ML101110355
| ML101110355 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/20/2010 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML101110355 (124) | |
Text
u.s. Nucle~r Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:
Date: 03-05-2010 Facility/Unit: Vogtle 1 & 2 Region:
I D II
- III D IV D Reactor Type: wll CEDBWDGED 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 overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results RO/SRO-Only/Total Examination Values 75
/
25
/ 100 Points Applicant's Scores
/ -- / --
Points Applicant's Grade
/ -- / --
Percent U.S. Nuclear Regulatory Commission Site-Specific SRO 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. CEDBWDGED 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 overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results RO/SRO-Only/Total Examination Values 75
/
25
/ 100 Points Applicant's Scores
/ -- / --
Points Applicant's Grade
/ -- / --
Percent
Date: 03-05-2010 VEGPNRC SRO Examination Answer Sheet Student Name:
- 1.
- 26.
5l.
- 76.
- 2.
- 27.
- 52.
- 77.
- 3.
- 28.
- 53.
- 78.
- 4.
- 29.
- 54.
- 79.
- 5.
- 30.
- 55.
- 80.
- 6.
- 31.
- 56.
- 81.
- 7.
- 32.
- 57.
- 82.
- 8.
- 33.
- 58.
- 83.
- 9.
- 34.
- 59.
- 84.
- 10.
- 35.
- 60.
- 85.
II.
- 36.
6l.
- 86.
- 12.
- 37.
- 62.
- 87.
(
- 13.
- 38.
- 63.
- 88.
- 14.
- 39.
- 64.
- 89.
- 15.
- 40.
- 65.
- 90.
- 16.
- 41.
- 66.
9l.
- 17.
- 42.
- 67.
- 92.
- 18.
- 43.
- 68.
- 93.
- 19.
- 44.
- 69.
- 94.
- 20.
- 45.
- 70.
- 95.
- 21.
- 46.
7l.
- 96.
- 22.
- 47.
- 72.
- 97.
- 23.
- 48.
- 73.
- 98.
- 24.
- 49.
- 74.
- 99.
- 25.
- 50.
- 75.
100.
/
(
Date: 03-05-2010 VEGP NRC SRO Examination Answer Sheet Student Name:
- 1.
- 26.
- 51.
- 76.
- 2.
- 27.
- 52.
- 77.
- 3.
- 28.
- 53.
- 78.
- 4.
- 29.
- 54.
- 79.
- 5.
- 30.
- 55.
- 80.
- 6.
- 31.
- 56.
- 81.
- 7.
- 32.
- 57.
- 82.
- 8.
- 33.
- 58.
- 83.
- 9.
- 34.
- 59.
- 84.
- 10.
- 35.
- 60.
- 85.
- 11.
- 36.
- 61.
- 86.
- 12.
- 37.
- 62.
- 87.
l
- 13.
- 38.
- 63.
- 88.
- 14.
- 39.
- 64.
- 89.
- 15.
- 40.
- 65.
- 90.
- 16.
- 41.
- 66.
- 91.
- 17.
- 42.
- 67.
- 92.
- 18.
- 43.
- 68.
- 93.
- 19.
- 44.
- 69.
- 94.
- 20.
- 45.
- 70.
- 95.
- 21.
- 46.
- 71.
- 96.
- 22.
- 47.
- 72.
- 97.
- 23.
- 48.
- 73.
- 98.
- 24.
- 49.
- 74.
- 99.
- 25.
- 50.
- 75.
100.
- 1.
HL*15RSRO 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.1NB09and1NB10 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*15RSRO 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.1NB09and1NB10 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-15RSRO 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
- 2.
(
(
HL-15R SRO 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
- 3.
(
HL-1SRSRO 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 SRO 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-15R SRONRC 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 SRO 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-1SRSRO -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-0121is 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 SRONRC 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
- 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
- 6.
(
HL-15R SRO NRC EXAM 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 SRO NRC EXAM Which ONE ofthe 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 SRO 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 SRO 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, 1HV-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
- 8.
HL-15RSRO 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, 1HV-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 SRO 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 SRO 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
-H.L-15RSRO. NRC EXAM
- 10.
A loss of offsite power resulted inan automatic plant trip.
- Red lights are LIT on all RCP 1 E handswitches.
- Red lights 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 SRO 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 lights 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*15RSRO 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 SRO 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 SRO 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
- 12.
(
HL-15R SRO 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 _--l..(1:-J.) __ aligned to be directly cooled by _....I(=2J...) __
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 SRO 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 SRO 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 MFPT strip?
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
- 14.
--HL-15R SRO 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, EDG-2A
- 14.
HL-15R SRO 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
- 15.
HL-15R SRO NRC 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
- 15.
t,
HL-15R SRO NRC 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-15R SRO NRC EXAM Complete the following statement for the PRZR Pressure Control System:
When PRZR levellowers __, 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 HL-15R SRO NRC EXAM
- 16.
Complete the following statement for the PRZR Pressure Control System:
When PRZR levellowers __, then __
wi" de-energize, if energized.
A. below 17%
ONLY the backup heaters B. 5% below program level backup and proportional heaters C. below 17%
backup and proportional heaters D. 5% below program level ONLY the backup heaters
(
16
- 17.
-HL-15R SRO 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
- 17.
(
-HL-15R SRO 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 SRO.NRC EXAM Five minutes following a reactor trip and safety injection, the OATC places Train A 81 reset handswitch in the "reset" position.
P-4 Train A will be generated when the Train A reactor trip breaker is open..J.1L.
81 reset will blockflL.
A. (1) and the Train B bypass breaker is open (2) only the Train A PRZR Low Pressure 81 and Low 8teamline Pressure 81 signals B. (1) and the Train A bypass breaker is open (2) all Train A automatic 81 signals C. (1) or the Train A bypass breaker is open (2) only the Train A PRZR Low Pressure 81 and Low 8teamline Pressure 81 signals D. (1) or the Train B bypass breaker is open (2) all Train A automatic 81 signals 18
- 18.
