ML101110374

Initial Final RO Written Exam

ML101110374
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Site:	Vogtle
Issue date:	04/21/2010
From:	NRC/RGN-II
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{{#Wiki_filter:u.s. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name: Date: 03-05-2010 Facility/Unit: Vogtle 1 & 2 Region: I D II

• III D IV D Reactor Type: W. CE D BW D GE D Start Time:

Finish Time: Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours after the examination begins. ( Applicant Certification All work done on this examination is my own. I have neither given nor received aid. Applicant's Signature Results Examination Value 75 Points Applicant's Score Points Applicant's Grade Percent u.s. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name: Date: 03-05-2010 Facility/Unit: Vogtle 1 & 2 Region: I D II

• III D IV D Reactor Type: W. CE D BW D GE D Start Time:

Finish Time: Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours after the examination begins. ( Applicant Certification All work done on this examination is my own. I have neither given nor received aid. Applicant's Signature Results Examination Value 75 Points Applicant's Score Points Applicant's Grade Percent

Date: 03-05-2010 VEGP NRC RO-Examination Answer Sheet Student Name:

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Date: 03-05-2010 VEGP NRC RO Examination Answer Sheet Student Name:

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1.

HL-15R RO NRC EXAM-Which ONE of the following describes the power supplies to the Rod Drive Motor Generator (MG) sets and the breakers that are required to be locally tripped during an ATWT per 19211-C, FR-S.1, Response to Nuclear Power Generation/ATWT, if the Reactor Trip breakers will not open? MG Set Power Supplies Breakers to Trip A. 1NB09 and 1NB10 MG set motor breakers B. 1NB09 and 1NB10 MG set output breakers C. 1 NB08 and 1 NB09 MG set motor breakers D. 1 NB08 and 1 NB09 MG set output breakers 1

1.

( HL-15R RO NRC EXAM Which ONE of the following describes the power supplies to the Rod Drive Motor Generator (MG) sets and the breakers that are required to be locally tripped during an ATWT per 19211-C, FR-S.1, Response to Nuclear Power Generation/ATWT, if the Reactor Trip breakers will not open? MG Set Power Supplies Breakers to Trip A. 1 NB09 and 1 NB1 0 MG set motor breakers B. 1 NB09 and 1 NB1 0 MG set output breakers C. 1 NB08 and 1 NB09 MG set motor breakers D. 1 NB08 and 1 NB09 MG set output breakers 1

2.

HL~15R -RO NRC-EXAM Initial conditions: Unit 2 was operating at 100% power The reactor was manually tripped 2NAA and 2NAB de-energize on the reactor trip The crew implements 19001-C, "ES-0.1 Reactor Trip Recovery" Current conditions: 2NAB has been re-energized RCS Tave - 559 F and rising RCS WR Tcold - 558 F and rising AFW flow - 150 GPM per SG SG NR levels - 18% and slowly rising CST levels Both at 93% The UO and OA TC shall... A. maintain stable plant conditions in Hot Standby and raise AFW flow while attempting to start RCP 1. B. initiate a natural circulation cooldown and raise AFW flow while attempting to start RCP 4. C. maintain stable plant conditions in Hot Standby and raise the steaming rate with SG ARVs while attempting to start RCP 4. D. initiate a natural circulation cooldown and raise the steaming rate with SG ARVs while attempting to start RCP 1. 2

2.

( ( HL-15R-RO NRC EXAM Initial conditions: Unit 2 was operating at 100% power The reactor was manually tripped 2NAA and 2NAB de-energize on the reactor trip The crew implements 19001-C, "ES-0.1 Reactor Trip Recovery" Current conditions: 2NAB has been re-energized RCS Tave - 559 F and rising RCS WR Tcold - 558 F and rising AFW flow - 150 GPM per SG SG NR levels - 18% and slowly rising CST levels Both at 93% The UO and OATC shall... A. maintain stable plant conditions in Hot Standby and raise AFW flow while attempting to start RCP 1. B. initiate a natural circulation cooldown and raise AFW flow while attempting to start RCP 4. C. maintain stable plant conditions in Hot Standby and raise the steaming rate with SG ARVs while attempting to start RCP 4. D. initiate a natural circulation cooldown and raise the steaming rate with SG ARVs while attempting to start RCP 1. 2

3.

HL-15R RO NRC -EXAM Given the following conditions: - Dropped rod recovery is in progress while at power. - Control Bank C and Control Bank D are partially withdrawn. - 14915, "Special Condition Surveillance Logs", Data Sheet 5 for "Rod Insertion Limit Monitor Inoperable" is being performed by the OATC. Which ONE of the following choices lists banks and groups of a dropped rod that will render the RIL Monitor INOPERABLE during rod recovery? A. Control Bank C, Group 1 OR Control Bank D, Group 1 B. Control Bank C, Group 2 AND Control Bank D, Group 1 C. Control Bank C, Group 1 AND Control Bank D, Group 2 D. Control Bank C, Group 2 OR Control Bank D, Group 2 3

3.

HL-15R RO NRC-EXAM Given the following conditions: - Dropped rod recovery is in progress while at power. - Control Bank C and Control Bank D are partially withdrawn. - 14915, "Special Condition Surveillance Logs", Data Sheet 5 for "Rod Insertion Limit Monitor Inoperable" is being performed by the OATC. Which ONE of the following choices lists banks and groups of a dropped rod that will render the RIL Monitor INOPERABLE during rod recovery? A. Control Bank C, Group 1 OR Control Bank D, Group 1 B. Control Bank C, Group 2 AND Control Bank D, Group 1 C. Control Bank C, Group 1 AND Control Bank D, Group 2 D. Control Bank C, Group 2 OR Control Bank D, Group 2 3

4.

HL-1-SR-RO -NRC EXAM With an RCP shaft vibration of 20.2 mils, which ONE of the following correctly identifies where RCP vibrations are read and the required action to take? Location Action to take A. IPC computer points Immediately trip the affected RCP(s) B. IPC computer points Continue RCP operation and monitor vibrations C. Locally in Control Building Immediately trip the affected RCP(s) D. Locally in Control Building Continue RCP operation and monitor vibrations 4

4.

HL-15R RO NRC EXAM With an RCP shaft vibration of 20.2 mils, which ONE of the following correctly identifies where RCP vibrations are read and the required action to take? Location Action to take A. IPC computer points Immediately trip the affected RCP(s) B. IPC computer points Continue RCP operation and monitor vibrations C. Locally in Control Building Immediately trip the affected RCP(s) D. Locally in Control Building Continue RCP operation and monitor vibrations 4

5.

• -HL~15R-RONRC EXAM Given the following conditions:

- There is a 50 GPM RCS leak with the reactor at 100% power - PRZR level is slowly lowering - 120 GPM CVCS letdown is in service - The NCP is in service - Tave is stable at 586.4 F - RCP seal injection flow is 8 GPM per pump - Charging flow controller FIC-0121 is in automatic Which one of the following describes:

1) why charging flow will automatically increase, and

2) required operator actions, if any?

A. 1) PRZR level is lowering below the program level.

2) No operator action required, charging flow will automatically restore PRZR level to program level.

B. 1) PRZR level is lowering below the program level.

2) Letdown will be manually isolated and charging flow will be manually adjusted to restore PRZR level.

C. 1) PRZR program level changing.

2) No operator action required, charging flow will automatically restore PRZR level to program level.

D. 1) PRZR program level changing.

2) Letdown will be manually isolated and charging flow will be manually adjusted to restore PRZR level.

5

5.

HL~15R~ RO NRC EXAM Given the following conditions: - There is a 50 GPM RCS leak with the reactor at 100% power - PRZR level is slowly lowering - 120 GPM CVCS letdown is in service - The NCP is in service - Tave is stable at 586.4 F - RCP seal injection flow is 8 GPM per pump - Charging flow controller FIC-0121 is in automatic Which one of the following describes:

1) why charging flow will automatically increase, and

2) required operator actions, if any?

A. 1) PRZR level is lowering below the program level.

2) No operator action required, charging flow will automatically restore PRZR level to program level.

B. 1) PRZR level is lowering below the program level.

2) Letdown will be manually isolated and charging flow will be manually adjusted to restore PRZR level.

C. 1) PRZR program level changing.

2) No operator action required, charging flow will automatically restore PRZR level to program level.

D. 1) PRZR program level changing.

2) Letdown will be manually isolated and charging flow will be manually adjusted to restore PRZR level.

5

HL-15R RO NRC EXAM

6.

( A malfunction has resulted in seal injection flows being out of limits. Which one of the following choices lists the correct action to take for the given RCP seal injection flow? Rep Seal Injection Flow Action to take A. 7.8 gpm Depress UP arrow to throttle HV-0182 OPEN B. 13.4 gpm Depress UP arrow to throttle HV-0182 CLOSED C. 13.4 gpm Depress DOWN arrow to throttle HV-0182 OPEN D. 7.8 gpm Depress DOWN arrow to throttle HV-0182 CLOSED 6 HL-15R RO NRC EXAM

6.

I A malfunction has resulted in seal injection flows being out of limits. ( Which one of the following choices lists the correct action to take for the given RCP seal injection flow? Rep Seal Injection Flow Action to take A. 7.8 gpm Depress UP arrow to throttle HV-0182 OPEN B. 13.4 gpm Depress UP arrow to throttle HV-0182 CLOSED C. 13.4 gpm Depress DOWN arrow to throttle HV-0182 OPEN D. 7.8 gpm Depress DOWN arrow to throttle HV-0182 CLOSED 6

7.

( HL-15R RONRC EXAM Which ONE of the following describes the power supplies to the RHR loop suction isolation valves? A. The outboard loop suctions are powered from a 1 E 480V MCC. The inboard loop suctions are powered from an opposite train 1 E 480V MCC. . B. The inboard loop suctions are powered from a 1 E 480V MCC. The outboard loops suctions are powered from an opposite train 1 E 480V MCC. C. Both loop suctions on one train are powered from 1 E 480V MCCs. Both loop suctions on the other train are powered from 1 E 25KVA Inverters. D. One loop suction on each train is powered from 1 E 480V MCCs. One loop suction on each train is powered from 1 E 25KVA Inverters. 7

7.

( HL-15R RO NRC EXAM Which ONE of the following describes the power supplies to the RHR loop suction isolation valves? A. The outboard loop suctions are powered from a 1 E 480V MCC. The inboard loop suctions are powered from an opposite train 1 E 480V MCC. B. The inboard loop suctions are powered from a 1 E 480V MCC. The outboard loops suctions are powered from an opposite train 1 E 480V MCC. C. Both loop suctions on one train are powered from 1 E 480V MCCs. Both loop suctions on the other train are powered from 1 E 25KVA Inverters. D. One loop suction on each train is powered from 1 E 480V MCCs. One loop suction on each train is powered from 1 E 25KVA Inverters. 7

8.

( --HL~15R RO-NRCEXAM While in Mode 5 with RHR Train B in service, which ONE of the following is the effect during a loss of instrument air? RHR Hx Outlet, 1 HV-607 RHR Hx Bypass, 1HV-619 A. Fails OPEN Fails OPEN B. Fails SHUT Fails SHUT

c.

Fails OPEN Fails SHUT D. Fails SHUT Fails OPEN 8

8.

( . HL-15R RO NRC EXAM While in Mode 5 with RHR Train B in service, which ONE of the following is the effect during a loss of instrument air? RHR Hx Outlet, 1 HV-607 RHR Hx Bypass, 1 HV-619 A. Fails OPEN Fails OPEN B. Fails SHUT Fails SHUT

c.

Fails OPEN Fails SHUT D. Fails SHUT Fails OPEN 8

9.

HL-15R RO NRC EXAM Given the following: - The ECCS Accumulator isolation valves were inadvertently left CLOSED and in AUTO with power on the valves. - PRZR pressure has been raised from 930 psig to 2100 psig. - A spurious Safety Injection (SI) occurs. Which ONE of the following identifies the effect on the ECCS Accumulator isolation valves:

1. at 2100 psig prior to the SI signal, and

2. after the spurious SI signal At 2100 psig After Spurious 51 signal A. valves are closed.

Open signal is generated to the valves. B. valves are closed. Open signal is NOT generated to the valves. C. valves automatically open. Open signal is generated to the valves. D. valves automatically open. Open signal is NOT generated to the valves. 9

9.

( HL-15R RO NRC EXAM Given the following: - The ECCS Accumulator isolation valves were inadvertently left CLOSED and in AUTO with power on the valves. - PRZR pressure has been raised from 930 psig to 2100 psig. - A spurious Safety Injection (SI) occurs. Which ONE of the following identifies the effect on the ECCS Accumulator isolation valves:

1. at 2100 psig prior to the SI signal, and

2. after the spurious SI Signal At 2100 psig After Spurious SI signal A. valves are closed.

