automatic actuation.
C. Correct. CIAS actuates with SIAS D. This would be correct if this was a Unit 2 question. Unit 2 CSAS setpoint is 5.4 psig. Unit 1 is 10 psig.
75
Technical Reference(s): Ops Policy OPS-523 (Attach if not previously provided) 1-EOP-03 LOCA Proposed references to be provided to applicants during examination:
Learning Objective: 0702824 Obj. 18 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 41.5 43.5 45.3 45.13 Comments:
76
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KIA# 013A3.02 Importance Rating 4.1 Engineered Safety Features Actuation: Ability to monitor automatic operation of the ESFAS including: Operation of actuated equipment Proposed Question: RO 39 Unit 1 is in 1-EOP-03, LOCA, with the following:
- Pressurizer pressure is 980 psia
- 1A HPSI did not start and cannot be started
- All Charging pumps are operating Which ONE of the following states the expected Safety Injection flow?
References provided A. 530 gpm B. 400 gpm C. 330 gpm D. 220 gpm Proposed Answer: D Explanation (Optional):
A. If applicant used two trains and added the flow of the Charging pumps B. If applicant used two trains alone C. If applicant used one train and added the flow of the Charging pumps D. Correct, one train SI flow. Charging pump flow (132 gpm for three pumps) is NOT added to this figure.
Technical Reference(s): 1-EOP-99, Figure 2 SI flow VS. (Attach if not previously provided)
RCS pressure Proposed references to be provided to applicants during examination: 1-EOP-99 Figure 2 SI flow VS. RCS pressure 77
Learning Objective: LP 0702824 Obj. 17 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 41.7 45.5 Comments:
78
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KIA# 022K2.01 Importance Rating 3.0 Knowledge of power supplies to the following: Containment cooling fans Proposed Question: RO 40 Unit 2 has experienced a LOCA. RCS pressure is 1580 psia and the crew has entered 2-EOP-03, LOCA.
On the trip, feeder breakers to MCC 2B9 tripped.
Which ONE of the following states the RUNNING Containment Fan Coolers?
A. C and D Containment Fan Coolers.
B. A and C Containment Fan Coolers.
C. A and B Containment Fan Coolers.
D. B and D Containment Fan Coolers.
Proposed Answer: C 79
Explanation (Optional):
A. MCC 2B9 supplies Containment fans coolers IC and ID.
B. Plausible, as the B 120V DC bus supplies B and D instrument inverters.
C. Correct D. Plausible, as the B 120V DC bus supplies B and D instrument inverters.
Technical Reference(s): 0711502 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702210 Obj. 7b, 14a (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:
80
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 022K4.02 Importance Rating 3.1 Knowledge of CCS design feature(s) and/or interlock(s) which provide for the following: Correlation of fan speed and flowpath changes with containment pressure.
Proposed Question: RO 41 Unit 2 has tripped from 100% power. Fifteen minutes post trip the following conditions are observed:
- Containment temperature is 130°F
- Containment Pressure is 3.8 psig Which ONE of the following states the status of the Containment Coolers
- 1) PRIOR to the event and
- 2) AFTER the above stated conditions A. 1) Three Coolers running in FAST speed
- 2) Four Coolers running in FAST speed B. 1) Four Coolers running in SLOW speed
- 2) Four Coolers running in SLOW speed C. 1) Three Coolers running in FAST speed
- 2) Four Coolers running in SLOW speed D. 1) Four Coolers running in SLOW speed
- 2) Four Coolers running in FAST speed Proposed Answer: C Explanation (Optional):
Normal operation of Containment Coolers are three fans running in FAST speed. SlAS (3.5 psig Containment Pressure) starts all four Containment Coolers in SLOW speed.
SLOW speed basis is, Diesel loading consideration due to dense moisture laden Containment air drawing higher current from Containment fan cooler motors.
81
Technical Reference(s): Lesson Text 0711207 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702210 Obj. 14 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New X Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 41.7 Comments:
82
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KIA# 026A1.03 Importance Rating 3.5 Containment Spray: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment sump level.
Proposed Question: RO 42 Unit I has experienced a Large Break Loss of Coolant Accident. 1-EOP-03, LOCA is in use.
Prior to the event RWT level was 36.5 feet. RAS occurred about 20 minutes ago. The IA and lB Containment Spray pump flow indication is oscillating between 1800 gpm and 3000 gpm.
Which ONE of the following states:
- 1) The expected current Containment sump level.
- 2) The Operator actions associated with the Containment Spray pump flow oscillations.
(references provided)
A. 1) 23.75 feet
- 2) Close Spray Header valve FCV-07-1A and FCV-07-1B.
B. 1) 23.75 feet
- 2) Stop the Containment Spray pumps C. 1) 24feet
- 2) Close Spray Header valve FCV-07-IA and FCV-07-1 B.
D. 1) 24feet
- 2) Stop the Containment Spray pumps 83
Proposed Answer: D Explanation (Optional):
A. Both incorrect. Figure 9 starting at RWT level 36 feet to RAS setpoint (<4 ft.) indicates 24 feet in containment sump. If used Unit 2 RAS setpoint 23.75 is correct. FCV-07-IA and FCV-07-1 B are not to be closed. Plausible as RHR (LPSI) valves are closed if flow oscillations while in reduced inventory.
B. Part 1 incorrect. Part 2 correct. NOTE: This would be the correct answer if asked on Unit
- 2. (Unit 2 RAS setpoint is 6 feet not 4 feet)
C. Part 1 correct Part 2 incorrect.
D. Correct Technical Reference(s): 1-EOP-99 Figure 9 (Attach if not previously provided) 1-EOP-03, LOCA Proposed references to be provided to applicants during examination: 1-EOP-99 Figure 9 Learning Objective: PSL OPS 0702210 Obj. 4b (As available) 0702824 Obj. 17 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 45.5 Comments:
84
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A # 026AK3.02 Importance Rating 4.2 Containment Spray: Knowledge of the effect that a loss or malfunction of the CSS will have on the following: Recirculation spray system Proposed Question: RO 43 Unit I is experiencing a large break loss of coolant accident and is implementing 1-EOP-03, LOCA with the following:
- The 1A Containment Spray pump is out of service.
- The 1A HPSI pump is out of service.
- All Containment Coolers are running.
- RAS has occurred and the I B Containment Spray pump tripped and cannot be restarted.
Which ONE of the following states the status of Core cooling AND Containment cooling.
A. 1) Core cooling CANNOT be maintained.
- 2) Containment cooling CAN be maintained.