HL-15R SRO NRC EXAM Five minutes following a reactor trip and safety injection, the GATC 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..ilL.
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-15R SRO 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
- 19.
(
HL-15R SRO 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 OT ONB Overtemperature OT Excessive fuel heat generation rate (kW 1ft)
PRZR High Pressure RCS integrity PRZR Low Pressure ONB B. Overpower OT Excessive fuel heat generation rate (kW 1ft)
Overtemperature OT ONB PRZR High Pressure RCCA drive housing rupture PRZR Low Pressu re Excessive RCS cooldown C. Overpower OT Excessive fuel heat generation rate (kW 1ft)
Overtemperature OT ONB PRZR High Pressure RCS integrity PRZR Low Pressure ONB O. Overpower OT ONB Overtemperature OT Excessive fuel heat generation rate (kW 1ft)
PRZR High Pressure RCCA drive housing rupture PRZR Low Pressure Excessive RCS cooldown 19
- 20.
-HL-15R SRO 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 impacton 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-15R SRO 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
- 21.
HL-15R -SRO 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 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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-15RSRO 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 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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*15RSRO 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 SRO NRC EXAM Given the following conditions:
- The unit is at 100% power.
- PRZR pressure control is selected to the 457 / 456 position.
The OA TC 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 SRO 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 SRO 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-15R SRO NRC EXAMc 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 Sisignal 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
B. 1) low
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 SRO NRC EXAM Initial conditions:
A steamline break inside containment has occurred EOP 19010-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
B. 1) low
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*15RSRO 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*15RSRO 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.
(
HL-15R S.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-15R SRO 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
- 27.
HL-15R SRO 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 SRO 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
HL*15RSRO 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-15R SRO 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*15RSRO 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
- 29.
(
HL-15R SRO 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 SRO 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
- 30.
(
HL--15R SRO 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 SRO 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 SRO 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-15R SRO. 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
Leo 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 SRO 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
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
- 33.
H-L-15R SRONRC 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 - 465°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 iegs into the downcomer.
33
- 33.
t HL-15R SRO 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-15RSRO NRC EXAM Given the following conditions:
- An ReS 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.
- 8. S/G ARVs.
Maximum rate.
C. Steam Dumps.
~ 1000 F per hour.
D. Steam Dumps.
Maximum rate.
34
- 34.
HL-15R SRO NRC EXAM Given the following conditions:
- 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
- 35.
HL-15R SRO 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
- 35.
(
HL-15R SRO 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
- 36.
HL-tSR SRO NRC EXAM 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-tSR SRO NRC EXAM 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
- 37.
HL-15R SRO 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 1at 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 1 BA03 extinguish.
1AA02 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 SRO 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.
1 AA02 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 NAOS extinguish.
1 NA01, 1 NA04 and 1 NAOS breaker position indication lights remain lit.
D. 1 of the 3 white potential lights for 1 NA01, 1 NA04 and 1 NAOS extinguish.
1 NA01, 1 NA04 and 1 NAOS breaker position indication lights extinguish.
37
- 38.
(
HL-15R SRO 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
- 38.
(
HL-15R SRO 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-15RSRONRCEXAM-
- 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. UN C. SI followed by a UN D. UN concurrent with an SI 39 HL-15R SRO 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 UN D. UN concurrent with an SI 39
- 40.
HL-15R -SRONRC 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
- 40.
(
(
HL-15RSRO 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 SRQ NRC EXAM 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 SRQ 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 SRO NRC EXAM
- 42.
Given the following plant conditions:
- Unit2 Waste Gas Decay Tank (GDT) # 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 GDT relief valve lifting are present.
D. Continue the release, the pressure change in Unit 2 GDT # 6 is expected.
42 HL-15R SRO 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.
D. Continue the release, the pressure change in Unit 2 GOT # 6 is expected.
(
(
42
- 43.
HL-15R SRONRC 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
- 43.
(
(
HL-15R SRO 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
- 44.
-HL*15RSRO NRC EXAM Giventhe following conditions:
- Unit 1 core offload commences 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> 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 Norm'al 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
- 44.
(
HL-15R SRO NRC EXAM Given the following conditions:
- Unit 1 core offload commences 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> 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-15R SRQ-NRC EXAM 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.
S. 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
- 45.
(
HL-15R SRO NRC EXAM 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 SRO 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 SRO 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
HL-15R SRO NRC EXAM
- 47.
(
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 SRO 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
- 48.
HL-15R SRO 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 SRO 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) OMCB 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-SRO 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) 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 SRO 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) 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
- 50.
.HL-15R SRO.NRCEXAM 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
- 50.
(
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-1.SR SRO 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 HL-15RSRO NRC EXAM
- 51.
(
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) 5570 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) 5570 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
- 52.
(
HL-15R SRO 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 INOPERABIUTIES would require termination of the release and SS notification.
Max time limit Inoperable Instrumentation A.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ARE-0014 B.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ARE-0014
- c.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> RE-12442C D.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> RE-12442C 52
- 52.
(
HL-15R SRO 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ARE-0014 B.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ARE-0014
- c.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> RE-12442C D.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> RE-12442C 52
- 53.
HL-15R SRO 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
- 53.
(
HL-15R SRO 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 OHVC 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 OESF panel may be overridden D. at the OESF panel may NOT be overridden 53
- 54.
(
HL-15R SRO 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 SRO 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.
-1RE-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
- 55.
HL*15RSRO 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
- 55.
(
HL-15R SRO 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*15RSRO 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 preventsequencer lockout on successive undervoltage conditions within a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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*15RSRO 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 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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
- 57.
(
(
HL-15R SRO NRC EXAM 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 only D. 1) Unit 1 OR Unit 2 PMEC
- 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 only
(
D. 1) Unit 1 OR Unit 2 PMEC
- 2) Unit 1 OR Unit 2 57
- 58.
HL-15R SRO. 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
- 58.