Open signal is generated to the valves. B. valves are closed. Open signal is NOT generated to the valves. C. valves automatically open. Open signal is generated to the valves. D. valves automatically open. Open signal is NOT generated to the valves. 9

--HL--15R RO NRC EXAM

10.

A loss of offsite power resulted in an automatic plant trip. - Red lights are LIT on all RCP 1 E handswitches. - Red I'ights are LIT on all RCP non-1 E handswitches. -19001-C, "ES-0.1 Reactor Trip Response" is in effect. Which ONE of the following is the:

1) event which caused the reactor trip and

2) indication the operators will use to monitor RCS temperature?

Cause of Reactor Trip Temperature monitoring A. RCP underfrequency RCS Tave B. RCP underfrequency RCS WR Tcold C. RCS loops low flow RCS Tave D. RCS loops low flow RCS WR Tcold 10 HL-15R RO NRC EXAM

10.

A loss of offsite power resulted in an automatic plant trip. - Red lights are LIT on all RCP 1 E handswitches. - Red l'ights are LIT on all RCP non-1 E handswitches. -19001-C, "ES-0.1 Reactor Trip Response" is in effect. Which ONE of the following is the: 1 ) event which caused the reactor trip and

2) indication the operators will use to monitor RCS temperature?

Cause of Reactor Trip Temperature monitoring A. RCP underfrequency RCS Tave B. RCP underfrequency RCS WR Tcold C. RCS loops low flow RCS Tave D. RCS loops low flow RCS WR Tcold f " ( 10

HL-15R RO NRC EXAM

11.

Given the following while at 100% power. - Plant systems are in normal alignment. - A reactor trip occurs. - RCS pressure is 1830 psig and lowering. - Containment pressure is 2.3 psig and rising. RCP seal leakoff flows from the # 1 seals are currently directed to the... (Assume NO manual actions) A. PRT B. RCDT C. CTMT sump D. Seal Water Hx Outlet to the NCP ( 11 HL-15R RO NRC EXAM

11.

Given the following while at 100% power. - Plant systems are in normal alignment. - A reactor trip occurs. - RCS pressure is 1830 psig and lowering. - Containment pressure is 2.3 psig and rising. RCP seal leakoff flows from the # 1 seals are currently directed to the... (Assume NO manual actions) A. PRT B. RCDT C. CTMT sump D. Seal Water Hx Outlet to the NCP 11

12.

( HL-15R RO. NRC EXAM. Given the following: The unit is at 100% power PRT high temperature exists due to leakage from a PRZR PORV All systems are in their normal alignment PRT cooling _--->-(1.:....<) __ aligned to be directly cooled by _..... (=2.L-) __ A. (1) is normally (2) ACCW B. (1) is normally (2) NSCW C. (1) must be manually (2) ACCW D. (1) must be manually (2) NSCW 12

12.

( HL-15R RO NRC EXAM Given the following: The unit is at 100% power PRT high temperature exists due to leakage from a PRZR PORV All systems are in their normal alignment PRT cooling ( 1) aligned to be directly cooled by (2) A. (1) is normally (2) ACCW B. (1) is normally (2) NSCW C. (1) must be manually (2) ACCW D. (1) must be manually (2) NSCW 12

13.

( HL-15R RO NRC EXAM Given the following sequence of events: At 1400, PRZR Safety valve failed open. At 1402, Tave is 557°F, PRZR pressure is 1940 psig. At 1405, Tave is 556°F, PRZR pressure is 1840 psig. Which ONE of the following lists the first initiating signals for the FWI valves closure and the MFPTs trip? FWI Valves Closure MFPTs Trip A. Low PRZR pressure SI Low PRZR pressure SI B. Reactor trip coincident with low Tave Low PRZR pressure SI C. Low PRZR pressure SI Reactor trip coincident with low T ave D. Reactor trip coincident with low Tave Reactor trip coincident with low Tave 13

13.

( ( HL-15R RO NRC EXAM Given the following sequence of events: At 1400, PRZR Safety valve failed open. At 1402, Tave is 557°F, PRZR pressure is 1940 psig. At 1405, Tave is 556°F, PRZR pressure is 1840 psig. Which ONE of the following lists the first initiating signals for the FWI valves closure and the MFPTs trip? FWI Valves Closure MFPTs Trip A. Low PRZR pressure SI Low PRZR pressure SI B. Reactor trip coincident with low Tave Low PRZR pressure SI

c. Low PRZR pressure SI Reactor trip coincident with low Tave D. Reactor trip coincident with low Tave Reactor trip coincident with low Tave 13

14.

~HL-15R-RO NRC EXAM Which one of the following choices lists all the procedurally allowable power supplies for Unit 1 CCW pumps 1,3, and 5 per 13427A-1, "4160V AC Bus 1AA02 1 E Electrical Distribution System?" A. RAT-1A, RAT-1B, SAT, EDG-1A B. RAT-1A, UAT back feed, SAT, EDG-2A C. RAT-1A, RAT-2A, SAT, EDG-1A D. RAT-1A, UAT back feed, SAT, EDG-2A 14

14.

( HL-15R RO NRC EXAM Which one of the following choices lists all the procedurally allowable power supplies for Unit 1 CCW pumps 1, 3, and 5 per 13427 A-1, "4160V AC Bus 1 AA02 1 E Electrical Distribution System?" A. RAT-1A, RAT-1B, SAT, EDG-1A B. RAT-1A, UAT back feed, SAT, EOG-2A C. RAT-1A, RAT-2A, SAT, EDG-1A D. RAT-1A, UAT back feed, SAT, EOG-2A 14

15.

HL-15R RO'-NRCEXAM Given the following: - A 200 gpm RCS leak is in progress. - RCS pressure is 1465 psig and stable. - Containment pressure is 2.1 psig and rising very slowly. - The crew transitions to 19012-C, "E-1.2 Post LOCA Cooldown & Depressurization". Which ONE of the following is CORRECT regarding minimum S/G NR water level required for these plant conditions and why? A. 10%, ensures S/G tubes are covered to promote reflux boiling. B. 32%, ensures S/G tubes are covered to promote reflux boiling. C. 10%, ensures S/G inventory to ensure a secondary heat sink. D. 32%, ensures S/G inventory to ensure a secondary heat sink. 15

15.

( HL-15R RONRC EXAM Given the following: - A 200 gpm RCS leak is in progress. - RCS pressure is 1465 psig and stable. - Containment pressure is 2.1 psig and rising very slowly. - The crew transitions to 19012-C, "E-1.2 Post LOCA Cooldown & Depressurization". Which ONE of the following is CORRECT regarding minimum S/G NR water level required for these plant conditions and why? A. 10%, ensures S/G tubes are covered to promote reflux boiling. B. 32%, ensures S/G tubes are covered to promote reflux boiling. C. 10%, ensures S/G inventory to ensure a secondary heat sink. D. 32%, ensures S/G inventory to ensure a secondary heat sink. 15

16.

HL-15RRO NRC EXAM Complete the following statement for the PRZR Pressure Control System: When PRZR level I owe rs __, then __ will de-energize, if energized. A. below 17% B. 5% below program level C. below 17% D. 5% below program level 16 ONLY the backup heaters backup and proportional heaters backup and proportional heaters ONLY the backup heaters

16.

( HL-15R RO NRC EXAM Complete the following statement for the PRZR Pressure Control System: When PRZR level lowers , then will de-energize, if energized. A. below 17% B. 5% below program level C. below 17% D. 5% below program level 16 ONLY the backup heaters backup and proportional heaters backup and proportional heaters ONLY the backup heaters

17.

HL-1SR.RONRC EXAM. To maintain Containment parameters within the accident analysis assumptions for a DBA LOCA, the Containment Pressure and Containment Air Temperature LCO limits for Mode 1 are... A. +1.8 psig and 1200 F B. +1.8 psig and 1300 F C. -3.0 psig and 1200 F D. -3.0 psig and 1300 F 17

17.

( ( HL-1SR,RO NRC EXAM To maintain Containment parameters within the accident analysis assumptions for a DBA LOCA, the Containment Pressure and Containment Air Temperature LCO limits for Mode 1 are... A. +1.8 psig and 1200 F B. +1.8 psig and 1300 F C. -3.0 psig and 1200 F D. -3.0 psig and 1300 F 17

18.

HL*15R RO NR*C EXAM* Five minutes following a reactor trip and safety injection, the OATCplaces Train A SI reset handswitch in the "reset" position. P-4 Train A will be generated when the Train A reactor trip breaker is open ~ SI reset will blockfl.L. A. (1) and the Train B bypass breaker is open (2) only the Train A PRZR Low Pressure SI and Low Steamline Pressure SI signals B. (1) and the Train A bypass breaker is open (2) all Train A automatic SI signals C. (1) or the Train A bypass breaker is open (2) only the Train A PRZR Low Pressure SI and Low Steamline Pressure SI signals D. (1) or the Train B bypass breaker is open (2) all Train A automatic SI signals 18

18.

( ( HL*15R RO NRC EXAM Five minutes following a reactor trip and safety injection, the OATC places Train A SI reset handswitch in the "reset" position. P-4 Train A will be generated when the Train A reactor trip breaker is open ~ SI reset will blockflL. A. (1) and the Train B bypass breaker is open (2) only the Train A PRZR Low Pressure SI and Low Steamline Pressure SI signals B. (1) and the Train A bypass breaker is open (2) all Train A automatic SI signals C. (1) or the Train A bypass breaker is open (2) only the Train A PRZR Low Pressure SI and Low Steamline Pressure SI signals D. (1) or the Train B bypass breaker is open (2) all Train A automatic SI signals 18

19.

HL~15RRO NRC EXAM Which one ofthe following matches the reactor trip signals to their limiting accident I protection? Reactor Trip Signal Limiting Accident I Protection A. Overpower DT DNB Overtemperature DT Excessive fuel heat generation rate (kW 1ft) PRZR High Pressure RCS integrity PRZR Low Pressure DNB B. Overpower DT Excessive fuel heat generation rate (kW 1ft) Overtemperature DT DNB PRZR High Pressure RCCA drive housing rupture PRZR Low Pressure Excessive RCS cooldown C. Overpower DT Excessive fuel heat generation rate (kW 1ft) Overtemperature DT DNB PRZR High Pressure RCS integrity PRZR Low Pressure DNB D. Overpower DT DNB Overtemperature DT Excessive fuel heat generation rate (kW 1ft) PRZR High Pressure RCCA drive housing rupture PRZR Low Pressure Excessive RCS cooldown 19

19.

( ( HL-15R RO NRC EXAM Which one of the following matches the reactor trip signals to their limiting accident I protection? Reactor Trip Signal Limiting Accident I Protection A. Overpower DT DNB Overtemperature DT Excessive fuel heat generation rate (kW 1ft) PRZR High Pressure RCS integrity PRZR Low Pressure DNB B. Overpower DT Excessive fuel heat generation rate (kW 1ft) Overtemperature DT DNB PRZR High Pressure RCCA drive housing rupture PRZR Low Pressure Excessive RCS cooldown C. Overpower DT Excessive fuel heat generation rate (kW 1ft) Overtemperature DT DNB PRZR High Pressure RCS integrity PRZR Low Pressure DNB D. Overpower DT DNB Overtemperature DT Excessive fuel heat generation rate (kW 1ft) PRZR High Pressure RCCA drive housing rupture PRZR Low Pressure Excessive RCS cooldown 19

20.

c HL~~5R RO NRC EXAM A loss of 120V AC vital bus 1 BY1 B has occurred with the unit at 100% power. Which one of the following correctly decribes the impact on SSPS? A. Only SSPS Train B channel" Input relays are de-energized. The Train B Slave relays are inoperable. B. Only SSPS Train B channel" input relays are de-energized. The Train B Slave relays are operable. C. SSPS Train A and Train B channel" Input relays are de-energized. The Train B Slave relays are operable. D. SSPS Train A and Train B channel" Input relays are de-energized. The Train B Slave relays are inoperable. 20

20.

( ( HL~~ 5R RO NRC EXAM A loss of 120V AC vital bus 1 BY1 B has occurred with the unit at 100% power. Which one of the following correctly decribes the impact on SSPS? A. Only SSPS Train B channel II Input relays are de-energized. The Train B Slave relays are inoperable. B. Only SSPS Train B channel II input relays are de-energized. The Train B Slave relays are operable. C. SSPS Train A and Train B channel II Input relays are de-energized. The Train B Slave relays are operable. D. SSPS Train A and Train B channel II Input relays are de-energized. The Train B Slave relays are inoperable. 20

21.