B. 1) Core cooling CAN be maintained.
- 2) Containment cooling CAN be maintained.
C. 1) Core cooling CANNOT be maintained.
- 2) Containment cooling CANNOT be maintained.
D. 1) Core cooling CAN be maintained.
- 2) Containment cooling CANNOT be maintained.
Proposed Answer: B 85
Explanation (Optional):
Alignment of Cooled Containment Spray to the suction of the HPSI pumps is not required for core cooling.
On Unit 1, four Containment Coolers are 100% Containment heat removal capacity.
Technical Reference(s): UFSAR 6.3.2.1.2 (Attach if not previously provided)
Lesson Text 0711207 Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702210 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: 41.7 45.6 Comments:
86
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# I KIA# 039A2.04 Importance Rating 3.4 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: Malfunctioning steam dump Proposed Question: RO 44 Given the following conditions
- Unit I is at 3% power following a Short Notice Outage.
- Prior to that, the unit had been on line for 200 days.
- RCS temperature is being controlled with Atmospheric Dump Valves (ADVs) in automatic.
- The Main Steam Isolation valves are closed.
- A manual Reactor trip is inserted due to loss of Instrument air.
- Following the trip, a Loss of Offsite Power (LOOP) occurs.
Which ONE of the following states how RCS Heat Removal will be controlled?
While implementing EOP-09 LOOP, RCS Heat Removal will be controlled by:
A. the Main Steam Safeties cycling until local control is established using 1-EOP-99, Appendix U, Local Operation of Unit I Atmosphere Dump valves.
B. the Main Steam Safeties cycling until Instrument air is restored using 1-AOP-18.01, Instrument air Malfunction.
C. placing the ADV controllers in manual / manual closed until local control is established using 1-EOP-99, Appendix U, Local Operation of Unit 1 Atmosphere Dump valves.
D. placing the ADV controllers in manual I manual closed until Instrument air is restored using 1-AOP-18.01, Instrument air Malfunction.
Proposed Answer: A 87
Explanation (Optional):
A. Correct, MSSVs will open and cycle to control SG pressure due to Unit 1 ADVs are air operated fail closed valves. EOP-99 Appendix U is only guidance to locally control ADVs.
B. 1-AOP-18.01, Instrument air Malfunction will be implemented but has no guidance for local operation of the ADVs.
C. Placing the ADVs in manual I manual is a Unit 2 function when loss of AC power occurs.
On Unit 1, placing in manual and closed is plausible if applicant believes the ADVs fail open on loss of instrument air.
D. Both incorrect Technical Reference(s): 1-EOP-99 Appendix U, Local (Attach if not previously provided)
Operation of the ADVs Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702304 Obj. 9c (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:
88
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# I KIA# 059K1.05 Importance Rating 3.1 Main Feedwater: Knowledge of the physical connections and/or cause-effect relationships between the MFW and the following systems: RIDS Proposed Question: RO 45 Given the following:
- Unit 1 is at 60% power
- The 1A MFW pump trips Which ONE of the following describes the expected plant response:
- 1) RCS Tcold will increase on:
- 2) SIG water level:
A. 1)alI 4 cold legs
- 2) lower due to shrink B. 1) A cold legs only
- 2) lower due to shrink C. 1)all 4 cold legs
- 2) increase due to swell D. 1) A cold legs only
- 2) increase due to swell Proposed Answer: A 89
Explanation (Optional):
A. Plausible if applicant thinks that the differential temperature across the SG rises which equates to a higher tT power B. Correct C. Plausible if applicant thinks less feedwater implies greater boiling in tube bundle D. Plausible if applicant associates increase in SG level due to heatup implies a greater heat transfer area exists in the SC with a subsequent contraction of the RCS.
Technical Reference(s): Lesson Text 0711827 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: 0702827 Obj. 2 (As available)
Question Source: Bank # 2004 PSL NRC 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: 41.2 to 41.9 45.7 to 45.8 Comments:
90
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# I KJA# 061K5.02 Importance Rating 3.2 Auxiliary/Emergency Feedwater: Knowledge of the operational implications of the following concepts as they apply to the AFW:
Decay heat sources and magnitude.
Proposed Question: RO 46 Unit 1 has been at 100% power for 282 days. If the Unit lost all Main Feedwater and tripped on low SG level, which ONE of the following states the MINIMUM Auxiliary Feedwater capacity to remove decay heat, cool the primary and allow the SG level to recover?
A. One motor driven pump, assuming the Operator trips ALL Reactor Coolant pumps.
B. One motor driven pump, assuming the Operator trips TVVO Reactor Coolant pumps.
C. The steam driven pump, assuming the Operator trips ALL Reactor Coolant pumps.
D. The steam driven pump, assuming the Operator trips TWO Reactor Coolant pumps.
Proposed Answer: B Explanation (Optional):
A. Analysis is tripping TWO RCPs not ALL B. Correct C. The steam driven pump is twice the capacity of the motor driven pump, thus not MINIMUM.
D. Same as C Technical Reference(s): Unit 1 FSAR Chapter 10 Page (Attach if not previously provided) 10.5-5, 10.5-12d Proposed references to be provided to applicants during examination:
Learning Objective: 0702822 Obj. 8 (As available)
Question Source: Bank #
91
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 45.7 Comments:
92
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# I KIA# 062K4.OI Importance Rating 2.6 AC Electrical Distribution: Knowledge of ac distribution system design feature(s)and/or interlock(s) which provide for the following:
Bus lockouts Proposed Question: RO 47 Which ONE of the following will result is a:
- 1) Bus Lockout on the 1A2 4.16KV bus?
And
- 2) What is the result of the bus lockout?
A. 1) Degraded voltage condition.
- 2) 1A Diesel Generator starts and its output breaker CLOSES on the 1A3 4.16KV bus.
B. 1) Degraded voltage condition.
- 2) 1A Diesel Generator starts but its output breaker DOES NOT CLOSE on the 1A3 4.16KV bus.
C. 1) Differential current between phases.
- 2) 1A Diesel Generator starts and its output breaker CLOSES on the 1A3 4.16KV bus.
D. 1) Differential current between phases.
Proposed Answer: C 93
Explanation (Optional):
A. Bus lockout will cause all power sources to the bus to open and the Diesel to start but not close in on the bus. Previous experience shows a loss of the 1A3 4.16KV bus will not result in a unit trip within a few seconds.
B. Degraded voltage (18 sec time delay) on 1A3 bus will start the Diesel generator and open the tie breakers but not result in unit trip.