(
HL-15R SRO 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 SRO NRC EXAM Which ONE of the following describes the effect a loss of all AC power for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 SRO NRC EXAM Which ONE of the following describes the effect a loss of all AC power for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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-15R SRO 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 SRO 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
- 8. 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 SRO 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 requir.ements 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 SRO 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
HL-15R SRO-NRC EXAM 62..
Per 10002-C, "Plant Operating Orders":
- 1) Which one of the following is the proper Standing Order numericaldesignator 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 SRO 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.. 1-SR SRO 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 SRO 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 SRO 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
- 64.
(
(
HL-15R SRO 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
- 65.
HL-15R SRO 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
- 65.
HL-15R SRO 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
- 66.
HL*15RSRO 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 SRO 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 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
- 67.
(
-HL*15RSRO 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. Exposu*re 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 SRO 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.
HL-15R SRO 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. ROorSS 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.
- 68.
(
(
HL-15R SRO 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.
- 69.
HL-15RSRO-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
- 69.
(
HL-15R SRONRC 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 190 13-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 SRONRC 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 SRO 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 SRO-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 SRONRC 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 SRO 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.
SI RCS pressure 72 HL-15R SRO 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.
/ \\
72
- 73.
HL-15R SRO 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.
- The 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 SRO 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.
- The 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.
.: HL-15R SRO NRC EXAM Given the following plant conditions:
- A reactor trip concurrent with an LOSP to both RATs has occurred.
- 19232-C, "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 ARVPV-3030 to dump steam to the atmosphere.
D. Operate Steam Dumps in MANUAL in STEAM PRESSURE mode to dump steam.
74
- 74.
(
(
HL-15R SRO NRC EXAM Given the following plant conditions:
- A reactor trip concurrent with an LOSP to both RATs has occurred.
- 19232-C, "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.
(
H~15R SRONRC 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 SRO 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
- 76.
(
HL-15R SRO NRC EXAM Initial conditions:
- Unit at 100% power for last 10 weeks
- All rods out at 228 steps Current conditions:
- "ROD AT BOTTOM" alarm is alarming
- Control Bank 0 rod H-8 rod bottom LED lit
- Tave is lowering
- QPTR & AFO remain within limits
- The SS enters AOP 18003-C, "Rod Control System Malfunction" Which of the following identifies the limits and required actions of AOP 18003-C during the rod recovery?
A. Do not exceed 75% thermal power, rod pulls are limited to 3 step increments.
Reset the Bank Overlap Unit to restore the RIL alarm to operable status.
B. Do not exceed 65% thermal power, rod pulls are limited to 3 step increments.
Reset the Bank Overlap Unit to restore the RIL alarm to operable status.
C. Do not exceed 75% thermal power, the 3 step rod pull limit may be suspended for this condition. Reset the PIA converter to restore the RIL alarm to operable status.
O. Do not exceed 65% thermal power, the 3 step rod pull limit may be suspended for this condition. Reset the PIA converter to restore the RIL alarm to operable status.
76
- 76.
(
(
HL-15R SRO NRC EXAM Initial conditions:
- Unit at 100% power for last 10 weeks
- All rods out at 228 steps Current conditions:
- "ROD AT BOTTOM" alarm is alarming
- Control Bank 0 rod H-8 rod bottom LED lit
- T ave is lowering
- QPTR & AFD remain within limits
- The SS enters AOP 18003-C, "Rod Control System Malfunction" Which of the following identifies the limits and required actions of AOP 18003-C during the rod recovery?
A. Do not exceed 75% thermal power, rod pulls are limited to 3 step increments.
Reset the Bank Overlap Unit to restore the RIL alarm to operable status.
B. Do not exceed 65% thermal power, rod pulls are limited to 3 step increments.
Reset the Bank Overlap Unit to restore the RIL alarm to operable status.
C. Do not exceed 75% thermal power, the 3 step rod pull limit may be suspended for this condition. Reset the PIA converter to restore the RIL alarm to operable status.
D. Do not exceed 65% thermal power, the 3 step rod pull limit may be suspended for this condition. Reset the PIA converter to restore the RIL alarm to operable status.
76
- 77.
HL-15R SRONRC EXAM Initial conditions:
- An RCP seal LOCA is in progress
- The OATC is unable to maintain PRZR level with normal charging
- SI is manually actuated
- 1 NAA de-energizes 30 seconds after the reactor trip
- All RCP breakers remain closed Current conditions:
19010-C, "E-1 Loss of Reactor or Secondary Coolant" is in progress CSFST monitoring is in progress:
- Core Cooling Orange due to low RVLlS Dynamic Range reading 40%
- CNMT Yellow due to radiation levels 800 mR/hr
- Inventory Yellow due to low PRZR level of 0%
RCS pressure is 1450 psig and slowly lowering with both CCPs and SIPs running.
REFERENCES PROVIDED The SS should...
A. direct the OATC to open the breakers for RCPs 1 & 3 and then delcare an Alert emergency.
B. direct the OATC to open the breakers for all four RCPs and then declare a Site Area emergency.
C. direct the OATC to open the breakers for RCPs 1 & 3 and then delcare a Site Area emergency.
D. direct the OATC to open the breakers for all four RCPs and then declare an Alert emergency.
77
- 77.
(
(
HL-15R SRONRC EXAM Initial conditions:
- An RCP seal LOCA is in progress
- The OATC is unable to maintain PRZR level with normal charging
- SI is manually actuated
- 1 NAA de-energizes 30 seconds after the reactor trip
- All RCP breakers remain closed Current conditions:
19010-C, "E-1 Loss of Reactor or Secondary Coolant" is in progress CSFST monitoring is in progress:
- Core Cooling Orange due to low RVLlS Dynamic Range reading 40%
- CNMT Yellow due to radiation levels 800 mR/hr
- Inventory Yellow due to low PRZR level of 0%
RCS pressure is 1450 psig and slowly lowering with both CCPs and SIPs running.