HL~15R RO NRC EXAM Given the following: - The plant is at 17% power. The following conditions exist on Reactor Coolant Pump # 2. - # 1 seal DIP is 190 psig. - # 1 seak leakoff flow is 5.2 gpm. Which ONE of the following describes the required sequence I response to these conditions? A. Shutdown the RCP, enter AOP-18005-C, "Partial Loss of Flow". B. Commence a unit shutdown per UOP-12004-C, shutdown the RCP within 8 hours. C. Trip the Reactor, enter 19000-C, "Reactor Trip or Safety Injection", shutdown the RCP. D. Maintain current power, shutdown the RCP with engineering I management concurrence. 21

21.

( ( HL-15R RO NRC EXAM Given the following: - The plant is at 17% power. The following conditions exist on Reactor Coolant Pump # 2. - # 1 seal DIP is 190 psig. - # 1 seak leakoff flow is 5.2 gpm. Which ONE of the following describes the required sequence I response to these conditions? A. Shutdown the RCP, enter AOP-18005-C, "Partial Loss of Flow". B. Commence a unit shutdown per UOP-12004-C, shutdown the RCP within 8 hours. C. Trip the Reactor, enter 19000-C, "Reactor Trip or Safety Injection", shutdown the RCP. D. Maintain current power, shutdown the RCP with engineering I management concurrence. 21

22.

HL~15RRO-NRC EXAM Given the following conditions: - The unit is at 100% power. - PRZR pressure control is selected to the 457 / 456 position. The DATC determines that the controlling channel for Pressurizer Pressure control has failed. Which one of the following describes the instrument failure and the plant response if no operator actions were taken? A. PT-457 fails high, PRZR pressure cycles between 2185 psig and 2200 psig. B. PT -456 fails low, PRZR pressure cycles between 2345 psig and 2325 psig. C. PT-456 fails low, reactor trips on the high PRZR Pressure setpoint. D. PT-457 fails high, reactor trips on the low PRZR Pressure setpoint. 22

22.

( HL-15R RO NRC EXAM Given the following conditions: - The unit is at 100% power. - PRZR pressure control is selected to the 457 / 456 position. The OATC determines that the controlling channel for Pressurizer Pressure control has failed. Which one of the following describes the instrument failure and the plant response if no operator actions were taken? A. PT-457 fails high, PRZR pressure cycles between 2185 psig and 2200 psig. B. PT-456 fails low, PRZR pressure cycles between 2345 psig and 2325 psig. C. PT -456 fails low, reactor trips on the high PRZR Pressure setpoint. D. PT-457 fails high, reactor trips on the low PRZR Pressure setpoint. 22

23.

-HL-15R RO NRC EXAM The unit is shutdown with RCS temperature 3750 F. CNMT HI TEMP alarm has just annunciated. The UO notes that CNMT air temperature is rising with CNMT coolers 1,2,5, and 6 in service on high speed. Which one of the following decribes the actions the UO can take to stop the CNMT air temperature rise? A. Start CNMT coolers 3 and 4 simultaneously on high speed. B. Start CNMT coolers 3 and 7 simultaneously on high speed. C. Start CNMT coolers 3 and 4 sequentially on high speed. D. Start CNMT coolers 3 and 7 sequentially on high speed. 23

23.

( ( HL-15R RO NRC EXAM The unit is shutdown with RCS temperature 3750 F. CNMT HI TEMP alarm has just annunciated. The UO notes that CNMT air temperature is rising with CNMT coolers 1, 2, 5, and 6 in service on high speed. Which one of the following decribes the actions the UO can take to stop the CNMT air temperature rise? A. Start CNMT coolers 3 and 4 simultaneously on high speed. B. Start CNMT coolers 3 and 7 simultaneously on high speed. C. Start CNMT coolers 3 and 4 sequentially on high speed. D. Start CNMT coolers 3 and 7 sequentially on high speed. 23

24.

( HL~15RRONRC EXAM Initial conditions: A steam line break inside containment has occurred EOP 1901 O-C, "E-1 Loss of Reactor or Secondary Coolant" is being implemented The following sequence of events occurs: - The SI signal is RESET - CNMT pressure is 8.6 psig and lowering - A loss of both RATs occurs - Both EDGs start and re-energize their respective buses Operators will:

1) verify the sequencers start all CNMT coolers on ____ speed, and

2) the next action necessary will be to __ _

A. 1) low

2) shift the CNMT coolers to high speed to maximize CNMT energy removal.

B. 1)low

2) restart the SI and RHR pumps as necessary to maintain RCS inventory.

C. 1) high

2) shift the CNMT coolers to low speed to prevent a CNMT cooler fan motor overcurrent condition.

D. 1) high

2) shift the CNMT coolers to low speed to prevent an EDG output breaker overcurrent condition.

24

24.

( ( HL~15R RONRC EXAM Initial conditions: A steamline break inside containment has occurred EOP 1901 O-C, "E-1 Loss of Reactor or Secondary Coolant" is being implemented The following sequence of events occurs: - The SI signal is RESET - CNMT pressure is 8.6 psig and lowering - A loss of both RATs occurs - Both EDGs start and re-energize their respective buses Operators will:

1) verify the sequencers start all CNMT coolers on ____ speed, and

2) the next action necessary will be to __ _

A. 1) low

2) shift the CNMT coolers to high speed to maximize CNMT energy removal.

B. 1) low

2) restart the SI and RHR pumps as necessary to maintain RCS inventory.

C. 1) high

2) shift the CNMT coolers to low speed to prevent a CNMT cooler fan motor overcurrent condition.

D. 1) high

2) shift the CNMT coolers to low speed to prevent an EDG output breaker overcurrent condition.

24

25.

... HL-15R-RO NRC EXAM Given the following conditions: - A loss of all AC power occurs in Mode 1. - The plant is currently in Mode 3. - HV-8103A, B, C, D Seal Injection Isolation Valves are CLOSED. Which ONE of the following describes:

1) the Mode in which seal injection will be re-established, and

2) the reason for closing the seal injection isolation valves?

A. 1) Mode 3.

2) To prevent steam binding the charging pumps via back leakage in the seal lines.

B. 1) Mode 3.

2) To prevent seal damage and RCP shaft bowing due to excessive thermal stresses.

C. 1) Mode 5.

2) To prevent steam binding the charging pumps via back leakage in the seal lines.

D. 1) Mode 5.

2) To prevent seal damage and RCP shaft bowing due to excessive thermal stresses.

25

25.

( ( HL-15R-RO NRC EXAM Given the following conditions: - A loss of all AC power occurs in Mode 1. - The plant is currently in Mode 3. - HV-81 03A, B, C, D Seal Injection Isolation Valves are CLOSED. Which ONE of the following describes:

1) the Mode in which seal injection will be re-established, and

2) the reason for closing the seal injection isolation valves?

A. 1) Mode 3.

2) To prevent steam binding the charging pumps via back leakage in the seal lines.

B. 1) Mode 3.

2) To prevent seal damage and RCP shaft bowing due to excessive thermal stresses.

C. 1) Mode 5.

2) To prevent steam binding the charging pumps via back leakage in the seal lines.

D. 1) Mode 5.

2) To prevent seal damage and RCP shaft bowing due to excessive thermal stresses.

25

26.

C" -HL~15R-RO NRC EXAM Given the following sequence: - The plant is in Mode 6 at midloop. - RHR pump "A" trips due to a loss of RCS inventory. - The RCS has been refilled and RHR pump "B" is ready to be started. Complete the following two sentences:

1) To start the pump, the RHR Hx Bypass Valve controller (FIC-0619) should be __

2) To ensure compliance with Tech Spec flow requirements, per procedure the potentiometer setting for the RHR Hx Bypass Valve controller (FIC-0619) should be setat. __

Given: Formula for Potentiometer setting in gpm is (desired flow /5000)2 X 10.

1) RHR Hx Bypass valve

2) Potentiometer setting A. in automatic.

3.6 B. in automatic. 4.1 C. in manual and closed. 3.6 D. in manual and closed. 4.1 26

26.

( ( HL-15RRO NRC EXAM Given the following sequence: - The plant is in Mode 6 at midloop. - RHR pump "A" trips due to a loss of RCS inventory. - The RCS has been refilled and RHR pump "B" is ready to be started. Complete the following two sentences:

1) To start the pump, the RHR Hx Bypass Valve controller (FIC-0619) should be __

2) To ensure compliance with Tech Spec flow requirements, per procedure the potentiometer setting for the RHR Hx Bypass Valve controller (FIC-0619) should be set at --

Given: Formula for Potentiometer setting in gpm is (desired flow /5000)2 X 10.

1) RHR Hx Bypass valve

2) Potentiometer setting A. in automatic.

3.6 B. in automatic. 4.1 C. in manual and closed. 3.6 D. in manual and closed. 4.1 26

27.

HL-15R RO NRC EXAM Which one of the following lists ALL the locations where the control room crew can monitor and control:

1) Containment Cooler fan speeds, and

2) NSCW cooling water valves?

MLBs - Monitor Light Boxes on the vertical section of the main control board QMCB - Sloping portion of the NSCW section of the main control board QHVC - Main Control Room HVAC panel Indications Controls A. 1) MLBs, QHVC QHVC

2)

QMCB only QMCB B. 1) MLBs, QMCB QMCB

2)

MLBs only QMCB C. 1) QHVC only QHVC

2)

QMCB only QMCB D. 1) MLBs, QHVC QHVC

2)

MLBs, QMCB QMCB 27

27.

( ( HL-15R RO NRC EXAM Which one of the following lists ALL the locations where the control room crew can monitor and control:

1) Containment Cooler fan speeds, and

2) NSCW cooling water valves?

MLBs - Monitor Light Boxes on the vertical section of the main control board OMCB - Sloping portion of the NSCW section of the main control board OHVC - Main Control Room HVAC panel Indications Controls A. 1) MLBs,OHVC OHVC

2)

OMCB only OMCB B. 1) MLBs,OMCB OMCB

2)

MLBs only OMCB C. 1) OHVC only OHVC

2)

OMCB only OMCB D. 1 ) MLBs,OHVC OHVC

2)

MLBs,OMCB OMCB 27

-- HL-15R.-RO *NRC EXAM 28. . Given the following: - A loss of offsite power occurs. - Both EDGs start and tie onto their respective ESF buses. - All equipment sequences on as expected. Which ONE of the following describes the PRZR heater banks available for RCS pressure control? A. All Backup Heater Banks. B. Backup Heater Banks A and B. C. Proportional Heater Bank and All Backup Heater Banks. D. Proportional Heater Bank and Backup Heater Banks A and B. 28

28.

( ( HL-15RRO NRC EXAM Given the following: - A loss of offsite power occurs. - Both EDGs start and tie onto their respective ESF buses. - All equipment sequences on as expected. Which ONE of the following describes the PRZR heater banks available for RCS pressure control? A. All Backup Heater Banks. B. Backup Heater Banks A and B. C. Proportional Heater Bank and All Backup Heater Banks. D. Proportional Heater Bank and Backup Heater Banks A and B. 28

29.

HL~15R~ RO NRC EXAM Given the current plant conditions: - A large RCS LOCA has occurred - CNMT Hydrogen monitors indicate 5% - Containment pressure is 5.5 psig - TSC directs lowering of eN MT H2 concentration using 13130-1, "Post-Accident Hydrogen Control" Which one of the following describes the operational implication of the Hydrogen concentration (%) and the PREFERRED method to reduce Hydrogen concentration inside containment? Operational Implication PREFERRED Method to reduce Hydrogen A. Potential Combustible atmosphere Dilution with Service Air B. Potential Combustible atmosphere Post-LOCA Hydrogen Purge C. Embrittlement of CNMT liner Dilution with Service Air D. Embrittlement of CNMT liner Post-LOCA Hydrogen Purge 29

29.

( HL~15R RO NRC EXAM Given the current plant conditions: - A large RCS LOCA has occurred - CNMT Hydrogen monitors indicate 5% - Containment pressure is 5.5 psig - TSC directs lowering of CNMT H2 concentration using 13130-1, "Post-Accident Hydrogen Control" Which one of the following describes the operational implication of the Hydrogen concentration (%) and the PREFERRED method to reduce Hydrogen concentration inside containment? Operational Implication PREFERRED Method to reduce Hydrogen A. Potential Combustible atmosphere Dilution with Service Air B. Potential Combustible atmosphere Post-LOCA Hydrogen Purge C. Embrittlement of CNMT liner Dilution with Service Air D. Embrittlement of CNMT liner Post-LOCA Hydrogen Purge 29

30.

HL~15R RONRC EXAM The plant is in Mode 3. - SR / IR Signal Processor Channel Operational Tests have been performed. - Background counts for both SR channels are 1000 cps. - The UO records the counts when the HFASA alarm lights for each SR channel. N31 - 2080 cps N32 - 2340 cps Which ONE of the following is CORRECT regarding Technical Specification LCO 3.3.8, High Flux At Shutdown Alarm (HFASA)? A. The LCO is met for both SR NIS HFASA alarms. B. LCO entry required due to N31 setpoint too low. C. LCO entry required due to N32 setpoint too high. D. LCO entry required for both SR NIS HFASA alarms. 30

30.