C. Correct. This will result in loss of the bus which results in loss of Condensate pumps etc.
which will result in loss of the Main Feedwater pumps and unit trip.
D. Must have SIAS, CIAS, or MSIS signal to initiate load shedding and Diesel start.
Technical Reference(s): Lesson text 0711502 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702502 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: 41.7 Comments:
94
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# I KIA# 062K4.06 Importance Rating 2.9 AC Electrical Distribution: Knowledge of ac distribution system design feature(s)and/or interlock(s) which provide for the following:
One-line diagram of 6.9kv distribution, including sources of normal and alternative power Proposed Question: RO 48 On the 6.9KV busses, the AUTOMATIC transfer from the I to the 2 is considered a 3 transfer.
A. 1. Auxiliary Transformers
- 2. Startup Transformers
- 3. Live Bus B. 1. Startup Transformers
- 2. Auxiliary Transformers
- 3. Fast Dead Bus C. 1. Auxiliary Transformers
- 2. Startup Transformers
- 3. Fast Dead Bus D. 1. Startup Transformers
- 2. Auxiliary Transformers
- 3. Live Bus Proposed Answer: C 95
Explanation (Optional):
A. An AUTOMATIC transfer ONLY occurs from the auxiliary to the startup transformers.
This is considered a Fast Dead bus transfer. A live bus transfer is only done during a MANUAL transfer.
B. Transferring from the startup to the auxiliary transformers is ONLY a manual operation.
C. Correct D. See above Technical Reference(s): Lesson Text 0711502 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702502 Obj. 4b, 4c (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:
96
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KIA# 063K3.O1 Importance Rating 3.7 DC Electrical Distribution: Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following:
ED/G Proposed Question: RO 49 Unit I A Diesel Generator is running fully loaded during a surveillance. A loss of 125V DC power to the 1A Diesel Voltage and Governor control occurs.
Which ONE of the following states the effect of losing the above DC power?
The IA Diesel will:
A. continue to run fully loaded but will not respond to Operator demands for load changes.
B. continue to run at minimum load due to the governor failing to its lowest setting.
C. trip on mechanical overspeed.
D. trip on loss of excitation.
Proposed Answer: A Explanation (Optional):
A. Correct, DC power controls air start solenoids B. Will not start due to air start solenoids not energized. Other DC power dependent: field flash, governor control, lockout relay.
C. Same as B D. Same as B Technical Reference(s): PSL OPS 0711501 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702501 Obj. 8 (As available) 97
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 45.6 Comments:
98
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KJA# 064K1.05 Importance Rating 3.4 Emergency Diesel Generator: Knowledge of the physical connections and/or cause-effect relationships between the ED/G system and the following systems: Starting Air Systems Proposed Question: RO 50 The Unit 2 SNPO has reported the following local Emergency Diesel Generator alarm on the 2A Diesel. All the air receivers indicate 138 psig.
STARTING AIR PRESS LOW 5-1 While investigating the alarm the SNPO also noticed the air dryer system indicated PINK.
Which ONE of the following states the Starting I Operability status of the 2A Diesel?
The air pressure is:
A. sufficient to start the Diesel but the Diesel must be declared INOPERABLE due to air pressure below the minimum required.
B. sufficient to start the Diesel. The Diesel is considered INOPERABLE as the Air Dryer Package is considered OUT OF SERVICE.
C. sufficient to start the Diesel. The Diesel is considered OPERABLE as the air pressure is above the minimum required.
D. NOT sufficient to start the Diesel AND the Air Dryer Package is considered OUT OF SERVICE the Diesel must be declared INOPERABLE.
Proposed Answer: C Explanation (Optional):
99
A. Air pressure is adequate to start the Diesel AND the air pressure is above the minimum required of 129 psig.
B. The air dryer is not considered out of service unless the dryer package indicates RED.
Even if it indicated RED the Diesel is not required to be declared OOS.
C. Correct. All receivers above the minimum pressure of 129 psig.
D. Pressure is adequate to start the Diesel and air receivers above the minimum.
Technical Reference(s): 2-ARP-06-A1 7 (Attach if not previously provided) 2-OSP-59.01A 2A EDG Monthly Su rveil lance.
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702501 Obj. 15b (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: 41.2 to 41.9 45.7 to 45.8 Comments:
100
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KIA# 064K6.08 Importance Rating 3.2 Emergency Diesel Generator: Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system:: Fuel oil storage tanks.
Proposed Question: RO 51 Unit 1 Diesel Generator fuel oil storage tanks have been severely damaged due to tornados on site. BOTH Unit 1 fuel oil storage tanks have been breached and contain no oil.
Unit 2 Diesel Generator fuel oil storage tanks were unaffected.
Which ONE of the following states the MAXIMUM Diesel Generators that can be run and the MAXIMUM run time for the above condition?
A. All Diesel Generators fully loaded for a period of three (3) days.
B. All Diesel Generators fully loaded for a period of seven (7) days.
C. One (1) Diesel generator fully loaded on each Unit for a period of seven (7) days.
D. One (1) Diesel generator fully loaded on each Unit for a period of three (3) days.
Proposed Answer: C Explanation (Optional):
A. Unit 2 Diesel Generator storage tanks have more than twice the capacity of Unit 1 tanks.
Unit I tanks are not missile protected. Unit 2 tanks are enclosed in concrete barriers.
Three days plausible as the T.S for a Diesel being taken out of service due to un-planned maintenance is three days.
Technical Reference(s): Lesson Text PSL OPS 0711501 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702501 Obj. lie (As available) 101
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 45.7 Comments:
102
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A # 073A4.03 Importance Rating 3.1 Process Radiation Monitoring: Ability to manually operate and/or monitor in the control room: Check source for operability demonstration Proposed Question: RO 52 Given the following conditions on Unit 1:
- A new check source has just been installed on the 1A Steam Generator Blowdown Radiation monitor.
- During testing, the Check Source pushbutton was depressed.
Which ONE of the following states the response of the 1A Steam Generator Blowdown isolation and sample valves (below), as a result of depressing the CHECK SOURCE (CS) button?
- FCV-23-4 Inside Containment
- FCV-23-3 Outside Containment
- FCV-23-7 Sample Valve A. ONLY FCV-23-3 and FCV-23-7 close B. ONLY FCV-23-3 and FCV-23-4 close C. ONLY FCV-23-4 and FCV-23-7 close D. ALL of the above valves close Proposed Answer: D 103
Explanation (Optional):
Note: On Unit 1 all the above valves will close on Hi Rad, i.e. depressing the Check Source pushbutton. On Unit 2 the inside containment valve FCV-23-4 does not get a Hi Rad closure signal. FCV-23-4 will receive a closure signal from Pressure switch PS-23-3 at 600 psia on the blowdown line. If this was a Unit 2 question the correct answer would be A.