REFERENCES PROVIDED The SS should...
A. direct the OATC to open the breakers for RCPs 1 & 3 and then delcare an Alert emergency.
B. direct the OATC to open the breakers for all four RCPs and then declare a Site Area emergency.
C. direct the OA TC to open the breakers for RCPs 1 & 3 and then delcare a Site Area emergency.
D. direct the OA TC to open the breakers for all four RCPs and then declare an Alert emergency.
77
- 78.
(
HL-15R SRO NRC EXAM 19241-C, "FR-P.1 Response to Imminent Pressurized Thermal Shock" is being implemented.
- RCS WR pressure is 2335 psig
- RCS WR cold leg temperatures are 1900 F and stable
- All RCPs are stopped
- PRZR level is 15%
The SS is at Step 23 of 19241-C (REFERENCE PROVIDED)
The SS will direct the OATC to depressurize the RCS to lower subcooling using
- 1)
, and the first parameter from Step 23 that will be met to stop the depressurization is
- 2) __
A. 1) auxiliary spray
- 2) RCS pressure less than 125 psig B. 1) one train of COPS
- 2) RCS pressure less than 125 psig C. 1) auxiliary spray
- 2) RCS subcooling 24 to 34 degrees F D. 1) one train of COPS
- 2) RCS subcooling 24 to 34 degrees F 78
- 78.
(
HL-15R SRO NRC EXAM 19241-C, "FR-P.1 Response to Imminent Pressurized Thermal Shock" is being implemented.
- RCS WR pressure is 2335 psig
- RCS WR cold leg temperatures are 1900 F and stable
- All RCPs are stopped
- PRZR level is 15%
The SS is at Step 23 of 19241-C (REFERENCE PROVIDED)
The SS will direct the OATC to depressurize the RCS to lower subcooling using
- 1)
,and the first parameter from Step 23 that will be met to stop the depressurization is
- 2) __
A. 1) auxiliary spray
- 2) RCS pressure less than 125 psig B. 1) one train of COPS
- 2) RCS pressure less than 125 psig C. 1) auxiliary spray
- 2) RCS subcooling 24 to 34 degrees F D. 1) one train of COPS
- 2) RCS subcooling 24 to 34 degrees F 78
- 79.
HL-15R SRONRC EXAM Safety Injection has actuated from 100% power SS is implementing EOP 1901 O-C, "E-1 Loss of Reactor or Secondary Coolant" SPDS indications for CSFSTs:
- Subcriticality - GREEN
- Core Cooling - YELLOW due to RCS subcooling < 24 F
- Heat Sink - GREEN
- Integrity - GREEN
- Containment - YELLOW due to CNMT radiation> 750 mR/hr
- Inventory - YELLOW due to PRZR level> 92%
PRZR level is 100%
RCS pressure is 1040 psig The SS is at the step 15 which reads:
- 15.
Pressure in all SGs -
STABLE OR RISING RCS pressure - STABLE OR LOWERING The correct actions to take are to...
A. return to an eariler step in 19010-C until RCS subcooling is> 24 F, then transition to 19011-C, "SI Termination".
B. return to an eariler step in 1901 O-C until SG pressures stabilize then continue with 19010-C.
C. continue with the next step in 19010-C, then start an RCS cooldown in 19012-C, "ES-1.2 Post LOCA Cooldown and Depressurization".
D. continue with the next step in 19010-C, then transition to 19011-C when RCS pressure starts increasing.
79
- 79.
(
HL-15R SRO NRC EXAM Safety Injection has actuated from 100% power SS is implementing EOP 1901 O-C, "E-1 Loss of Reactor or Secondary Coolant" SPDS indications for CSFSTs:
- Subcriticality - GREEN
- Core Cooling - YELLOW due to RCS subcooling < 24 F
- Heat Sink - GREEN
- Integrity - GREEN
- Containment - YELLOW due to CNMT radiation> 750 mRlhr
- Inventory - YELLOW due to PRZR level> 92%
PRZR level is 100%
RCS pressure is 1040 psig The SS is at the step 15 which reads:
- 15.
Pressure in all SGs -
STABLE OR RISING RCS pressure - STABLE OR LOWERING The correct actions to take are to...
A. return to an eariler step in 19010-C until RCS subcooling is > 24 F, then transition to 19011-C, "SI Termination".
B. return to an eariler step in 1901 O-C until SG pressures stabilize then continue with 19010-C.
C. continue with the next step in 1901 O-C, then start an RCS cooldown in 19012-C, "ES-1.2 Post LOCA Cooldown and Depressurization".
D. continue with the next step in 1901 O-C, then transition to 19011-C when RCS pressure starts increasing.
79
- 80.
HL*15RSRO NRC*EXAM Given the following conditions:
-.19030-C, "E-3 Steam Generator Tube Rupture" is being implemented
- Rapid RCS cooldown and depressurization have been completed
- The loop 1 PRZR spray valve is stuck open
- PRZR level is 76% and rapidly rising
- RCS pressure is 1150 psig and lowering The SS will direct the OATC to...
A. stop RCP 1 then stop RCP 4 if pressure continues to lower.
Operate ECCS pumps as necessary if RCS pressure continues to lower after stopping both RCPs. Then transition to 19133-C, "ECA-3.3 SGTR Without Pressurizer Pressure Control".
B. stop RCP 4 then stop RCP 1 if pressure continues to lower.
Transition to 19131-C, "ECA-3.1 SGTR With Loss of Reactor Coolant: Subcooled Recovery Desired" if pressure continues to lower after stopping both RCPs.
C. stop RCP 4 then stop RCP 1 if pressure continues to lower.
Operate ECCS pumps as necessary if RCS pressure continues to lower after stopping both RCPs. Then transition to 19133-C, "ECA-3.3 SGTR Without Pressurizer Pressure Control".
D. stop RCP 1 then stop RCP 4 if pressure continues to lower.
Transition to 19131-C, "ECA-3.1 SGTR With Loss of Reactor Coolant: Subcooled Recovery Desired" if pressure continues to lower after stopping both RCPs.