( HL~15R RO NRC EXAM The plant is in Mode 3. - SR / IR Signal Processor Channel Operational Tests have been performed. - Background counts for both SR channels are 1000 cps. - The UO records the counts when the HFASA alarm lights for each SR channel. N31 - 2080 cps N32 - 2340 cps Which ONE of the following is CORRECT regarding Technical Specification LCO 3.3.8, High Flux At Shutdown Alarm (HFASA)? A. The LCO is met for both SR NIS HFASA alarms. B. LCO entry required due to N31 setpoint too low. C. LCO entry required due to N32 setpoint too high. D. LCO entry required for both SR NIS HFASA alarms. 30

31.

( HL~15R RO NRC EXAM Which ONE of the following is CORRECT regarding:

1) The minimum Spent Fuel Pool level (elevation) required by Tech Specs for adequate shielding and design basis fuel handling events.

2) how the FHB crew would be alerted to High radiation on RE-0008, Fuel Handling Building Area radiation monitor.

1) Tech Spec level

2) RE-0008 high rad alarm A. 214 ft. 6 inch audible horn and blinking strobe light B. 214 ft. 6 inch warble type siren on plant gai-tronics C. 217 ft. 0 inch audible horn and blinking strobe light D. 217 ft. 0 inch warble type siren on plant gai-tronics 31

31.

( ( HL~15R RO NRC EXAM Which ONE of the following is CORRECT regarding:

1) The minimum Spent Fuel Pool level (elevation) required by Tech Specs for adequate shielding and design basis fuel handling events.

2) how the FHB crew would be alerted to High radiation on RE-0008, Fuel Handling Building Area radiation monitor.

1) Tech Spec level

2) RE-0008 high rad alarm A. 214 ft. 6 inch audible horn and blinking strobe light B. 214 ft. 6 inch warble type siren on plant gai-tronics C. 217 ft. 0 inch audible horn and blinking strobe light D. 217 ft. 0 inch warble type siren on plant gai-tronics 31

32.

( HL~15RRO NRC EXAM The plant is at full power. SG # 2 ARV, "PV-3010," has been declared INOPERABLE due to large hydraulic fluid leaks on the valve operator. Which ONE of the following describes:

1) LCO entry (not INFO) and

2) All the applicable modes the ARVs are required to be OPERABLE?

LCO entry Applicable Modes A. Is required Modes 1,2, and 3 B. Is required Modes 1 and 2 only C. Is NOT required Modes 1,2, and 3 D. Is NOT required Modes 1 and 2 only 32

32.

( HL.. 15R RO NRC EXAM The plant is at full power. SG # 2 ARV, "PV-3010," has been declared INOPERABLE due to large hydraulic fluid leaks on the valve operator. Which ONE of the following describes:

1) LCO entry (not INFO) and

2) All the applicable modes the ARVs are required to be OPERABLE?

LCO entry Applicable Modes A. Is required Modes 1,2, and 3 B. Is required Modes 1 and 2 only C. Is NOT required Modes 1,2, and 3 D. Is NOT required Modes 1 and 2 only 32

HL.. 15R'RO NRC EXAM

33.

( A SGTR coincident with an RCS LOCA is in progress. ( - All RCPs have been tripped. - RVLlS Full Range indicates 65%. - All SG levels are> 50% NR. - Intact SG pressures - 1000 psig. - Core Exit Thermocouples - 5600 F and stable. - RCS pressure - 1118 psig and stable.~ - WR Tcolds - 4650 F. Which one of the following identifies:

1) the current method of core cooling, and

2) the flow path for this cooling method?

A. 1) Reflux Cooling

2) steam flows to the S/G via the top of the hot legs, transfers heat to the secondary side water, condenses in the S/G tubes and returns to the vessel via the bottom of the hot legs.

B. 1) Reflux Cooling

2) steam flows to the S/G via the top of the hot legs, transfers heat to the secondary side water, condenses in the S/G tubes and returns to the vessel via the cold legs into the downcomer.

C. 1) Natural Circulation

2) steam flows to the S/G via the top of the hot legs, transfers heat to the secondary side water, condenses in the S/G tubes and returns to the vessel via the bottom of the hot legs.

D. 1) Natural Circulation

2) steam flows to the S/G via the top of the hot legs, transfers heat to the secondary side water, condenses in the S/G tubes and returns to the vessel via the cold legs into the downcomer.

33

33.

( ( HL.. 15RRO NRC EXAM A SGTR coincident with an RCS LOCA is in progress. - All RCPs have been tripped. - RVLlS Full Range indicates 65%. - All SG levels are> 50% NR. - Intact SG pressures - 1000 psig. - Core Exit Thermocouples - 5600 F and stable. - RCS pressure - 1118 psig and stable.~ - WR Tcolds - 4650 F. Which one of the following identifies:

1) the current method of core cooling, and

2) the flow path for this cooling method?

A. 1) Reflux Cooling

2) steam flows to the S/G via the top of the hot legs, transfers heat to the secondary side water, condenses in the S/G tubes and returns to the vessel via the bottom of the hot legs.

B. 1) Reflux Cooling

2) steam flows to the S/G via the top of the hot legs, transfers heat to the secondary side water, condenses in the S/G tubes and returns to the vessel via the cold legs into the downcomer.

C. 1) Natural Circulation

2) steam flows to the S/G via the top of the hot legs, transfers heat to the secondary side water, condenses in the S/G tubes and returns to the vessel via the bottom of the hot legs.

D. 1) Natural Circulation

2) steam flows to the S/G via the top of the hot legs, transfers heat to the secondary side water, condenses in the S/G tubes and returns to the vessel via the cold legs into the downcomer.

33

34.

HL~15RRO NRC EXAM Given the following conditions: - An RCS LOCA has occurred. - Containment pressure is 13.5 psig and stable. - A loss of offsite power to 13.8 kV switchgear NAA has occurred. - RCS pressure is 1080 psig and stable. - The crew is performing 19012-C, "ES-1.2 Post-LOCA Cooldown and Depressurization. " Which ONE of the following describes the method that will be used to perform the cooldown of the RCS and the MAXIMUM cooldown rate allowed by 19012-C? A. S/G ARVs. ~ 1000 F per hour. B. S/G ARVs. Maximum rate. C. Steam Dumps. ~ 1000 F per hour. D. Steam Dumps. Maximum rate. 34

34.

HL-15RRO NRC EXAM Given the following conditions: - An RCS LOCA has occurred. - Containment pressure is 13.5 psig and stable. - A loss of offsite power to 13.8 kV switchgear NAA has occurred. - RCS pressure is 1080 psig and stable. - The crew is performing 19012-C, "ES-1.2 Post-LOCA Cooldown and Depressurization." Which ONE of the following describes the method that will be used to perform the cooldown of the RCS and the MAXIMUM cooldown rate allowed by 19012-C? A. S/G ARVs. ~ 100°F per hour. B. S/G ARVs. Maximum rate. ( C. Steam Dumps. ~ 100°F per hour. D. Steam Dumps. Maximum rate. 34

35.

- -HL-15R RO NRC EXAM The plant is at 100% power when the following annunciator is received following a circulating water pump trip: TURB CNDSR LO VAC - The SS enters AOP 18013-C, "Rapid Power Reduction." - The UO rapidly reduces turbine load. - Tave is 3.80 F higher than Tref. Which one of the following describes:

1) AOP-18013-C, power reduction target, and

2) the PREFERRED operation of the control rods in accordance with 18013-C?

Target Control Rods A. low vacuum alarm clear manual B. low vacuum alarm clear automatic C. 20% rated thermal power manual D. 20% rated thermal power automatic 35

35.

( HL-15R RO NRC EXAM The plant is at 100% power when the following annunciator is received following a circulating water pump trip: TURB CNDSR LO VAC - The SS enters AOP 18013-C, "Rapid Power Reduction." - The UO rapidly reduces turbine load. - Tave is 3.8°F higher than Tref. Which one of the following describes:

1) AOP-18013-C, power reduction target, and

2) the PREFERRED operation of the control rods in accordance with 18013-C?

Target Control Rods A. low vacuum alarm clear manual B. low vacuum alarm clear automatic C. 20% rated thermal power manual D. 20% rated thermal power automatic 35

HL~15R RO NRC EXAM

36.

( Given the following plant conditions: - The unit is at 100% power. - A Main Feedwater line break occurs at FRV # 3. RCS temperature will __ prior to the reactor trip and SG # 3 pressure will __ after a FWI occurs. Res temperature response SG # 3 pressure response A. rise stabilize B. rise completely depressurize C. lower stabilize D. lower completely depressurize 36

36.

( ( HL~15R RONRCEXAM Given the following plant conditions: - The unit is at 100% power. - A Main Feedwater line break occurs at FRV # 3. RCS temperature will __ prior to the reactor trip and SG # 3 pressure will __ after a FWI occurs. Res temperature response SG # 3 pressure response A. rise stabilize B. rise completely depressurize C. lower stabilize D. lower completely depressurize 36

HL-15R RONRC EXAM

37.

( Which one of the following choices lists conditions requiring entry into EOP 191 OO-C, "ECA-O.O Loss of All AC Power" with Unit 1 at 100% power? A. 2 of the 3 white potential lights for both 1AA02 and 1 BA03 extinguish. 1 AA02 and 1 BA03 breaker position indication lights remain lit. B. 1 of the 3 white potential lights for both 1AA02 and 1BA03 extinguish. 1 AA02 and 1 BA03 breaker position indication lights extinguish. C. 2 of the 3 white potential lights for both 1 NA01, 1 NA04 and 1 NA05 extinguish. 1 NA01, 1 NA04 and 1 NA05 breaker position indication lights remain lit. D. 1 of the 3 white potential lights for 1 NA01, 1 NA04 and 1 NA05 extinguish. 1 NA01, 1 NA04 and 1 NA05 breaker position indication lights extinguish. ( 37

37.

( HL-15R RO NRC EXAM Which one of the following choices lists conditions requiring entry into EOP 191 OO-C, "ECA-O.O Loss of All AC Power" with Unit 1 at 100% power? A. 2 of the 3 white potential lights for both 1AA02 and 1 BA03 extinguish. 1AA02 and 1 BA03 breaker position indication lights remain lit. B. 1 of the 3 white potential lights for both 1AA02 and 1 BA03 extinguish. 1 AA02 and 1 BA03 breaker position indication lights extinguish. C. 2 of the 3 white potential lights for both 1 NA01, 1 NA04 and 1 NA05 extinguish. 1 NA01, 1 NA04 and 1 NA05 breaker position indication lights remain lit. D. 1 of the 3 white potential lights for 1 NA01, 1 NA04 and 1 NA05 extinguish. 1 NA01, 1 NA04 and 1 NA05 breaker position indication lights extinguish. 37

38.

HL-15RRO NRC EXAM Given the following conditions: - Reactor power is steady-state at 100%. - Rod control is in automatic. - Sealing steam pressure drops to 0 psig due to a malfunction. Which ONE of the following conditions will result if NO operator action is taken in response to this condition? A. Lowering megawatt output and rising condenser pressure. B. Rising megawatt output and rising condenser hotweillevei. C. Lowering megawatt output and lowering condenser pressure. D. Rising megawatt output and rising steam seal header pressure. 38

38.

( ( HL-15R RO NRC EXAM Given the following conditions: - Reactor power is steady-state at 100%. - Rod control is in automatic. - Sealing steam pressure drops to 0 psig due to a malfunction. Which ONE of the following conditions will result if NO operator action is taken in response to this condition? A. Lowering megawatt output and rising condenser pressure. B. Rising megawatt output and rising condenser hotwell level.

c. Lowering megawatt output and lowering condenser pressure.

D. Rising megawatt output and rising steam seal header pressure. 38

HL-15R RO NRC EXAM

39.

Initial conditions: - ACCW pump # 1 running - A plant event results in both ESF Sequencers running, Current conditions: - Both ACCW pumps running. - The last load started at 50.5 seconds. Which ONE of the following is the CORRECT initiating event? A. SI B. U/V C. SI followed by a U/V D. U/V concurrent with an SI 39 HL-15R RO NRC EXAM

39.

Initial conditions: - ACCW pump # 1 running - A plant event results in both ESF Sequencers running, Current conditions: - Both ACCW pumps running. - The last load started at 50.5 seconds. Which ONE of the following is the CORRECT initiating event? A. SI B. U/V C. SI followed by a U/V D. U/V concurrent with an SI ( ( 39

40.