Technical Reference(s): Text 0711410, 0511023 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702410 Obj. 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 x Comprehension or Analysis 10 CFR Part 55 Content: 41.7 45.5 to 45.8 Comments:
Combined the two bank questions to make a two part question.
104
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A # 076G2.2.3 Importance Rating 3.8 Service Water: Knowledge of the design, procedural, and operational differences between units.
Proposed Question: RO 53 At 100% power, on Unit if two Intake Cooling Water Pumps are electrically aligned AND operating on the same electrical bus in Mode 1, the associated must be declared inoperable.
A. One (1), Diesel Generator B. One (1), Off-Site Power Source C. Two (2), Diesel Generator D. Two (2), Off-Site Power Source Proposed Answer: B Explanation (Optional):
A. Unit I correct, Diesel not correct.
B. Correct, if two ICW pumps are operating on the same electrical bus, this could result in degraded voltage.
C. Both incorrect D. Unit 2 not correct Technical Reference(s): 1-NOP-21.03A 1A Intake (Attach if not previously provided)
Cooling Water System Operation.
OPS policy OPS-503, Ref, CR 2006-21661 Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702313 Obj. 10 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x 105
Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 41.5 41.6 41.7 41.10 45.12 Comments:
106
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KIA# 078K1.05 Importance Rating 3.4 Instrument Air: Knowledge of the physical connections and/or cause-effect relationships between the lAS and the following systems:
MSIV air Proposed Question: RO 54 Both Units are in MODE 3 with the following:
- Main Steam Isolation valves (MSIVs) are CLOSED
- The secondary steam system is DEPRESSURIZED.
- SC pressures are 900 psia
- RCS pressure is 2250 psia The following alarm is received:
MSIV HCV-08-1 A AIR PRESS LOW!
DC FAILURE Which ONE of the following states the response of HCV-08-1A on UNIT 1 AND UNIT 2?
If the alarm was due to:
A. DC failure ONLY, Unit 1 HCV-08-1A will open and Unit 2 HCV-08-1A will open.
B. DC failure ONLY, Unit 1 HCV-08-1A will open and Unit 2 HCV-08-1A will stay closed.
C. total loss of air pressure ONLY, Unit 1 HCV-08-IA will stay closed and Unit 2 HCV-08-1A will stay closed D. total loss of air pressure ONLY, Unit 1 HCV-08-IA will open and Unit 2 HCV 08-lA will open.
107
Proposed Answer: C Explanation (Optional):
NOTE: MSIVs fail open on loss of DC power and fail closed on loss of air pressure.
A. This would be true IF both MSIVs were already open on loss of DC power but due to design differences between Units, Unit 1 will not open against full steam pressure tip. As stated in stem the secondary steam system is depressurized with the MSIVs closed.
B. This is backwards. Unit I MSIV will stay closed (due to tp across the Unit 1 MSIV) and Unit 2 MSIV will open (Unit 2 will open against full 1p).
C. Correct D. Both MSIVs close on loss of air.
Technical Reference(s): PSL OPS 0711304 (Attach if not previously provided) 1 -ARP-0 1 -Q47 2-ARP-01-P47 Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702304 Obj. 9c (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: 41.2 to 41.9 45.7 to 45.8 Comments:
108
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# I KIA# 103A3.01 Importance Rating 3.9 Containment: Ability to monitor automatic operation of the containment system, including: Containment Isolation Proposed Question: RO 55 Unit 1 is operating at 100% power. PT-07-2A, Containment Pressure transmitter failed high and has yet to be bypassed. A loss of the MD instrument bus occurs.
Which ONE of the following defines ALL the ESFAS signals that will actuate?
A. CIAS, CSAS, MSIS and SIAS B. CSAS,SIAS C. CIAS, MSIS and SIAS D. CIAS,SIAS Proposed Answer: D Explanation (Optional):
A. CSAS is energize to actuate. On Unit I MSIS DOES NOT actuate on high containment pressure. This is only a Unit 2 function only.
B. CSAS is energize to actuate.
C. On Unit 1 MSIS DOES NOT actuate on high containment pressure. This is only a Unit 2 function.
D. Correct.
Technical Reference(s): Lesson Text 0711401 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: Lesson Plan 0702401 Obj. 8 (As available)
Question Source: Bank # 2004 Modified Bank # (Note changes or attach parent)
New 109
Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 41.7 45.5 Comments:
110
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 KIA# 002K1.03 Importance Rating 3.8 Reactor Coolant: Knowledge of the physical connections and/or cause-effect relationships between the RCS and the following systems: Borated water storage tank.
Proposed Question: RO 56 Unit I is in 1-EOP-03, LOCA with a LOOP and the 1A Emergency Diesel Generator out of service. Pressurizer pressure is 1350 psia. It is ten (10) minutes into the event.
Which ONE of the following states the suction source for the Charging Pumps?
A. Volume Control Tank B. Refueling Water Tank C. Boric Acid Makeup Tanks via the Gravity feeds V-2508 and V-2509.
D. Boric Acid Makeup Tanks via the Emergency Borate valve V-2514.
Proposed Answer: C Explanation (Optional):
A. VCT is the normal flowpath with NO SIAS present. RCS pressure of 1350 psia will result in SIAS and the VCT outlet valve closing.
B. Refueling Water Tank will be the suction source when the BAMTs lower to between 20-30% as per 1-EOP-03. This will occur much later in the event and when SIAS can be reset.
C. Correct, gravity feeds powered from the B side.
D. A power is not available so the Boric Acid makeup pumps and V-2514 is not available.
Technical Reference(s): Lesson text 0711205 (Attach if not previously provided) 1-EOP-03, LOCA Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702205 Obj. 5 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent) 111
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 41.2 to 41.9 45.7 to 45.8 Comments:
112
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 KIA# 015K2.01 Importance Rating 3.3 Nuclear Instrumentation: Knowledge of bus power supplies to the following: NIS channels, components, and interconnections Proposed Question: RO 57 Unit 1 is at 100% power with the following RPS indications:
- Two (2) K relays Ki and K2 are de-energized.
- Two (2) logic matrix relays open.
- Channel A Wide Range Nuclear channel indicating 0.
- Channel A Linear Range Nuclear channel indicating 0.