80
- 80.
(
(
HL-15R SRO NRC EXAM Given the following conditions:
- 19030-C, "E-3 Steam Generator Tube Rupture" is being implemented
- Rapid RCS cooldown and depressurization have been completed The loop 1 PRZR spray valve is stuck open
- PRZR level is 76% and rapidly rising
- RCS pressure is 1150 psig and lowering The SS will direct the OATC to...
A. stop RCP 1 then stop RCP 4 if pressure continues to lower.
Operate ECCS pumps as necessary if RCS pressure continues to lower after stopping both RCPs. Then transition to 19133-C, "ECA-3.3 SGTR Without Pressurizer Pressure Control".
B. stop RCP 4 then stop RCP 1 if pressure continues to lower.
Transition to 19131-C, "ECA-3.1 SGTR With Loss of Reactor Coolant: Subcooled Recovery Desired" if pressure continues to lower after stopping both RCPs.
C. stop RCP 4 then stop RCP 1 if pressure continues to lower.
Operate ECCS pumps as necessary if RCS pressure continues to lower after stopping both RCPs. Then transition to 19133-C, "ECA-3.3 SGTR Without Pressurizer Pressure Control".
D. stop RCP 1 then stop RCP 4 if pressure continues to lower.
Transition to 19131-C, "ECA-3.1 SGTR With Loss of Reactor Coolant: Subcooled Recovery Desired" if pressure continues to lower after stopping both RCPs.
80
-HL-15R SRO-NRC-EXAM--
- 81.
C Initial conditions:
- A LOCA occurred 125 minutes ago
- ECCS cold leg recirculation cooling was aligned using 19013-C, "ES-1.3 Transfer to Cold Leg Recirculation" 28 minutes ago Current conditions:
- CNMT pressure is 12 psig
- "RWST EMPTY" level alarm has just actuated
- CNMT radiation monitors RE-002 & RE-003 are in high alarm The SS is implementing 1901 O-C, "E-1 Loss of Reactor or Secondary Coolant" Which one of the following describes the actions the SS is required to take?
A. remain in 1901 O-C, and stop both CNMT spray pumps and close the pump discharge valves.
B. remain in 1901 O-C, and align both CNMT spray pumps for recirculation.
C. transfer back into 19013-C, and stop both CNMT spray pumps and close the pump discharge valves.
D. transfer back into 19013-C, and align both CNMT spray pumps for recirculation.
81
-HL-15R SRO-NRC EXAM
- 81.
Initial conditions:
- A LOCA occurred 125 minutes ago
- ECCS cold leg recirculation cooling was aligned using 19013-C, "ES-1.3 Transfer to Cold Leg Recirculation" 28 minutes ago Current conditions:
- CNMT pressure is 12 psig
- "RWST EMPTY" level alarm has just actuated
- CNMT radiation monitors RE-002 & RE-003 are in high alarm The SS is implementing 1901 O-C, "E-1 Loss of Reactor or Secondary Coolant" Which one of the following describes the actions the SS is required to take?
A. remain in 1901 O-C, and stop both CNMT spray pumps and close the pump discharge valves.
B. remain in 1901 O-C, and align both CNMT spray pumps for recirculation.
C. transfer back into 19013-C, and stop both CNMT spray pumps and close the pump discharge valves.
D. transfer back into 19013-C, and align both CNMT spray pumps for recirculation.
81
- 82.
HL~15R SRO NRC EXAM Initial conditions:
- A loss of RCS level during mid-loop operations occurred
- AOP 18019-C, "Loss of Residual Heat Removal" is implemented
- RHR pump 1 B has been stopped Current conditions:
- Core exit TCs have been verified at 129 F and increasing
- "RCS MIDLOOP LO LEVEL" alarm is lit
- RCS level is currently 185' 10" and lowering
- RCS cold and hot legs are intact (no openings)
The SS is at step B11 which reads:
B11.
Check RCS level:
- a. LESS THAN 188 FEET
- b. LESS THAN 186 FEET Which one of the following is the required method to restore RCS level in accordance with AOP 18019-C?
A. VCT using a CCP through the normal charging path into an intact cold leg.
B. RWST using a CCP through the normal charging path into an intact cold leg.
C. RWST using an SI pump through the RCS hot legs.
D. RWST using an SI pump through the RCS cold legs.
82
- 82.
HL~15R SRO NRC EXAM Initial conditions:
- A loss of RCS level during mid-loop operations occurred
- AOP 18019-C, "Loss of Residual Heat Removal" is implemented
- RHR pump 1 B has been stopped Current conditions:
- Core exit TCs have been verified at 129 F and increasing
- "RCS MIDLOOP LO LEVEL" alarm is lit
- RCS level is currently 185' 10" and lowering
- RCS cold and hot legs are intact (no openings)
The SS is at step B11 which reads:
B11.
Check RCS level:
- a. LESS THAN 188 FEET
- b. LESS THAN 186 FEET Which one of the following is the required method to restore RCS level in accordance with AOP 18019-C?
A. VCT using a CCP through the normal charging path into an intact cold leg.
B. RWST using a CCP through the normal charging path into an intact cold leg.
C. RWST using an SI pump through the RCS hot legs.
D. RWST using an SI pump through the RCS cold legs.
82
- 83.
-HL-15R SRO NRC EXAM Initial conditions:
- 19010-C, "E-1 Lost of Reactor or Secondary Coolant" has been implemented
- The OATC is monitoring CSFSTs Current conditions:
- CNMT CSFST is Orange due to high containment pressure
- The OATC reports transition to 19251-C, "FR-Z.1 Response to High Containment Pressure" is required
- Neither train of CNMT spray is operating
- RWST LO-LO LEVEL alarm is active Which one of the following choices describes the correct diagnosis and actions to take?
A. CNMT spray has failed to automatically actuate. Go to 19251-C and remain in that procedure until directed to return to "procedure and step in effect".