• HL~~15R RO NRC EXAM The.following indications occur with the unit at full power:

- All four SGs channel 1 NR levels go off-scale low - All four SGs channel 1 pressures go off-scale low This is a loss of __ and the correct action to take is to __ A. 1AY1A place all 4 MFRVs and MFPT SPEED CONTROL MASTER in manual and match channel 2 feed flows to channel 2 steam flows while maintaining SG NR levels. B. 1AY2A place all 4 MFRVs and MFPT SPEED CONTROL MASTER in manual and match channel 2 feed flows to channel 2 steam flows while maintaining SG NR levels. C. 1AY1A verify reactor trip and initiate 19000-C, "E-O Reactor Trip or Safety Injection". D. 1AY2A verify reactor trip and initiate 19000-C, "E-O Reactor Trip or Safety Injection". 40 HL-15R RO NRC EXAM

40.

( Thefollowing indications occur with the unit at full power: ( - All four SGs channel 1 NR levels go off-scale low - All four SGs channel 1 pressures go off-scale low This is a loss of __ and the correct action to take is to __ A. 1AY1A place all 4 MFRVs and MFPT SPEED CONTROL MASTER in manual and match channel 2 feed flows to channel 2 steam flows while maintaining SG NR levels. B. 1AY2A place all 4 MFRVs and MFPT SPEED CONTROL MASTER in manual and match channel 2 feed flows to channel 2 steam flows while maintaining SG NR levels. C. 1AY1A verify reactor trip and initiate 19000-C, "E-O Reactor Trip or Safety Injection". D. 1AY2A verify reactor trip and initiate 19000-C, "E-O Reactor Trip or Safety Injection". 40

41.

HL-15R RO NRC EXAM For the Steam Generator Water Level Control System (SGWLC), which ONE of the* following describes this systems' normal operation and program level input? A. SGWLC is a level dominant system that ultimately adjusts Feed Reg valve position by level error. Program level is constant at 65% NR. B. SGWLC is a level dominant system that ultimately adjusts Feed Reg valve position by level error. Program level is variable based on input from Auctioneered High Power Range NIS. C. SGWLC is a flow dominant system that ultimately adjusts Feed Reg valve position by mismatch in steam flow versus feed flow. Program level is constant at 65% NR. D. SGWLC is a flow dominant system that ultimately adjusts Feed Reg valve position ( by mismatch in steam flow versus feed flow. Program level is variable based on input from Auctioneered High Power Range NIS. 41

41.

HL-15R RO NRC EXAM For the Steam Generator Water Level Control System (SGWLC), which ONE of the following describes this systems' normal operation and program level input? A. SGWLC is a level dominant system that ultimately adjusts Feed Reg valve position by level error. Program level is constant at 65% NR. B. SGWLC is a level dominant system that ultimately adjusts Feed Reg valve position by level error. Program level is variable based on input from Auctioneered High Power Range NIS. C. SGWLC is a flow dominant system that ultimately adjusts Feed Reg valve position by mismatch in steam flow versus feed flow. Program level is constant at 65% NR. D. SGWLC is a flow dominant system that ultimately adjusts Feed Reg valve position ( by mismatch in steam flow versus feed flow. Program level is variable based on input from Auctioneered High Power Range NIS. ( 41

HL-15R RO NRC EXAM

42.

Given the following plant conditions: - Unit 2 Waste Gas Decay Tank (GOT) # 6 release was started at 0600. - A-RE-0014, Waste Gas Radiation Monitor is reading as expected. - The Aux. Building SO has given you Data Sheet 1 of SOP-13202-2, "Gaseous Releases" for your evaluation (Reference provided). Which ONE of the following describes the required action to perform, and why? A. Continue the release, all indications are as expected for a release. B. Stop the release, indications of an accidental release are present. C. Stop the release, indications of a GOT relief valve lifting are present. O. Continue the release, the pressure change in Unit 2 GOT # 6 is expected. ( 42 HL-15R RO NRC EXAM

42.

Given the following plant conditions: - Unit 2 Waste Gas Decay Tank (GOT) # 6 release was started at 0600. - A-RE-0014, Waste Gas Radiation Monitor is reading as expected. - The Aux. Building SO has given you Data Sheet 1 of SOP-13202-2, "Gaseous Releases" for your evaluation (Reference provided). Which ONE of the following describes the required action to perform, and why? A. Continue the release, all indications are as expected for a release. B. Stop the release, indications of an accidental release are present. C. Stop the release, indications of a GOT relief valve lifting are present. O. Continue the release, the pressure change in Unit 2 GOT # 6 is expected. ( ( 42

43.

- HL~15RRO-NRC EXAM Given the following conditions: - Manual reactor trip from 65% power. - All AFW pumps are running. - All MDAFW valves are throttled to 50 gpm per SG. - All TDAFW valves are throttled completely closed. - Both MFPTs are tripped per EOP direction. Steam Generator NR levels are stable as follows: SG # 1 - 40%, SG #2 - 37%, SG # 3 - 36%, SG # 4 - 41% Which ONE of the following describes the AFW system effect on the SG levels following a spurious Safety Injection? SG # 1 and # 4 levels SG # 2 and # 3 levels A. stable stable B. stable rising

c.

rising stable D. rising rising 43 HL-15R-RO NRC EXAM

43.

( Given the following conditions: ( - Manual reactor trip from 65% power. - All AFW pumps are running. - All MDAFW valves are throttled to 50 gpm per SG. - All TDAFW valves are throttled completely closed. - Both MFPTs are tripped per EOP direction. Steam Generator NR levels are stable as follows: SG # 1 - 40%, SG # 2 - 37%, SG # 3 - 36%, SG # 4 - 41% Which ONE of the following describes the AFW system effect on the SG levels following a spurious Safety Injection? SG # 1 and # 4 levels SG # 2 and # 3 levels A. stable stable B. stable rising C. rising stable D. rising rising 43

44.

HL~15R RONRC EXAM Given the following conditions: - Unit 1 core offload commences 150 hours after reactor shutdown. - All FHB ventilation systems are in normal lineup for this condition. A fuel handling event has occurred in the Spent Fuel Pool area resulting in the following alarms: - 1 RE-0008, "FHB Area" monitor is in HIGH alarm. - ARE-2532A, "FHB Effluent" monitor is in HIGH alarm. Which ONE of the following describes additional radiation monitors expected to be in alarm, if any, and the expected FHB HVAC lineup? A. RE-12442A, B, C, Plant Vent Rad Monitors. The FHB Normal supply and exhaust fans discharge to the plant vent duct work. B. RE-12442A, B, C, Plant Vent Rad Monitors. The FHB Normal supply and exhaust dampers close, the FHB Normal supply and exhaust fans trip. C. No additional radiation monitors would alarm. The FHB Normal supply and exhaust fans discharge to the plant vent duct work. D. No additional radiation monitors would alarm. The FHB Normal supply and exhaust dampers close, the FHB Normal supply and exhaust fans trip. 44 HL-15R RO NRC EXAM

44.

~ Given the following conditions: ( ( - Unit 1 core offload commences 150 hours after reactor shutdown. - All FHB ventilation systems are in normal lineup for this condition. A fuel handling event has occurred in the Spent Fuel Pool area resulting in the following alarms: - 1 RE-0008, "FHB Area" monitor is in HIGH alarm. - ARE-2532A, "FHB Effluent" monitor is in HIGH alarm. Which ONE of the following describes additional radiation monitors expected to be in alarm, if any, and the expected FHB HVAC lineup? A. RE-12442A, B, C, Plant Vent Rad Monitors. The FHB Normal supply and exhaust fans discharge to the plant vent duct work. B. RE-12442A, B, C, Plant Vent Rad Monitors. The FHB Normal supply and exhaust dampers close, the FHB Normal supply and exhaust fans trip. C. No additional radiation monitors would alarm. The FHB Normal supply and exhaust fans discharge to the plant vent duct work. D. No additional radiation monitors would alarm. The FHB Normal supply and exhaust dampers close, the FHB Normal supply and exhaust fans trip. 44

45.

HL~1-5R RO NRC EXAM Given the followin~ indications: - NSCW Train A Supply header flow offscale high. - NSCW Train A Return header flow offscale low. - NSCW TRAIN A LO HDR PRESS annunciator is LIT. The NSCW Train A "low flow" annunciators are lit for: - Containment Coolers 1, 2, 5, and 6 - Reactor Cavity Cooler - DG-A - RHR pump A Which ONE of the following is the CORRECT location of the NSCW pipe break? A. NSCW return line break inside the Auxiliary Building. B. NSCW supply line break inside the Auxiliary Building. C. NSCW return line break between the Auxiliary Building and the NSCW basin. D. NSCW supply line break between the cooling tower and the Auxiliary Building. 45 HL-15R RO NRC EXAM

45.

( Given the following indications: - NSCW Train A Supply header flow offscale high. - NSCW Train A Return header flow offscale low. - NSCW TRAIN A LO HDR PRESS annunciator is LIT. The NSCW Train A "low flow" annunciators are lit for: - Containment Coolers 1,2, 5, and 6 - Reactor Cavity Cooler - DG-A - RHR pump A Which ONE of the following is the CORRECT location of the NSCW pipe break? A. NSCW return line break inside the Auxiliary Building. ( B. NSCW supply line break inside the Auxiliary Building. C. NSCW return line break between the Auxiliary Building and the NSCW basin. D. NSCW supply line break between the cooling tower and the Auxiliary Building. ( 45

46.

HL~15R~RO NRC EXAM Following a main generator trip, which ONE of the following describes the design automatic bus transfer function for the Reserve Auxiliary Transformers (RATs) for the:

1) 13.8kV buses and

2) Non-1 E 4160kV buses?

13.8kV buses Non-1E 4160kV buses A. Fast bus transfer Fast bus transfer B. Fast bus transfer Residual bus transfer

c. Residual bus transfer Fast bus transfer D. Residual bus transfer Residual bus transfer 46

46.

( ( HL-15R RO NRC EXAM Following a main generator trip, which ONE of the following describes the design automatic bus transfer function for the Reserve Auxiliary Transformers (RATs) for the:

1) 13.8kV buses and

2) Non-1E 4160kV buses?

13.8kV buses Non-1E 4160kV buses A. Fast bus transfer Fast bus transfer B. Fast bus transfer Residual bus transfer

c. Residual bus transfer Fast bus transfer D. Residual bus transfer Residual bus transfer 46

47.

HL-15R-RO-NRC EXAM During a loss of 125V DC Switchgear CD1, which ONE of the following can be performed in the control room? A. Start the TDAFW pump by opening the steam admission valve HV-51 06. B. Isolate the TDAFW steam supply valve from SG# 2 by closing HV-3019. C. Align the TDAFW pump suction from CST # 1 to CST # 2 by opening HV-5113. D. Reduce TDAFW pump discharge flow by throttling valves HV-5120, HV-5122, HV-5125 and HV-5127. 47

47.

( HL-15R RONRC EXAM During a loss of 125V DC Switchgear CD1, which ONE of the following can be performed in the control room? A. Start the TDAFW pump by opening the steam admission valve HV-51 06. B. Isolate the TDAFW steam supply valve from SG # 2 by closing HV-3019. C. Align the TDAFW pump suction from CST # 1 to CST # 2 by opening HV-5113. D. Reduce TDAFW pump discharge flow by throttling valves HV-5120, HV-5122, HV-5125 and HV-5127. 47

48.

HL-15RRO NRC EXAM Given the following conditions: - The unit is in Mode 3, normal operating temperature and pressure. - 125V DC bus AD1 is inadvertently de-energized. Which ONE of the following is CORRECT regarding:

1) QMCB remote indication for pumps powered by 4160 1 E bus AA02, and

2) their breaker protective trips while AD1 is de-energized?

1) QMCB Remote Indication A. available B. available C. NOT available D. NOT available

2) Breaker Protective Trips available NOT available available NOT available 48 HL-15R RO -NRC EXAM

48.

Given the following conditions: - The unit is in Mode 3, normal operating temperature and pressure. - 125V DC bus AD1 is inadvertently de-energized. Which ONE of the following is CORRECT regarding:

1) QMCB remote indication for pumps powered by 4160 1 E bus AA02, and

2) their breaker protective trips while AD1 is de-energized?

1) QMCB Remote Indication

2) Breaker Protective Trips A. available available B. available NOT available C. NOT available available D. NOT available NOT available

( ( 48

HL.. 15R RO-NRC EXAM

49.

Given the following plant conditions: - 0900, a loss of 125V DC power to panel 1 BD12 occurred - 0905, Safety Injection actuated As a result of the above conditions:

1) DG1 B engine will

, and

2) will annunciate in the control room.

A. start "DG1 B ENGINE CNTL POWER A FAILURE" B. start "DG1 B ENGINE CNTL POWER B FAILURE" C. NOT start "DG1 B ENGINE CNTL POWER A FAILURE" D. NOT start "DG1 B ENGINE CNTL POWER B FAILURE" 49 HL-15R RO-NRC EXAM

49.

Given the following plant conditions: - 0900, a loss of 125V DC power to panel1BD12 occurred - 0905, Safety Injection actuated As a result of the above conditions:

1) DG 1 B engine will

, and

2) will annunciate in the control room.