Which ONE or the following states the failure that has caused the above condition and the status of the RPS Trip Circuit Breakers (TCBs)?
A loss of:
A. A Instrument bus. Four (4) TCBs are open.
B. A Instrument bus. Two (2) TCBs are open.
C. A CEA MG set. Four (4) TCBs are open.
D. A 125V DC bus. Eight (8) TCBs are open.
Proposed Answer: A Explanation (Optional):
A. Correct, each K relay operates two TCBs. Two logic matrix relays will open two K relays.
B. Loss of Instrument bus will result in four TCBs opening.
C. Loss of one CEA MG set will have no effect as long as the other MG set is operating and the bus tie breaker is closed, which is the normal operating practice.
D. A loss of A DC bus will result in a loss of two instrument busses, four K relays opening and eight TCBs opening.
113
Technical Reference(s): Lesson Text 0711404 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702404 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: 41.7 Comments:
114
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 KIA# 016K5.O1 Importance Rating 2.7 Non-nuclear Instrumentation: Knowledge of the operational implication of the following concepts as they apply to the NNIS:
Separation of control and protection circuits Proposed Question: RO 58 Unit 1 is at 100% power steady state.
Steam Generator (SC) level transmitter LT-9013A, IA SC Safety Channel level transmitter failed low.
No Operator actions have been taken when SG level transmitter LT-9023A, 1 B SG Safety Channel level transmitter fails low.
Which ONE of the following states the plant response AT THIS TIME?
Main Feedwater Regulating Valve (MFRV) controller and the SG low level RPS channel A bistable A. goes to manual; goes to trip.
B. goes to manual; stays in its current state.
C. stays in its current operational mode; goes to trip.
D. stays in its current operational mode; stays in its current state.
115
Proposed Answer: C Explanation (Optional):
A. The LTs-9013/23 A,B,C,D are safety related channels that have an input to the RPS. They also have an input to the Main Feedwater control for a HIGH SG level condition only. High level conditions will close MFRVs, stop Main Feedwater pumps and trip the turbine but a SG high level condition does not have a direct input to the RPS. A turbine trip on high SG level will trip the Reactor. The MFRV going to manual would be correct if the SG level transmitter was LT-901 I or LT-9021.
B. Neither is correct. (above)
C. Correct A. RPS channel A bistable goes to trip Technical Reference(s): Lesson Text 0711408 (Attach if not previously provided)
Lesson Text 0711404 Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702408 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: 41.6 43 Comments:
116
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 KIA# 017G2.4.21 Importance Rating 4.0 In-core Temperature Monitor: Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
Proposed Question: RO 59 Unit I has tripped from 100% power and has entered 1-EOP-03, LOCA with the following conditions:
- Prior to the trip the A QSPDS was out of service
- When 1-EOP-03 was entered, an electrical malfunction resulted in the B QSPDS becoming out of service.
- All RCPs are off Which ONE of the following states ALL the Safety Functions that will NOT be able to be ASSESSED due to the status of the QSPDS system?
A. RCS Inventory Control and RCS Heat Removal B. RCS Inventory Control and Core Heat Removal C. RCS Heat Removal and Core Heat Removal D. RCS Pressure Control, Core Heat Removal and RCS Heat removal.
Proposed Answer: B Explanation (Optional):
A. RCS Inventory is correct BUT NOT ALL Safety Functions. Core Heat removal will not be able to be assessed due to loss of CETs. QSPDS uses Heated Junction Thermocouples to determine liquid level in the Reactor vessel. Without these HJTC available, RCS Inventory Control will not be able to be assessed. RCS Heat removal CAN be assessed by TOId which can be obtained on RTGB.
B. Correct C. RCS Heat removal CAN be assessed by T Id which can be obtained on RTGB.
0 D. Pressure Control CAN be assessed by Th t and RCS pressure which can be obtained on 0
RTGB.
117
Technical Reference(s): Lesson Text 0711407 (Attach if not previously provided) 1-EOP-03, LOCA Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702407 Obj. 6 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 41.7 43.5 45.12 Comments:
118
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 KIA# 033K3.03 Importance Rating 3.0 Spent Fuel Pool Cooling: Knowledge of the effect that a loss or malfunction of the Spent Fuel Pool Cooling System will have on the following: Spent fuel temperature Proposed Question: RO 60 Unit 2 is in 2-EOP-03, LOCA. Pressurizer pressure is 1580 psia.
Spent Fuel Pool temperature will:
A. continue to rise until the CCW N header is restored to the Fuel Pool heat exchangers.
B. continue to rise until the CCW MOVs to I from the Fuel Pool heat exchangers are opened from the A or B essential headers by taking the switches to SIAS OVERRIDE OPEN.
C. continue to rise until SIAS is reset and the CCW MOVs to I from the Fuel Pool heat exchangers are opened from the A or B essential headers by taking the switches to LOCKED CLOSED and return to OPEN.
D. remain stable due to Fuel Pool heat exchanger CCW MOVs to / from the Fuel Pool heat exchanges remaining open on SIAS.
Proposed Answer: C Explanation (Optional):
A. This would be correct if question was Unit 1 as Unit 1 Fuel Pool heat exchanger is supplied by the CCW N header. Unit 2 Fuel Pool heat exchangers are supplied by the essential COW A OR B headers.
B. Switches do not have SIAS override, however plausible as many switches do have SIAS override such as the COW N header valves.
- 0. Correct, SIAS must be reset and valves taken to LOCKED CLOSED and return to OPEN.
D. These valves get a SIAS close signal and can not be opened until SIAS reset.
Technical Reference(s): PSL OPS 0711209 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
119
Learning Objective: PSL OPS 0702209 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: 41.7 45.6 Comments:
120
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 KIA# 034K6.02 Importance Rating 2.6 Fuel Handling Equipment: Knowledge of the effect of a loss or malfunction on the following will have on the Fuel Handling System Radiation monitoring systems Proposed Question: RO 61 Unit 2 is in refueling operations performing a full core offload.
Which ONE of the following radiation monitors, if it were to fail high, would immediately require fuel handling operations to stop after the fuel bundle has been placed in a safe condition?
A. CIAS area monitor RR-26-3 B. Containment Process Particulate and Gas monitor RC-26-25 C. Spent Fuel area monitor RIM-26-7 D. Spent Fuel process monitor RR-26-2 Proposed Answer: A Explanation (Optional):
NOTE: There is no direct correlation or automatic action associated with radiation monitoring and Fuel Handling systems.