B. CNMT spray has failed to automatically actuate. Go to 19013-C, "ES-1.3 Transfer to Cold Leg Recirculation" and place at least one train of of ECCS in the cold leg recirculation mode of operation prior to transitioning to 19251-C.
C. CNMT spray actuation is not required. Go to 19251-C and return to 19010-C after both trains of CNMT coolers (low speed) are verified in service and proper CIA and CVI are verified.
D. CNMT spray actuation is not required. Go to 19013-C, and place at least one train of ECCS in the cold leg recirculation mode of operation prior to transitioning to 19251-C.
83
- 83.
HL~15R SRO NRC EXAM Initial conditions:
- 19010-C, "E-1 Lost of Reactor or Secondary Coolant" has been implemented
- The OATC is monitoring CSFSTs Current conditions:
- CNMT CSFST is Orange due to high containment pressure
- The OATC reports transition to 19251-C, "FR-Z.1 Response to High Containment Pressure" is required
- Neither train of CNMT spray is operating
- RWST LO-LO LEVEL alarm is active Which one of the following choices describes the correct diagnosis and actions to take?
A. CNMT spray has failed to automatically actuate. Go to 19251-C and remain in that procedure until directed to return to "procedure and step in effect".
B. CNMT spray has failed to automatically actuate. Go to 19013-C, "ES-1.3 Transfer to Cold Leg Recirculation" and place at least one train of of ECCS in the cold leg recirculation mode of operation prior to transitioning to 19251-C.
C. CNMT spray actuation is not required. Go to 19251-C and return to 19010-C after both trains of CNMT coolers (low speed) are verified in service and proper CIA and CVI are verified.
D. CNMT spray actuation is not required. Go to 19013-C, and place at least one train of ECCS in the cold leg recirculation mode of operation prior to transitioning to 19251-C.
83
- 84.
HL-t5RSRO NRC EXAM Initial conditions:
- PRZR level channel 459 failed low 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ago
- LCO 3.3.1 condition M is applicable for the failed channel
- PRZR LVL CNTL SELECT switch is in the 461/460 position
- AOP 18001-C, Sec~ion D, is being implemented Current conditions:
- I&C needs to perform an ACOT on PRZR level channel 461
- The surveillance will be late in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
- PRZR level channel 459 time to repair is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- Reactor power is 15%
The correct action(s) for the SS to take per cautions in AOP 18001-C is to...
A. bypass channel 459 using the BTl Panel AND trip channel 461 per Table D1 of AOP 18001-C.
B. Place the unit in mode 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to meet LCO 3.0.3 requirements.
C. trip channel 459 per Table D1 of AOP 18001-C AND bypass channel 461 using the BTl Panel.
D. leave channel 459 as is AND reduce power to less than P7 (10%) prior to bypassing channel 461 using the BTl Panel.
84
- 84.
HL-15R SRO NRC EXAM Initial conditions:
- PRZR level channel 459 failed low 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ago
- LCO 3.3.1 condition M is applicable for the failed channel
- PRZR LVL CNTL SELECT switch is in the 461/460 position
- AOP 18001-C, Section 0, is being implemented Current conditions:
- I&C needs to perform an ACOT on PRZR level channel 461
- The surveillance will be late in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
- PRZR level channel 459 time to repair is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- Reactor power is 15%
The correct action(s) for the SS to take per cautions in AOP 18001-C is to...
A. bypass channel 459 using the BTl Panel AND trip channel 461 per Table 01 of AOP 18001-C.
B. Place the unit in mode 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to meet LCO 3.0.3 requirements.
C. trip channel 459 per Table 01 of AOP 18001-C AND bypass channel 461 using the BTl Panel.
D. leave channel 459 as is AND reduce power to less than P7 (10%) prior to bypassing channel 461 using the BTl Panel.
84
- 85.
(
HL~15R SRO NRC EXAM Initial conditions:
- Core off-load is in progress on Unit 2
- The CNMT equipment hatch is open with a designated closure crew
- Both personnel airlock doors are open with a designated door operator
- No hoses or cables are run through the personnel airlock
- Reactor cavity water level is 219 feet Current conditions:
- A loss of all AC power occurs on Unit 2
- A spent fuel assembly is fully withdrawn in the refueling machine
- The mast is over the CNMT upender Which one of the following are the required actions the Fuel Handling Supervisor will direct for:
- 1) the spent fuel assembly in the refueling machine, and
- 2) The MINIMUM required actions to meet containment closure?
A. direct manual operation of the refueling machine to place the fuel assembly in a safe location.
Direct closure of the containment equipment hatch and ONE of the personnel airlock doors to meet technical specification action requirements.
B. direct manual operation of the refueling machine to place the fuel assembly in a safe location.
Direct closure of the containment equipment hatch and BOTH of the personnel airlock doors to meet technical specification action requirements.
C. leave the fuel assembly in its current position. Operation of the refueling machine is not possible without AC power.
Direct closure of the containment equipment hatch and ONE of the personnel airlock doors to meet technical specification action requirements.
D. leave the fuel assembly in its current position. Operation of the refueling machine is not possible without AC power.
Direct closure of the containment equipment hatch and BOTH of the personnel airlock doors to meet technical specification action requirements.
85
- 85.
(
HL-15R SRO NRC EXAM Initial conditions:
- Core off-load is in progress on Unit 2
- The CNMT equipment hatch is open with a designated closure crew
- Both personnel airlock doors are open with a designated door operator
- No hoses or cables are run through the personnel airlock
- Reactor cavity water level is 219 feet Current conditions:
- A loss of all AC power occurs on Unit 2
- A spent fuel assembly is fully withdrawn in the refueling machine
- The mast is over the CNMT upender Which one of the following are the required actions the Fuel Handling Supervisor will direct for:
- 1) the spent fuel assembly in the refueling machine, and
- 2) The MINIMUM required actions to meet containment closure?