A. start "DG1 B ENGINE CNTL POWER A FAILURE" B. start "DG1 B ENGINE CNTL POWER B FAILURE" C. NOT start ( "DG1 B ENGINE CNTL POWER A FAILURE" D. NOT start "DG1 B ENGINE CNTL POWER B FAILURE" 49

50.

HL-15R RO-NRC EXAM-The following sequence of events has occurred: - Unit 2 instrument and service air pressures are both lowering. - The Unit 1 and Unit 2 air headers were crosstied, but are now isolated from each other. - Unit 2 Reactor is tripped.

1) The air leak was on the __, and

2) the minimum pressure that requires the units to be isolated from each other is __.

1) Air Leak Location

2) Minimum Pressure A. Service Air Header 70 psig B. Service Air Header 80 psig

c. Instrument Air Header 70 psig D. Instrument Air Header 80 psig 50

50.

( ( HL-15R RONRC EXAM The following sequence of events has occurred: - Unit 2 instrument and service air pressures are both lowering. - The Unit 1 and Unit 2 air headers were crosstied, but are now isolated from each other. - Unit 2 Reactor is tripped.

1) The air leak was on the __, and

2) the minimum pressure that requires the units to be isolated from each other is __.

1) Air Leak Location

2) Minimum Pressure A. Service Air Header 70 psig B. Service Air Header 80 psig

c. Instrument Air Header 70 psig D. Instrument Air Header 80 psig 50

51.

HL~15R RO NRC EXAM Given the following: - A fire resulted in a control room evacuation. - Operators only had time to initiate a manual reactor trip. - Attempts to open Reactor Trip Breaker "B" were NOT successful - Local control from the shutdown panels has been established Based on the current conditions:

1) Prior to local operator actions, Steam Dumps will automatically control RCS Tave at

, if not affected by the fire; AND

2) What mitigating actions are directed in AOP 18038-1, "Operation from Remote Shutdown Panels?"

A. 1) 557°F

2) Locally open 125 VDC 1 E panel breakers to close all MSIVs and BSIVs and locally control RCS Tave using the SG ARVs.

B. 1) 557°F

2) Close all MSIVs and BSIVs from the remote shutdown panels and locally control the SG ARVs to maintain RCS Tave.

C. 1) 5590 F

2) Locally open 125 VDC 1 E panel breakers to close all MSIVs and BSIVs and control RCS Tave using the SG ARVs.

D. 1) 5590 F

2) Close all MSIVs and BSIVs from the remote shutdown panels and locally control the SG ARVs to maintain RCS Tave.

51

51.

( HL~15R RO NRC EXAM Given the following: - A fire resulted in a control room evacuation. - Operators only had time to initiate a manual reactor trip. - Attempts to open Reactor Trip Breaker "B" were NOT successful - Local control from the shutdown panels has been established Based on the current conditions:

1) Prior to local operator actions, Steam Dumps will automatically control RCS Tave at

, if not affected by the fire; AND

2) What mitigating actions are directed in AOP 18038-1, "Operation from Remote Shutdown Panels?"

A. 1) 557°F

2) Locally open 125 VDC 1 E panel breakers to close all MSIVs and BSIVs and locally control RCS Tave using the SG ARVs.

B. 1) 557°F

2) Close all MSIVs and BSIVs from the remote shutdown panels and locally control the SG ARVs to maintain RCS Tave.

C. 1) 5590 F

2) Locally open 125 VDC 1 E panel breakers to close all MSIVs and BSIVs and control RCS Tave using the SG ARVs.

D. 1) 5590 F

2) Close all MSIVs and BSIVs from the remote shutdown panels and locally control the SG ARVs to maintain RCS T ave.

51

52.

( HL-15R RO NRC EXAM From the time of sample collection, the MAXIMUM time a Waste Gas Decay Tank release can be initiated and the permit still be valid is ____ _ Which of the following instrument INOPERABILITIES would require termination of the release and SS notification. Max time limit Inoperable Instrumentation A. 12 hours ARE-0014 B. 24 hours ARE-0014

c.

12 hours RE-12442C D. 24 hours RE-12442C 52 HL-15R RO NRC EXAM

52.

{ From the time of sample collection, the MAXIMUM time a Waste Gas Decay Tank ( release can be initiated and the permit still be valid is ____ _ Which of the following instrument INOPERABILITIES would require termination of the release and SS notification. Max time limit Inoperable Instrumentation A. 12 hours ARE-0014 B. 24 hours ARE-0014

c.

12 hours RE-12442C D. 24 hours RE-12442C 52

53.

HL-15R.RONRC EXAM Regarding RE-12116, Control Room Air Intake Radiation Monitor:

1) Prior to a pulse check, state the location where operators may block the actuation signal, and

2) can a high radiation signal which is still present be overridden on the QHVC panel to allow realignment of the CR HVAC system?

Location To Block QHVC Override capability A. locally in the Control Building may be overridden B. locally in the Control Building may NOT be overridden C. at the QESF panel may be overridden D. at the QESF panel may NOT be overridden 53

53.

( ( HL-15RRO NRC EXAM Regarding RE-12116, Control Room Air Intake Radiation Monitor:

1) Prior to a pulse check, state the location where operators may block the actuation signal, and

2) can a high radiation signal which is still present be overridden on the QHVC panel to allow realignment of the CR HVAC system?

Location To Block QHVC Override capability A. locally in the Control Building may be overridden B. locally in the Control Building may NOT be overridden C. at the QESF panel may be overridden D. at the QESF panel may NOT be overridden 53

54.

HL~15R RO NRC EXAM During a release of WMT # 9, the following occurs on 1 RE-0018, "Waste Effluent Radiation Monitor." - 1 RX-0018 TROUBLE light illuminates on the DPM. - 1 RE-0018 has failed offscale LOW.

1) Per SOP 13216-1, "Liquid Waste Release," the release~_

2) The release __

A. 1) is NOT required to be terminated.

2) must be terminated unless independent grab samples are collected within one hour.

B. 1) is NOT required to be terminated.

2) must be terminated unless the discharge valve alignment is re-verified within one hour.

C. 1) must be terminated.

2) can be reinitiated with the radiation monitor inoperable.

D. 1) must be terminated.

2) can NOT be reinitiated until the radiation monitor is operable.

54

54.

( HL~15R RO NRC EXAM During a release of WMT # 9, the following occurs on 1 RE-0018, "Waste Effluent Radiation Monitor." - 1 RX-0018 TROUBLE light illuminates on the DPM. - 1 RE-0018 has failed offscale LOW.

1) Per SOP 13216-1, "Liquid Waste Release," the release __

2) The release __

A. 1) is NOT required to be terminated.

2) must be terminated unless independent grab samples are collected within one hour.

B. 1) is NOT required to be terminated.

2) must be terminated unless the discharge valve alignment is re-verified within one hour.

c. 1) must be terminated.

2) can be reinitiated with the radiation monitor inoperable.

D. 1) must be terminated.

2) can NOT be reinitiated until the radiation monitor is operable.

54

HL-15R RO NRC EXAM

55.

t The plant is at full power: A large leak has caused a loss of cooling water to the TPCCW system heat exchangers and AOP-18023-C, "Loss of Turbine Plant Cooling and Closed Cooling Water Systems." Which ONE of the following:

1) is a load directly cooled by TPCCW, and

2) what is the cooling water supply to the TPCCW Heat Exchanger?

1) TPCCW Load

2) TPCCW Hx Cooling Supply A. Generator Stator Coolers Turbine Plant Cooling Water pumps B. Main Feed Pump Lube Oil Coolers Turbine Plant Cooling Water pumps C. Generator Stator Coolers Circulating Water pumps D. Main Feed Pump Lube Oil Coolers Circulating Water pumps 55

55.

( HL-15R RO NRC EXAM The plant is at full power: A large leak has caused a loss of cooling water to the TPCCW system heat exchangers and AOP-18023-C, "Loss of Turbine Plant Cooling and Closed Cooling Water Systems." Which ONE of the following:

1) is a load directly cooled by TPCCW, and

2) what is the cooling water supply to the TPCCW Heat Exchanger?

1) TPCCW Load

2) TPCCW Hx Cooling Supply A. Generator Stator Coolers Turbine Plant Cooling Water pumps B. Main Feed Pump Lube Oil Coolers Turbine Plant Cooling Water pumps C. Generator Stator Coolers Circulating Water pumps D. Main Feed Pump Lube Oil Coolers Circulating Water pumps 55

56.

HL~15RRO NRC EXAM Given the following plant conditions. - The unit is at 100% power. - Section A of AOP-18017, "Abnormal Grid Disturbances/Loss of Grid" is in use. Which ONE of the following describes the:

1) desired operation of the DG's in this condition and

2) the reason for this alignment?

A. 1) Operable and in standby.

2) To ensure the DG starts and runs properly in the event of a degraded voltage condition.

B. 1) Operable and in standby.

2) To prevent sequencer lockout on successive undervoltage conditions within a 2 hour time period.

c. 1) Powering 1 E buses with the RAT feeder breakers open.

2) To isolate safety related loads from the grid and ensure safety related loads are powered by a reliable electrical source.

D. 1) Powering 1 E buses with the RAT feeder breakers open.

2) To prevent extended unloaded or low load operation which would result in the buildup of combustion products in the engine exhausts due to incomplete fuel burn in the cylinders.

56

56.

( ( HL~15R RO NRC EXAM Given the following plant conditions. - The unit is at 100% power. - Section A of AOP-18017, "Abnormal Grid Disturbances/Loss of Grid" is in use. Which ONE of the following describes the:

1) desired operation of the DG's in this condition and

2) the reason for this alignment?

A. 1) Operable and in standby.

2) To ensure the DG starts and runs properly in the event of a degraded voltage condition.

B. 1) Operable and in standby.

2) To prevent sequencer lockout on successive undervoltage conditions within a 2 hour time period.

c. 1) Powering 1 E buses with the RAT feeder breakers open.

2) To isolate safety related loads from the grid and ensure safety related loads are powered by a reliable electrical source.

D. 1) Powering 1 E buses with the RAT feeder breakers open.

2) To prevent extended unloaded or low load operation which would result in the buildup of combustion products in the engine exhausts due to incomplete fuel burn in the cylinders.

56

HL-15R RO-NRC EXAM

57.

Which one ofthe following,describes the swing compressor design features for:

1) locally transfering control of the swing air compressor between Units 1 and 2 by positioning the handswitch(es) located on the

, and

2) source of TPCCW to the swing compressor?

A. 1) Unit 1 PMEC only

2) Unit 1 only B. 1) Unit 1 PMEC only

2) Unit 1 OR Unit 2 C. 1) Unit 1 OR Unit 2 PMEC

2) Unit 1 only D. 1) Unit 1 OR Unit 2 PMEC

2) Unit 1 OR Unit 2 57 HL-15R RO NRC EXAM

57.

( Which one of the following describes the swing compressor design features for:

1) locally transfering control of the swing air compressor between Units 1 and 2 by positioning the handswitch(es) located on the

, and

2) source of TPCCW to the swing compressor?

A. 1) Unit 1 PMEC only

2) Unit 1 only B. 1) Unit 1 PMEC only

2) Unit 1 OR Unit 2 C. 1) Unit 1 OR Unit 2 PMEC

2) Unit 1 only

( D. 1) Unit 1 OR Unit 2 PMEC

2) Unit 1 OR Unit 2 57

58.

• HL~15RRONRC*EXAM The unit is at 100% power with the following annunciator illuminated. Air pressure has just lowered to 2 psig below the alarm setpoint:

SERVICE AIR HDR LO PRESS Which ONE of the following would be the CORRECT status of PV-9375, Instrument Air to Service Air Isolation valve and the status of the standby air compressors? PV-9375 status Standby Air Compressor status A. Open Running prior to alarm receipt. S. Open Started upon receipt of the alarm. C. Closed Running prior to alarm receipt. D. Closed Started upon receipt of the alarm. 58

58.

( ( HL~15R RO NRC EXAM The unit is at 100% power with the following annunciator illuminated. Air pressure has just lowered to 2 psig below the alarm setpoint: SERVICE AIR HDR LO PRESS Which ONE of the following would be the CORRECT status of PV-9375, Instrument Air to Service Air Isolation valve and the status of the standby air compressors? PV-9375 status Standby Air Compressor status A. Open Running prior to alarm receipt. B. Open Started upon receipt of the alarm. C. Closed Running prior to alarm receipt. D. Closed Started upon receipt of the alarm. 58

59.