A. Correct, a single CIAS monitor failing high will result in a Containment evacuation alarm which requires a mandatory Containment evacuation PRIOR to verifying the validity of the alarm.
B. Determine alarm validity is first step C. Determine alarm validity is first step D. Determine alarm validity is first step Technical Reference(s): 2-AOP-26.02, Area Radiation (Attach if not previously provided)
Monitors 2-AOP-26.01, Process Radiation Monitors Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702411 Obj. 11 .h (As available) 121
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 45.7 Comments:
122
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 KIA# 045A2.17 Importance Rating 2.7 Main Turbine Generator: Ability to (a) predict the impacts of the following malfunctions or operation on the MT/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Malfunction of electrohydraulic control Proposed Question: RO 62 Unit I has implemented 1-AOP-22.O1, Rapid Downpower due to a Main Feedwater control problem. The Unit was at 97% power when the Operator noticed the following light illuminated on the DEH panel:
Trans(fer) relay 24 V Monitor Which ONE of the following states the status of DEH control and how the down power will be controlled.
A. Remain in Operator Auto but should be placed in Manual. The Governor Valves will be in SINGLE VALVE CONTROL and the down power will continue by programming the load rate in the DEH computer.
B. Remain in Operator Auto but should be placed in Manual. The Governor Valves will be in SEQUENTIAL VALVE CONTROL and the down power will continue by programming the load rate in the DEH computer.
C. Swapped to Turbine Manual, the Governor Valves will be in SINGLE VALVE CONTROL and the down power will continue by adjusting the load using GV LOWER pushbuttons.
D. Swapped to Turbine Manual, the Governor Valves will be in SEQUENTIAL VALVE CONTROL and the down power will continue by adjusting the load using GV LOWER pushbuttons.
Proposed Answer: C 123
Explanation (Optional):
A. The DEH will be in turbine manual. DEH swapping to turbine manual places governor control in SINGLE VALVE control using GV LOWER pushbutton to lower load.
B. The DEH will be in turbine manual, SINGLE VALVE.
C. Correct D. When in Turbine Manual the GVs will be in SINGLE VALVE control.
Technical Reference(s): Lesson text 0711409 DEH (Attach if not previously provided)
Control System 1-AOP-22.03, DEH Turbine Control System Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702409 Obj. 11, 14 (As available)
Question Source: Bank #
Modified Bank # (Note changes or attach parent)
New x Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 41.5 43.5 45.3 45.5 Comments:
124
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 KIA# 056A2.04 Importance Rating 2.6 Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of condensate pumps Proposed Question: RO 63 Unit 1 is at 52% power performing an up power to 100% with the following:
- 1A and I B Main Feedwater pumps are running.
- 1A and 10 Condensate pumps are running.
The 1C Condensate pump trips. Steam Generator levels are 63% and slowly lowering.
Which of the following states:
- 1. the plant response
- 2. the procedure to be implemented The 1 B Main Feedwater Pump will trip:
A. 1) as a DIRECT result of the IC Condensate pump tripping.
- 2) 1-AOP-09.04, Feedwater, Condensate, And Heater Drain Pump Abnormal Operations.
B. 1) as a DIRECT result of the IC Condensate pump tripping.
- 2) 1-AOP-09.01, Feedwater Control System Abnormal Operations.
C. 1) on low suction pressure.
- 2) 1-AOP-09.04, Feedwater, Condensate, And Heater Drain Pump Abnormal Operations.
D. 1) on low suction pressure
- 2) 1-AOP-09.01, Feedwater Control System Abnormal Operations.
Proposed Answer: A 125
Explanation (Optional):
A. Correct B. Feedwater control system procedure plausible as the SG levels will trend lower which is an entry condition for 1-AOP-09.01 but only if adequate FW flow is available to recover SG levels.
C. Above 50% power Condensate pump tripping will result in a direct tripping of the same train Feedwater pump.
D. Both incorrect.
Technical Reference(s): 1-AOP-09.04, Feedwater, (Attach if not previously provided)
Condensate, or Heater Drain Pump Abnormal Operations 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 45.5 Comments:
126
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 K/A# 071A1.06 Importance Rating 2.5 Waste Gas Disposal: Ability to predict and/or monitor changes in parameters(to prevent exceeding design limits) associated with Waste Gas Disposal System operating the controls including: Ventilation system Proposed Question: RO 64 Unit 1 is performing a Gas release of the IA Gas Decay Tank.
Which ONE of the following will result in an AUTOMATIC termination of this release?
A. Waste Gas discharge radiation monitor, blue fail light is illuminated.
B. Plant Vent Exhaust monitor channel 01-05 goes into HIGH alarm.
C. The running RAB Supply fan, HVS-4A trips.
D. The running RAB exhaust fan, HVE-1 OA trips.
Proposed Answer: D Explanation (Optional):
A. The blue fail light is normally illuminated. If extinguished, the release will be terminated.
B. The plant vent radiation monitor has no AUTOMATIC function. If monitor does go into alarm Operator action is required to terminate the release.
C. Supply fan tripped will not terminate the release.
D. Correct. Release valve V6565 is interlocked with either RAB exhaust fans tripping.
Technical Reference(s): Lesson text 0511019 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0502019 Obj. 10 (As available)
Question Source: Bank #
Modified Bank # 3732 (Note changes or attach parent)
New
Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge ( 3 Corn prehension or Analysis 10 CFR Part 55 Content: 41.5 45.5 Comments:
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 KIA# 075K4.01 Importance Rating 2.5 Circulating Water: Knowledge of circulating water system design feature(s) and interlock(s) which provide for the following: Heat sink Proposed Question: RO 65 Unit I is operating at 85% power with 1A1, 181 andi B2 Circulating Water Pumps (CWP) running. In preparation to increase power to 100%, the Operator starts the 1A2 CWP.
Three (3) minutes after starting the 1A2 CWP the 1B2 CWP trips.
Which ONE of the following states the status of the CWPs?
A. IAI and 181 CWPs will be running.
B. 1A1 and 1A2 CWPs will be running.
C. 1A2 and IB1 CWPs will be running.
D. IA1, 1A2 and IBI CWPs will be running.
Proposed Answer: A Explanation (Optional):
A. Correct, 1AI and IB1 are parallel pumps (both discharge into common discharge tunnel). If parallel pump trips (1 B2) during the first 5 minutes of the second pump startup, the second pump will also trip (1A2).
B. Plausible if applicant does not know what CWP discharges into what tunnel and does not know the trip logic of the CWPs.
C. Plausible if applicant does not know what CWP discharges into what tunnel and does not know the trip logic of the CWPs.