A. direct manual operation of the refueling machine to place the fuel assembly in a safe location.
Direct closure of the containment equipment hatch and ONE of the personnel airlock doors to meet technical specification action requirements.
B. direct manual operation of the refueling machine to place the fuel assembly in a safe location.
Direct closure of the containment equipment hatch and BOTH of the personnel airlock doors to meet technical specification action requirements.
C. leave the fuel assembly in its current position. Operation of the refueling machine is not possible without AC power.
Direct closure of the containment equipment hatch and ONE of the personnel airlock doors to meet technical specification action requirements.
D. leave the fuel assembly in its current position. Operation of the refueling machine is not possible without AC power.
Direct closure of the containment equipment hatch and BOTH of the personnel airlock doors to meet technical specification action requirements.
85
- 86.
HL-15RSRO NRC EXAM A loss of RAT-1B has occurred.
Current conditions:
- OG-1 B is running with its output breaker open
- The SAT is available
- AOP 18031-C, "Loss of Class 1 E Electrical Systems" is being implemented Which one of the following describes:
- 1) the required actions per AOP 18031-C, and
- 2) The status of the PRZR heaters following the actions in 1) above?
A. 1) Emergency trip OG-1 Band re-energize 1 BA03 from the SAT.
- 2) All required groups of PRZR heaters are operable, no technical specification actions are required.
B. 1) Emergency trip OG-1 Band re-energize 1 BA03 from the SAT.
- 2) All required PRZR heaters are inoperable, enter LCO 3.0.3.
C. 1) Manually close OG-1 B output breaker to re-energize 1 BA03.
- 2) One required group of PRZR heaters is inoperable, restore PRZR heaters to operable status within Technical Specification requirements.
O. 1) Manually close OG-1 B output breaker to re-energize 1 BA03.
- 2) All required groups of PRZR heaters are operable, no technical specification actions are required.
86
- 86.
HL-15R SRO NRC EXAM A loss of RAT-1B has occurred.
Current conditions:
- OG-1 B is running with its output breaker open
- The SAT is available
- AOP 18031-C, "Loss of Class 1 E Electrical Systems" is being implemented Which one of the following describes:
- 1) the required actions per AOP 18031-C, and
- 2) The status of the PRZR heaters following the actions in 1) above?
A. 1) Emergency trip OG-1 Band re-energize 1 BA03 from the SAT.
- 2) All required groups of PRZR heaters are operable, no technical specification actions are required.
B. 1) Emergency trip OG-1 Band re-energize 1 BA03 from the SAT.
- 2) All required PRZR heaters are inoperable, enter LCO 3.0.3.
C. 1) Manually close OG-1 B output breaker to re-energize 1 BA03.
- 2) One required group of PRZR heaters is inoperable, restore PRZR heaters to operable status within Technical Specification requirements.
O. 1) Manually close OG-1 B output breaker to re-energize 1 BA03.
- 2) All required groups of PRZR heaters are operable, no technical specification actions are required.
86
- 87.
HL*15RSRO -NRC EXAM*
Unit 2 instrument air header pressure is 85 psig and lowering rapidilywith all compressors running.
The SS directs the TBO to locally isolate instrument air to the turbine building.
Which one of the following describes additional SS actions per AOP 18028-C, "Loss of Instrument Air"?
- 1) If instrument air pressure cannot be maintained> ___ initiate a reactor trip, and
- 2) initiate actions to __ _
A. 1) 80 psig
- 2) Stabilize RCS Temperatures in MODE 3 using Attachment A B. 1) 70 psig
- 2) Stabilize RCS Temperatures in MODE 3 using Attachment A C. 1) 80 psig
- 2) Cooldown to MODE 4 using Attachment B D. 1) 70 psig
- 2) Cooldown to MODE 4 using Attachment B 87
- 87.
HL*15RSRO NRC EXAM Unit 2 instrument air header pressure is 85 psig and lowering rapidily with all compressors running.
The SS directs the T80 to locally isolate instrument air to the turbine building.
Which one of the following describes additional SS actions per AOP 18028-C, "Loss of Instrument Air"?
- 1) If instrument air pressure cannot be maintained> ___ initiate a reactor trip, and
- 2) initiate actions to __ _
A. 1) 80 psig
- 2) Stabilize RCS Temperatures in MODE 3 using Attachment A B. 1) 70 psig
- 2) Stabilize RCS Temperatures in MODE 3 using Attachment A C. 1) 80 psig
- 2) Cooldown to MODE 4 using Attachment 8 D. 1) 70 psig
- 2) Cooldown to MODE 4 using Attachment 8 87
- 88.
HL-15R SRO NRC EXAM Initial conditions:
- The unit tripped from 100% power due to a control room fire
- AOP 18038-1 "Operation from Remote Shutdown Panels" was entered
- The CCPs and SI pumps were running when local control was established Current conditions:
- RCS Cold legs 1 - 4 temperatures - 5570 F
- RCS Hot legs 1 - 4 temperatures - 5590 F
- RCS Core exit temperatures - 5650 F
- WR RCS pressure - 1885 psig and rising
- PRZR level is 5% and rising
- AFW flow - 0 GPM
The SS is at the step of AOP 18038-1 to "check if ECCS flow should be reduced."
Using the above conditions:
- 1) ECCS flow reduction criteria are
, and
A. 1) met
- 2) sequentially stop the CCPs and SI pumps after verifying RCS subcooling requirements are met after each pump is stopped D. 1) NOT met
- 2) locally raise charging flow to fill the PRZR to 17% before energizing the PRZR backup heaters to prevent damage 88
- 88.
HL-15R SRO NRC EXAM Initial conditions:
- The unit tripped from 100% power due to a control room fire
- AOP 18038-1 "Operation from Remote Shutdown Panels" was entered
- The CCPs and SI pumps were running when local control was established Current conditions:
- RCS Cold legs 1 - 4 temperatures - 557°F
- RCS Hot legs 1 - 4 temperatures - 5590F
- RCS Core exit temperatures - 5650 F
- WR RCS pressure - 1885 psig and rising
- PRZR level is 5% and rising
- AFW flow - 0 GPM
The SS is at the step of AOP 18038-1 to "check if ECCS flow should be reduced."