HL~15R RO*NRC EXAM Which ONE of the following describes tne effect a loss of all AC power for 2 hours will have on the fire detection and protection systems and the system response? A.. The fire detectors are still capable of providing actuation signals. The Local Suppression Indication Panels (LSIPs) will automatically trip open their associated clapper valves due to the loss of AC power, fire suppression is available when the fusable links melt due to heat from a fire. B. The fire detectors are NOT capable of providing any fire alarms. The Diesel Fire Pump(s) will automatically start on low fire system header pressure, fire suppression is still available from the manual hose stations. C. The fire detectors are still capable of providing actuation signals. The Diesel Fire Pump(s) will automatically start on low fire system header pressure, automatic fire suppression is still available. D. The fire detectors are NOT capable of providing any fire alarms. The Local Suppression Indication Panels (LSIPs) will automatically trip open their associated clapper valves due to the loss of AC power, fire suppression is available when the fusable links melt due to heat from a fire. 59 (

59.

HL.. 15R RO NRC EXAM Which ONE of the following describes the effect a loss of all AC power for 2 hours will have on the fire detection and protection systems and the system response? A. The fire detectors are still capable of providing actuation signals. The Local Suppression Indication Panels (LSIPs) will automatically trip open their associated clapper valves due to the loss of AC power, fire suppression is available when the fusable links melt due to heat from a fire. B. The fire detectors are NOT capable of providing any fire alarms. The Diesel Fire Pump(s) will automatically start on low fire system header pressure, fire suppression is still available from the manual hose stations. C. The fire detectors are still capable of providing actuation signals. The Diesel Fire Pump(s) will automatically start on low fire system header pressure, automatic fire suppression is still available. ( D. The fire detectors are NOT capable of providing any fire alarms. ( The Local Suppression Indication Panels (LSIPs) will automatically trip open their associated clapper valves due to the loss of AC power, fire suppression is available when the fusable links melt due to heat from a fire. 59

60.

HL-15RRO NRC EXAM Which one of the following choices correctly describes the how the CNMT Spray system is actuated by SSPS? INPUT RELAYS SLAVE RELAYS A. Energize to actuate Energize to actuate B. Energize to actuate De-energize to actuate C. De-energize to actuate De-energize to actuate D. De-energize to actuate Energize to actuate 60

60.

( ( HL-15R RO NRC EXAM Which one of the following choices correctly describes the how the CNMT Spray system is actuated by SSPS? INPUT RELAYS SLAVE RELAYS A. Energize to actuate Energize to actuate B. Energize to actuate De-energize to actuate C. De-energize to actuate De-energize to actuate D. De-energize to actuate Energize to actuate 60

61.

HL-15R RO NRC EXAM The OATC needs to report to dosimetry for a whole body count and will be absent for 35 minutes. Based on the above conditions, which one of the following meets the requirements for a "SHORT TERM RELIEF" in accordance with procedures 10003-C, "Manning the Shift" and 10004-C, "Shift Relief?" A. - The relieving operator does NOT have to be from the same shift. - The relieving operator must perform a joint board walkdown with the offgoing OATC. B. - The relieving operator must be from the same shift. - The relieving operator must perform a joint board walkdown with the offgoing OATC. C. - The relieving operator must be from the same shift. - The relieving operator does NOT have to perform a joint board walkdown with the offgoing OATC. D. - A SHORT TERM RELIEF is NOT allowed. - A COMPLETE turnover must be performed. 61

61.

( ( HL-15R RO NRC EXAM The OATC needs to report to dosimetry for a whole body count and will be absent for 35 minutes. Based on the above conditions, which one of the following meets the requirements for a "SHORT TERM RELIEF" in accordance with procedures 10003-C, "Manning the Shift" and 10004-C, "Shift Relief?" A. - The relieving operator does NOT have to be from the same shift. - The relieving operator must perform a joint board walkdown with the offgoing OATC. B. - The relieving operator must be from the same shift. - The relieving operator must perform a joint board walkdown with the offgoing OATC. C. - The relieving operator must be from the same shift. - The relieving operator does NOT have to perform a joint board walkdown with the offgoing OA TC. D. - A SHORT TERM RELIEF is NOT allowed. - A COMPLETE turnover must be performed. 61

62.

HL-15R RO NRC EXAM Per 10002-C, "Plant Operating Orders":

1) Which one of the following is the proper Standing Order numerical designator which is applicable on both units?

2) Who is responsible for enforcing proper implementation of Standing Orders on the applicable units?

1 2 A. A-2010-1 Shift Manager B. A-2010-1 Shift Supervisors C. C-2010-1 Shift Manager D. C-2010-1 Shift Supervisors 62

62.

HL-15R RO NRC EXAM Per 10002-C, "Plant Operating Orders":

1) Which one of the following is the proper Standing Order numerical designator which is applicable on both units?

2) Who is responsible for enforcing proper implementation of Standing Orders on the applicable units?

1 2 A. A-2010-1 Shift Manager B. A-2010-1 Shift Supervisors C. C-2010-1 Shift Manager D. C-2010-1 Shift Supervisors 62

63.

HL-15R RO NRC EXAM The Reactor was at 2% power with preparations to start up a MFP in progress. - The OATC notices that SUR is indicating a negative 0.3 DPM. - Reactor power has lowered from the Power Range to one decade below the POAH. Which ONE of the following actions are required in accordance with plant UOPs and NMP-OS-001, "Reactivity Management"? A. Slowly raise power back to 2% using RCS dilution in 25 gallon increments. B. Slowly raise power back to 2% by withdrawing control rods in 3 step increments. C. Continue a plant shutdown to Mode 3. Restart the Reactor in accordance with 12003-C, "Reactor Startup." D. Continue a plant shutdown to Mode 3. NRC Region II approval must be obtained before reactor restart can be performed. 63

63.

( HL-15R RO NRC EXAM The Reactor was at 2% power with preparations to start up a MFP in progress. - The OATC notices that SUR is indicating a negative 0.3 DPM. - Reactor power has lowered from the Power Range to one decade below the POAH. Which ONE of the following actions are required in accordance with plant UOPs and NMP-OS-001, "Reactivity Management"? A. Slowly raise power back to 2% using RCS dilution in 25 gallon increments. B. Slowly raise power back to 2% by withdrawing control rods in 3 step increments. C. Continue a plant shutdown to Mode 3. Restart the Reactor in accordance with 12003-C, "Reactor Startup." D. Continue a plant shutdown to Mode 3. NRC Region II approval must be obtained before reactor restart can be performed. 63

64.

HL-15R RO NRC EXAM While in Mode 1, a valve stroke test is to be performed on a Safety Related MOV per OSP-14825, "Quarterly Inservice Valve Test". - The valve is a closed Containment Isolation Phase-A (CIA) valve. Which ONE of the following actions would be allowed prior to performing the stroke test on the valve? A. Cycling the valve. B. Opening the valve. C. Lubricating the valve stem. D. Cleaning boric acid from the valve stem. 64 HL-15R RO NRC EXAM

64.

( While in Mode 1, a valve stroke test is to be performed on a Safety Related MOV per OSP-14825, "Quarterly Inservice Valve Test". ( ( - The valve is a closed Containment Isolation Phase-A (CIA) valve. Which ONE of the following actions would be allowed prior to performing the stroke test on the valve? A. Cycling the valve. B. Opening the valve. C. Lubricating the valve stem. D. Cleaning boric acid from the valve stem. 64

65.

A fail open air operated valve (AOV) with a handwheel must be tagged shut asa boundary point for a clearance. To meet NMP-AD-003-002, "Tagging Standards":

1) The handwheel is required to be __ ---'-

2) The air supply valve is ___ _

1 2 A. in the closed position required to be isolated and vented B. in the closed position not required to be isolated and vented C. in the open position required to be isolated and vented D. in the open position not required to be isolated and vented 65

65.

( HL-1-5R RO NRC EXAM-A fail open air operated valve (AOV) with a handwheel must be tagged shut as a boundary point for a clearance. To meet NMP-AD-003-002, "Tagging Standards":

1) The handwheel is required to be __ _

2) The air supply valve is ___ _

1 2 A. in the closed position required to be isolated and vented B. in the closed position not required to be isolated and vented C. in the open position required to be isolated and vented D. in the open position not required to be isolated and vented 65

HL-15R RO NRC EXAM

66.

Given the following: - Unit 1 is at 3400 F maintaining stable plant conditions - 14905-1, "RCS Leak Rate Calculation" has just been completed. The following data was recorded. - Total RCS Leakage = 11.06 gpm - Leakage to PRT = 5.79 gpm - Leakage to RCOT = 4.08 gpm Primary-to-Secondary leakage is: - SG #1 = 0.06 gpm - SG # 2 = 0.05 gpm - SG # 3 = 0.10 gpm (~ - SG # 4 = 0.06 gpm Which ONE of the following statements is CORRECT concerning the leak rate data? A. No Tech Spec LCO entry is required. B. The identified leakage LCO limit has been exceeded. C. The unidentified leakage LCO limit has been exceeded.

o. The primary-to-secondary leakage LCO limit through SG # 3 has been exceeded.

66

66.

( ( HL-15R RO NRC EXAM Given the following: - Unit 1 is at 3400 F maintaining stable plant conditions - 14905-1, "RCS Leak Rate Calculation" has just been completed. The following data was recorded. - Total RCS Leakage = 11.06 gpm - Leakage to PRT = 5.79 gpm - Leakage to RCDT = 4.08 gpm Primary-to-Secondary leakage is: - SG # 1 = 0.06 gpm - SG # 2 = 0.05 gpm - SG # 3 = 0.10 gpm - SG # 4 = 0.06 gpm Which ONE of the following statements is CORRECT concerning the leak rate data? A. No Tech Spec LCO entry is required. B. The identified leakage LCO limit has been exceeded. C. The unidentified leakage LCO limit has been exceeded. D. The primary-to-secondary leakage LCO limit through SG # 3 has been exceeded. 66

HL-15R RO NRC EXAM

67.

( A General Emergency has been declared. The Extra UO in the control room has been dispatched to the CNMT Spray pump room to valve in NSCW cooling water to the CNMT Spray pump which had been previously tagged out. The pump is necessary to protect the CNMT Barrier for the safetyand health of the general public. - The expected dose for this task is 4500 mRem TEDE. - The Extra UO has a previous TEDE exposure of 1000 mRem for the year. Which of of the following choices is correct? A. Exposure received during the emergency will be added to his previous occupational dose history for non-emergency conditions. The Extra UO will be allowed to receive this dose. B. Exposure received during the emergency will NOT be added to his previous occupational dose history for non-emergency conditions. The Extra UO will NOT be allowed to receive this dose. C. Exposure received during the emergency will be added to his previous occupational dose history for non-emergency conditions. The Extra UO will NOT be allowed to receive this dose. D. Exposure received during the emergency will NOT be added to his previous occupational dose history for non-emergency conditions. The Extra UO will be allowed to receive this dose. 67

67.

( HL-15R RO NRC EXAM A General Emergency has been declared. The Extra UO in the control room has been dispatched to the CNMT Spray pump room to valve in NSCW cooling water to the CNMT Spray pump which had been previously tagged out. The pump is necessary to protect the CNMT Barrier for the safety and health of the general public. - The expected dose for this task is 4500 mRem TEDE. - The Extra UO has a previous TEDE exposure of 1000 mRem for the year. Which of of the following choices is correct? A. Exposure received during the emergency will be added to his previous occupational dose history for non-emergency conditions. The Extra UO will be allowed to receive this dose. B. Exposure received during the emergency will NOT be added to his previous occupational dose history for non-emergency conditions. The Extra UO will NOT be allowed to receive this dose. C. Exposure received during the emergency will be added to his previous occupational dose history for non-emergency conditions. The Extra UO will NOT be allowed to receive this dose. D. Exposure received during the emergency will NOT be added to his previous occupational dose history for non-emergency conditions. The Extra UO will be allowed to receive this dose. 67

68.

c: HL-15R RO-NRC EXAM Core offload is in progress during a refueling outage. - The RO notes RE-002 and RE-003 INTERMEDIATE radiation alarms illuminate. Which ONE of the following is CORRECT regarding:

1) What Tech Spec position has the authority suspend core alterations?

2) What the PA announcement for Containment evacuation should instruct?

1 A. RO or SS B. RO or SS C. SS only D. SS only 68 2 report to the Control Building HP Control Point for radiological monitoring. personnel exiting CNMT should remain in the vicinity until radiological monitoring and accountability are complete. report to the Control Building HP Control Point for radiological monitoring. personnel exiting CNMT should remain in the vicinity until radiological monitoring and accountability are complete. HL-15R RO NRC EXAM

68.

( Core offload is in progress during a refueling outage. ( - The RO notes RE-002 and RE-003 INTERMEDIATE radiation alarms illuminate. Which ONE of the following is CORRECT regarding:

1) What Tech Spec position has the authority suspend core alterations?

2) What the PA announcement for Containment evacuation should instruct?