D. This would be true if the I B2 CWP tripped 6 mihutes after starting the I A2 CWP.
Technical Reference(s): Lesson Text 0711314 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702314 Obj. 4a (As available) 129
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:
130
Examination Outline Cross-reference: Level RO SRO Tier# 3 Group # I KIA# 2.1.17 Importance Rating 3.9 Conduct of Operations: Ability to make accurate, clear, and concise verbal reports.
Proposed Question: RO 66 You are the RO at the controls when the following unexpected alarm is received:
E PZR CHANNEL X LEVEL HIGH/LOW In accordance with Operations Department Policy, which ONE of the following states the correct order to respond to this alarm?
A. Silence the alarm, acknowledge the alarm, announce what the alarm is to the Unit Supervisor.
B. Silence the alarm, announce what the alarm is to the Unit Supervisor, acknowledge the alarm.
C. Announce the alarm to the Unit Supervisor, silence the alarm, acknowledge the alarm.
D. Announce the alarm to the Unit Supervisor, acknowledge the alarm, silence the alarm.
Proposed Answer: B Explanation (Optional):
Correct order: silence the alarm, announce the alarm to the US, acknowledge the alarm.
Technical Reference(s): Operations Department Policy (Attach if not previously provided)
OPS-522, Annunciator
Response
Proposed references to be provided to applicants during examination:
Learning Objective: (As available) 131
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 45.12 45.13 Comments:
132
Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 1 KIA# 2.1.37 Importance Rating 4.3 conduct of Operations: Knowledge of procedures, guidelines, or limitations associated with reactivity management.
Proposed Question: RO 67 Given the following conditions:
- Unit 1 is in Mode 5 with Shutdown Cooling in service.
Which ONE of the following states the MINIMUM Shutdown Cooling flow necessary in accordance with procedural and Tech Spec requirements to perform the above evolution?
A. 6000 GPM B. 5000 GPM C. 3000 GPM D. 1000 GPM Proposed Answer: C Explanation (Optional):
3000 gpm based on minimum flow for mixing during dilution Technical Reference(s): T.S. 3.1.1.3 Boron Dilution (Attach if not previously provided)
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 133
Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 41.1 43.6 45.6 Comments:
134
Examination Outline Crossreference: Level RO SRO Tier# 3 Group# 1 KIA# 2.1.5 Importance Rating 2.9 Conduct of Operations: Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
Proposed Question: RO 68 Both Units are operating at 100% power with the following shift Complement:
- OneSM
- Two USs (one per Unit)
- Four ROs (two per Unit)
- Two SNPOs (one per Unit)
- Two NPOs (one per Unit)
- Two ANPOs (one per Unit)
- One STA All individuals from above, normally assigned to the fire brigade are qualified as their position dictates.
One of the SN P0ssuddenly becomes very ill and has left to go home.
What actions, if any, must be taken to ensure minimum shift complement and minimum fire brigade complement?
A. The SNPO position MUST be filled within two (2) hours to meet the minimum shift complement. The minimum fire brigade complement IS still met.
B. The SNPO position MUST be filled within two (2) hours to meet the minimum shift complement and the minimum fire brigade complement.
C. No action is required. The minimum shift complement IS still met and the minimum fire brigade complement IS still met.
D. The minimum shift complement IS still met. The fire brigade complement must be filled within two (2) hours.
Proposed Answer: A 135
Explanation (Optional):
A. Correct B. Fire Brigade minimum is one leader (SNPO) and four members. Even with one SNPO gone minimum staffing is met.
C. Minimum is not met with SNPO gone.
D. Fire Brigade is met with SNPO gone.
Technical Reference(s): Operations Department Policy (Attach if not previously provided)
OPS-201 Shift Compliment Rev. 9 Operations Department Policy OPS-207, Fire Brigade 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 43.5 45.12 Comments:
136
Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 2 K/A # 2.2.22 Importance Rating 4.0 Equipment control: Knowledge of limiting conditions for operations and safety limits.
Proposed Question: RO 69 Unit I is in Mode I
- 1) Which ONE of the following parameters is considered an input to a Technical Specification SAFETY LIMIT and what system is in place to prevent exceeding the SAFETY LIMIT associated with this parameter?
- 2) Which ONE of the following states the Technical Specification ACTION if the SAFETY LIMIT is exceeded?
A. 1) High RCS pressure, PORVs.
- 2) Be in Hot Standby within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
B. 1) High T Jd, Main Steam Safety Valves.
0
- 2) Be in Hot Standby within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
C. 1) High RCS pressure, PORVs.
- 2) Reduce RCS pressure to within its limit within 5 minutes D. 1) High Tcold, Main Steam Safety Valves.
- 2) Reduce T Id to within its limit within 5 minutes 0
Proposed Answer: B Explanation (Optional):
A. Pressure is a Safety Limit, however Pressurizer Safeties are what limits pressure to prevent exceeding safety limit not PORVs.
B. Correct, MSSVs prevent TQld from exceeding 580°F. HSB within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is correct C. Part 2 would be correct if unit was in mode 3, 4 or 5 at time of high pressure.
D. Part 2 is HSB within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Technical Reference(s): T.S. 2.1 (Attach if not previously provided)
T.S. Figure 2.1-1 Proposed references to be provided to applicants during examination:
137
Learning Objective: PSL OPS ADM 703 LPC 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 43.2 45.2 Comments:
138
Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 2 KIA# 2.2.42 Importance Rating 3.9 Equipment Control: Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
Proposed Question: RO 70 Unit 1 is at 100% power. Which ONE of the following will result in entering a Technical Specification action statement?
A. Performing 1A Emergency Diesel Generator monthly surveillance with the Diesel synchronized to the bus.
B. Performing 1A Auxiliary Feedwater pump surveillance.
C. Removing the 1A OR the 1AA Battery Charger from service.
D. Isolating a PORV by closing its block valve.
Proposed Answer: A Explanation (Optional):
A. Correct B. Does not affect operability of the AFW pump.
C. Only one Battery Charger is required to be operable.
D. PORVs not required in Mode 1. Only position indication. Isolating the PORV in Mode 1 does not place the Unit in an action statement.
Technical Reference(s): 1-OSP-59.O1A 1A DG Monthly (Attach if not previously provided)
Surveillance.
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 139
Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 41.7 41.10 43.2 43.3 45.3 Comments:
140
Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 3 KIA# 2.3.11 Importance Rating 3.8 Radiation Control: Ability to control radiation releases.