1 A. RO orSS B. RO or SS C. SS only D. SS only 68 2 report to the Control Building HP Control Point for radiological monitoring. personnel exiting CNMT should remain in the vicinity until radiological monitoring and accountability are complete. report to the Control Building HP Control Point for radiological monitoring. personnel exiting CNMT should remain in the vicinity until radiological monitoring and accountability are complete.

69.

HL-15R RO NRC EXAM Which of the following choices contains BOTH activities that require PA announcements? A. Reactor Startup per 12003-C. Transfer EGGS to Cold Leg Recirculation per 19013-C. B. Reactor Shutdown per 12005-C. Transfer ECCS to Hot Leg Recirculation per 19014-C. C. Reactor Startup per 12003-C. Transfer EGCS to Hot Leg Recirculation per 19014-C. D. Reactor Shutdown per 12005-C. Transfer EGCS to Gold Leg Recirculation per 19013-C. 69

69.

( HL-15R RO NRC EXAM Which of the following choices contains BOTH activities that require PA announcements? A. Reactor Startup per 12003-C. Transfer ECCS to Cold Leg Recirculation per 19013-C. B. Reactor Shutdown per 12005-C. Transfer ECCS to Hot Leg Recirculation per 19014-C. C. Reactor Startup per 12003-C. Transfer ECCS to Hot Leg Recirculation per 19014-C. D. Reactor Shutdown per 12005-C. Transfer ECCS to Cold Leg Recirculation per 19013-C. 69

70.

HL-15R RO NRC EXAM Given the following: - Loss of all off-site power. - DG-1 B emergency tripped. - The System Operator depressed the "Emergency Trip Reset" pushbutton. - No other operator actions were performed - DG-1 B automatically restarted Which one of the following conditions caused the emergency trip and would allow an automatic restart of the DG? A. Engine Overspeed B. Generator Differential

c. Low Lube Oil Pressure D. High Jacket Water Temperature 70

70.

( ( HL-15R RO NRC EXAM Given the following: - Loss of all off-site power. - DG-1 B emergency tripped. - The System Operator depressed the "Emergency Trip Reset" pushbutton. - No other operator actions were performed - DG-1 B automatically restarted Which one of the following conditions caused the emergency trip and would allow an automatic restart of the DG? A. Engine Overspeed B. Generator Differential C. Low Lube Oil Pressure D. High Jacket Water Temperature 70

HL-15R RO NRC EXAM

71.

Which one of the following EOPs will allow the use of 19005-C, "ES-O.O Rediagnosis?" A. 19000-C, "E-O Reactor Trip or Safety Injection" B. 19002-C, 'ES-O.2 Natural Circulation Cooldown" C. 19012-C, "ES-1.2 Post-LOCA Cooldown & Depressurization" D. 19231-C, "FR-H.1 Response to Loss of Secondary Heat Sink" 71 HL-15R RO NRC EXAM

71.

Which one of the following EOPs will allow the use of 19005-C, "ES-O.O Rediagnosis?" A. 19000-C, "E-O Reactor Trip or Safety Injection" B. 19002-C, 'ES-O.2 Natural Circulation Cooldown" C. 19012-C, "ES-1.2 Post-LOCA Cooldown & Depressurization" D. 19231-C, "FR-H.1 Response to Loss of Secondary Heat Sink" ( 71

72.

HL-15R RO NRC EXAM Given the following: - A LOCA outside Containment has occurred. - The crew is performing 19112-C, "LOCA Outside Containment". Which ONE of the following is:

1) the FIRST system to be isolated from the RCS to attempt leak isolation, and

2) the parameter monitored to determine if the leak has been isolated?

1) First System Isolated

2) Parameter Monitored A.

RHR RCS temperature B. C. D. RHR SI SI RCS pressure RCS temperature RCS pressure 72 HL-15R RO NRC EXAM

72.

Given the following: - A LOCA outside Containment has occurred. - The crew is performing 19112-C, "LOCA Outside Containment". Which ONE of the following is:

1) the FIRST system to be isolated from the RCS to attempt leak isolation, and

2) the parameter monitored to determine if the leak has been isolated?

1) First System Isolated

2) Parameter Monitored A.

RHR RCS temperature B. RHR RCS pressure C. SI RCS temperature D. SI RCS pressure ( ( 72

HL-15R RO NRC EXAM

73.

( Given the following: ( - 19231-C, Response to Loss of Secondary Heat Sink is in effect. - RCS Feed and Bleed requirements have NOT been met. - Th,e crew is currently trying to establish AFW, MFW, or Condensate flow. Which ONE of the following identifies the actions the crew will take regarding RCP operation and the bases? A. Trip the RCPs. Conserves S/G inventory delaying the need for feed and bleed. B. Trip the RCPs. Establishing natural circulation will tend to mitigate the transient. C. Leave the RCPs running. Prevents thermal and / or boric acid stratification. D. Leave the RCPs running. Ensures RCS pressure reduction capability. 73

73.

( ( HL-15R RO NRC EXAM Given the following: - 19231-C, Response to Loss of Secondary Heat Sink is in effect. - RCS Feed and Bleed requirements have NOT been met. - Th,e crew is currently trying to establish AFW, MFW, or Condensate flow. Which ONE of the following identifies the actions the crew will take regarding RCP operation and the bases? A. Trip the RCPs. Conserves S/G inventory delaying the need for feed and bleed. B. Trip the RCPs. Establishing natural circulation will tend to mitigate the transient. C. Leave the RCPs running. Prevents thermal and / or boric acid stratification. D. Leave the RCPs running. Ensures RCS pressure reduction capability. 73

74.

c ( HL-15R RO NRC EXAM Given the following plant conditions: - A reactor trip concurrent with an LOSP to both RATs has occurred. - 19232-G, "FR-H.2 Response to Steam Generator Overpressure" YELLOW path is in effect. - SG # 4 pressure is 1247 psig. Which ONE of the following actions would mitigate the SG # 4 overpressure condition in accordance with 19232-C? A. Stop RCP # 4 to reduce the heat input to SG # 4. B. Initiate maximum AFW flow to SG # 4 to inject cold water. C. Locally operate SG # 4 ARV PV-3030 to dump steam to the atmosphere. D. Operate Steam Dumps in MANUAL in STEAM PRESSURE mode to dump steam. 74

74.

( HL-15R RO NRC EXAM Given the following plant conditions: - A reactor trip concurrent with an LOSP to both RATs has occurred. - 19232-G, "FR-H.2 Response to Steam Generator Overpressure" YELLOW path is in effect. - SG # 4 pressure is 1247 psig. Which ONE of the following actions would mitigate the SG # 4 overpressure condition in accordance with 19232-C? A. Stop RCP # 4 to reduce the heat input to SG # 4. B. Initiate maximum AFW flow to SG # 4 to inject cold water. C. Locally operate SG # 4 ARV PV-3030 to dump steam to the atmosphere. D. Operate Steam Dumps in MANUAL in STEAM PRESSURE mode to dump steam. 74

75.

-HL-15R RONRC -EXAM Initial plant conditions: - The plant is in Mode 3. - An RCS leak has occurred in Containment. - The Containment Atmosphere sample valves for RE-2562A, B, C are open. Current plant conditions: - Containment Pressure is 1.2 psig and slowly rising. - Steam lines pressures are all - 1080 psig and stable. - PRZR pressure is 2235 psig and stable. - RE-002 and 003 high rad alarms lit on the SRDC. - The SS has entered 19253-C, "FR-Z.3, Response to Containment High Radiation Level" YELLOW path. Which ONE of the following would be the CORRECT status of the: (assume all systems function as designed, if required).

1) Containment Atmosphere sample valves, and

2) the Piping Penetration Area Filtration Units?

1 2 A. open in standby B. open auto started C. closed in standby D. closed auto started 75

75.

HL-15R RO NRC EXAM Initial plant conditions: - The plant is in Mode 3. - An RCS leak has occurred in Containment. - The Containment Atmosphere sample valves for RE-2562A, B, C are open. Current plant conditions: - Containment Pressure is 1.2 psig and slowly rising. - Steam lines pressures are all - 1080 psig and stable. - PRZR pressure is 2235 psig and stable. - RE-002 and 003 high rad alarms lit on the SRDC. - The SS has entered 19253-C, "FR-Z.3, Response to Containment High Radiation Level" YELLOW path. Which ONE of the following would be the CORRECT status of the: -{ (assume all systems function as designed, if required).

1) Containment Atmosphere sample valves, and

2) the Piping Penetration Area Filtration Units?

1 2 A. open in standby B. open auto started C. closed in standby D. closed auto started ( 75

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ANSWER KEY REPORT for HL'-t5R RO NRC EXAM Test Form: 0 001K2.052 D 002A2.03 2 C 3 003AK3.10 2 A 4 003G2.4.35 2 C 5 004G2.lo23 1 B 6 004K6.31 1 C 7 005K2.033 D 8 005K6.032 C 9 006K6.022 C 10 007EG2.4.31 3 D 11 007Kl.032 A 12 007K4.01 1 C 13 008AAl.041 B 14 008K2.021 A 15 009EK2.031 C 16 010Klo082 C 17 011EG2.2.38 1 A 18 012Klo05 1 B 19 012K5.01 1 C 20 013K5.023 D 21 015AK2.071 C 22 016Klo081 D onAloOl 1 A onA2.031 c 25 022AKloOl 1 D 26 025AA1.l91 D 27 026A3.023 D 28 027AAlo052 B 29 028K5.012 A 30 032AA2.071 C 31 033Alo021 C 32 035G2.2.40 1 C 33 038EKlo043 A 34 039A2.01 2 C 35 051AAlo042 B 36 054AKlo012 A 37 055EG2.4.02 1 A 38 055K3.012 A 39 056AK3.012 B 40 057AA2.051 A 41 059A3.021 A 42 060AG2.1.252 B 43 061AloOl 1 A 44 061AK2.01 1 B 062AA2.021 D 062G2.lo27 1 B Thursday, February 25,20101 :16:11 PM 1 I \\, 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 ID II' 001K2.052 002A2.032 003AK3.10 2 003G2.4.35 2 004G2.1.23 1 004K6.31 1 005K2.033 005K6.032 006K6.022 007EG2.4.31 3 007K1.032 007K4.01 1 008AA1.041 008K2.021 009EK2.031 010K1.082 01IEG2.2.38 1 012K1.051 012K5.01 1 013K5.023 015AK2.071 016K1.081 022A1.01 1 022A2.031 022AK1.01 1 025AA1.191 026A3.023 027AA1.052 028K5.012 032AA2.071 033Al.021 035G2.2.40 1 038EKl.043 039A2.012 051AA1.042 054AKl.012 055EG2.4.02 1 055K3.012 056AK3.012 057AA2.051 059A3.021 060AG2.1.252 061A1.01 1 061AK2.01 1 062AA2.02 1 062G2.1.27 1 ANSWER KEY REPORT for HL-t5R RO NRC EXAM Test Form: 0

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Answers---------

0 lWC' Ac:\\\\T: D C A C B C D C C D A C B A C C A B C D C D A C D D D B A C C C A C B A A A B A A B A B D B Thursday, February 25, 20101 :16:11 PM 1

_J 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 C":> 71 72 73 74 75 063K2.011 063K4.021 064A2.13 1 065AA2.031 068AK3.021 071K4.061 073A4.021 073K3.012 076K3.021 077AK3.022 078K4.011 079A4.01 1 086K6.042 103A4.031 G2.1.033 G2.1.152 G2.1.372 G2.2.121 G2.2.l32 G2.2.421 G2.3.042 G2.3.l32 G2.4.30 1 G2.4.351 WEOIEK1.21 WE04EK2.21 WE05EK3.2 1 WE13EA1.11 WE16EK1.12 ANSWER KEY REPORT forHL-15R RO NRC EXAM Test Form: 0 -- B D B D C B C C B A A A C A B D C B B B D B A C C B A C D Thursday, February 25,20101 :16:11 PM 2 ANSWER KEY REPORT for HL-15R RO NRC EXAM Test Form: 0

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Answers---------

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<\\Iw:< < ~If:" ii: l {- d~d>4 ( 063K2.01 1 B .J 063K4.021 D 49 064A2.13 1 B 50 065AA2.031 D 51 068AK3.021 C 52 071K4.061 B 53 073A4.021 C 54 073K3.012 C 55 076K3.021 B 56 077AK3.022 A 57 078K4.01 1 A 58 079A4.01 1 A 59 086K6.042 C 60 103A4.031 A 61 G2.1.033 B 62 G2.1.152 D 63 G2.1.372 C 64 G2.2.121 B 65 G2.2.132 B 66 G2.2.42 1 B 67 G2.3.042 D 68 G2.3.132 B G2.4.30 1 t G2.4.35 1 A C 71 WE01EK1.21 C 72 WE04EK2.21 B 73 WE05EK3.2 1 A 74 WE13EAl.l1 C 75 WE16EKl.l 2 D { \\ Thursday, February 25,2010 1 :16:11 PM 2}}