Proposed Question: RO 71 Which one of the following MANUAL operator actions, if not performed prior to the receipt of a Recirculation Actuation Signal (RAS), could result in an unmonitored radioactive release to the environment?
A. Unit I I Removing power inhibit from SI recirc valves.
B. Unit 2 I Aligning ECCS sumps to the reactor cavity sump.
C. Unit 1 / Isolating Low Pressure Safety Injection pump manual recircs.
D. Unit 2 I Isolating Containment Spray pump manual recircs.
Proposed Answer: A Explanation (Optional):
A. Correct, recirc valves (flow path to the RWT) will remain open discharging sump water to an unmonitored, vented to atmosphere, tank.
B. Could cause a release, but would be monitored through the ECCS ventilation monitor.
C. LPSI pumps auto stop on RAS, not an issue A. Unit 2 main header recirc valves auto close, whereas Unit 1 CS manual recircs are normally closed Technical Reference(s): 1 -EOP-03, 0711207 (Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective: PSL OPS 0702207-19 (As available)
Question Source: Bank # 2008 NRC Exam Modified Bank # (Note changes or attach parent)
New 141
Question History: Last NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 41.11 43.4 45.10 Comments:
142
Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 3 KIA# 2.3.12 Importance Rating 3.2 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: RO 72 Unit 1 is at 100% power MOL. The IA Charging pump is running and the RCO is preparing to start the 1 B Charging pump.
Which ONE of the following states the proper coordination with Health Physics (HP) and the reason for this coordination?
Notify HP:
A. when the I B Charging pump has been started so they can monitor for increasing radiation levels in the Charging pump cubicle and the letdown area.
B. when the 1 B Charging pump has been started so they can monitor for potential leakage and contamination levels in the Charging pump cubicle.
C. of the pending start. Allow approximately 15 minutes to verify no personnel in the area of letdown piping, as this area could exceed 1000 mr/hr.
D. of the pending start. Allow approximately 15 minutes to verify no personnel in the Charging pump cubicle as this area could exceed 100 mr/hr.
Proposed Answer: C Explanation (Optional):
A. HP is given approximately 15 minutes notice PRIOR to start of the pump. Radiation levels will rise in the Charging pump cubicle when the Charging pump is started however this area is already posted radiation area.
B. Potential does exist for increasing leakage / contamination but HP does not survey the Charging pump rooms during starting of pumps.
C. Correct, N-16 from increasing letdown flow could result in significant increase in radiation levels in the area of the letdown piping.
D. HP does not survey Charging pump cubicles after pump start.
143
Technical Reference(s): 1-NOP-02.02, Charging and (Attach if not previously provided)
Letdown 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:
144
Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 3 K/A# 2.3.5 Importance Rating 2.9 Radiation Control: Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
Proposed Question: RO 73 While performing Standard Post Trip actions on Unit 2 you notice the following on the PC-i i:
- Main Steam Line Monitor indicates MAGENTA
- SJAE Monitor indicates YELLOW Which ONE of the following states the status of the above monitors?
A. Main Steam Line Monitor has experienced a communications failure.
SJAE Monitor is in the ALERT range for activity.
B. Main Steam Line Monitor has experienced an equipment failure.
SJAE Monitor is in the ALERT range for activity.
C. Main Steam Line Monitor has experienced an equipment failure.
SJAE Monitor is in the HIGH range for activity.
D. Main Steam Line Monitor has experienced a communication failure.
SJAE Monitor is in the HIGH range for activity.
Proposed Answer: A Explanation (Optional):
MAGENTA indicates communication failure YELLOW indicates channel in alert LIGHT BLUE indicates an equipment failure Technical Reference(s): Lesson Text 0711411 (Attach if not previously provided) 2-AOP-26.Oi, Process Radiation Monitors Proposed references to be provided to applicants during examination:
Learning Objective: (As available) 145
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: 41.11 41.12 43.4 45.9 Comments:
146
Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 4 K/A# 2.4.28 Importance Rating 3.2 Emergency Procedures / Plan: Knowledge of procedures relating to a security event (non-safeguards information).
Proposed Question: RO 74 Which ONE of the following Security events REQUIRE a manual trip of BOTH Units and entry into the Emergency Plan lAW O-AOP-72.O1, Response To Security Events A. Vehicle bomb detonation in Owner Controlled Area B. Breach of Protected Area by unauthorized personnel C. A Credible Insider Threat D. Armed intruders are within the Protected Area fence Proposed Answer: D Explanation (Optional):
A. Requires a rapid downpower not a unit trip B. Requires a rapid downpower not a unit trip C. Does not require a downpower or a reactor trip but does require all personnel to assemble at their work locations for accountability.
D. Correct Technical Reference(s): O-AOP-72.O1, Response To (Attach if not previously provided)
Security Events 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 147
Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 41.10 43.5 45.13 Comments:
148
Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 4 K/A# 2.4.34 Importance Rating 4.2 Emergency Procedures! Plan: Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects.
Proposed Question: RO 75 The Unit 1 control room has been evacuated due to a fire. All RCO, US and SNPO actions have been performed lAW 1-ONP-1 00.02, Control Room Inaccessibility Appendix A through D. A cooldown to SDC is to be initiated from the Hot Shutdown Panel.
Which ONE of the following states how Shutdown margin and RCS shrinkage makeup will be maintained during the cooldown?
Charging pump suction is:
A. initially aligned to the BAMT(s) for Shutdown margin control and shrinkage makeup.
When Shutdown margin is met, the Charging pump suction is realigned to the RWT.
B. initially aligned to the BAMT(s) for Shutdown margin control. When Shutdown margin is met the Charging pumps are realigned to the VCT with the SIT(s) aligned to the VCT for shrinkage makeup.
C. aligned to the RWT and this lineup is maintained for Shutdown margin control and shrinkage makeup.
D. aligned to the VCT. Shutdown margin and shrinkage makeup is accomplished by stationing an Operator at the local Boric Acid station, aligning Boric acid and Primary water valves as needed.
Proposed Answer: A Explanation (Optional):
A. Correct B. Plausible as this lineup is directed in 1-ONP-02.01, Boron Concentration Control Appendix B, to be used when other sources are not available.
C. RWT lineup is to be performed after SDM is met.
D. Plausible as this lineup is directed in 1-ONP-02.01, Boron Concentration Control Appendix A, if Boric Acid valve FCV-2161 malfunctions from the Control room.
149
Technical Reference(s): 1-ONP-1 00.02, Control Room (Attach if not previously provided)
Inaccessibility 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 43.5 45.13 Comments:
150