Using the above conditions:
- 1) ECCS flow reduction criteria are
, and
A. 1) met
- 2) sequentially stop the CCPs and SI pumps after verifying RCS subcooling requirements are met after each pump is stopped D. 1) NOT met
- 2) locally raise charging flow to fill the PRZR to 17% before energizing the PRZR backup heaters to prevent damage 88
HL-15RSRO NRC EXAM
- 89. Initial conditions:
The unit is at 100% power CNMT mini-purge for pressure relief is in service Current conditions:
The DPM power supply fuse blows for RE-002, "Containment Area Low Range Monitor."
Which one of the following describes the required LCD action?
REFERENCES PROVIDED A. Restore RE-002 to operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
B. Analyze grab samples of the CNMT atmosphere once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C. Enter an INFO only LCD. All other Tech Spec LCD requirements are met.
D. Isolate the CNMT mini-purge exhaust penetration by closing and de-activiting one of the CNMT mini-purge exhaust valves within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
89 HL-15R SRO NRC EXAM
- 89. Initial conditions:
The unit is at 100% power CNMT mini-purge for pressure relief is in service Current conditions:
The DPM power supply fuse blows for RE-002, "Containment Area Low Range Monitor."
Which one of the following describes the required LCO action?
REFERENCES PROVIDED A. Restore RE-002 to operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
B. Analyze grab samples of the CNMT atmosphere once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C. Enter an INFO only LCO. All other Tech Spec LCO requirements are met.
D. Isolate the CNMT mini-purge exhaust penetration by closing and de-activiting one of the CNMT mini-purge exhaust valves within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
89
- 90.
HL~15R SRO NRC EXAM Initial conditions:
Unit 1 is at 100% power CNMT pressure relief is in progress per 13125-1, "Containment Purge System" 1RE-12442C, Plant Vent Effluent Radiogas Monitor (Low Range), is out of service Current conditions:
1 RE-12444C, Plant Vent Effluent Wide Range-Low Radiogas Monitor, fails low.
The SS will direct:
- 1) CNMT pressure relief
, and
- 2) per the ODCM.
A. termination ensure periodic grab samples of the Plant Vent are taken B. termination re-initiate CNMT pressure relief, provided samples are continuously collected with auxiliary sampling equipment C. continuation verify 1 RE-2565C, Containment Vent Effluent Radiogas Monitor, remains operable D. continuation ensure periodic grab samples of the Plant Vent occur 90 HL~15R SRO NRC EXAM
- 90.
Initial conditions:
Unit 1 is at 100% power CNMT pressure relief is in progress per 13125-1, "Containment Purge System" 1 RE-12442C, Plant Vent Effluent Radiogas Monitor (Low Range), is out of service Current conditions:
1 RE-12444C, Plant Vent Effluent Wide Range-Low Radiogas Monitor, fails low.
The SS will direct:
- 1) CNMT pressure relief
, and
- 2) per the ODCM.
A. termination ensure periodic grab samples of the Plant Vent are taken
(
B. termination
(
re-initiate CNMT pressure relief, provided samples are continuously collected with auxiliary sampling equipment C. continuation verify 1 RE-2565C, Containment Vent Effluent Radiogas Monitor, remains operable D. continuation ensure periodic grab samples of the Plant Vent occur 90
- 91.
HL-15R SRO NRC EXAM AOP 1 B02B-C "Loss of Instrument Air" is being implemented Instrument air pressure is 95 psig and lowering RCS Tave is 314 F The SS should direct the Turbine Building Operator to...
A. manually isolate the service air system when air pressure drops below BO psig.
Service air should be restored locally in the turbine building by implementing SOP 13710-1, "Service Air System" when service air pressure at the PMEC is above 97 psig to prevent excessive lowering of the instrument air system pressure.
B. manually isolate the service air system when air pressure drops below BO psig.
Service air should be restored by isolating control air to the Service Air Dryer and then resetting PV-9375 per Attachment B of AOP 1 B02B-C, "Loss of Instrument Air in Modes 4, 5, and 6" to prevent excessive service air flow.
C. verify automatic isolation of the service air system from the instrument air system at BO psig.
Service air should be restored locally in the turbine building by implementing SOP 13710-1, "Service Air System" when service air pressure at the PMEC is above 97 psig to prevent excessive lowering of the instrument air system pressure.
D. verify automatic isolation of the service air system from the instrument air system at BO psig.
Service air should be restored by isolating control air to the Service Air Dryer and then resetting PV-9375 per Attachment B of AOP 1 B02B-C, "Loss of Instrument Air in Modes 4,5, and 6" to prevent excessive service air flow.
91
- 91.
\\
(
(
HL-15R SRO NRC EXAM AOP 1 B02B-C "Loss of Instrument Air" is being implemented Instrument air pressure is 95 psig and lowering RCS Tave is 314 F The SS should direct the Turbine Building Operator to...
A. manually isolate the service air system when air pressure drops below BO psig.
Service air should be restored locally in the turbine building by implementing SOP 13710-1, "Service Air System" when service air pressure at the PMEC is above 97 psig to prevent excessive lowering of the instrument air system pressure.
B. manually isolate the service air system when air pressure drops below BO psig.
Service air should be restored by isolating control air to the Service Air Dryer and then resetting PV-9375 per Attachment B of AOP 1 B02B-C, "Loss of Instrument Air in Modes 4,5, and 6" to prevent excessive service air flow.
C. verify automatic isolation of the service air system from the instrument air system at BO psig.
Service air should be restored locally in the turbine building by implementing SOP 13710-1, "Service Air System" when service air pressure at the PMEC is above 97 psig to prevent excessive lowering of the instrument air system pressure.
D. verify automatic isolation of the service air system from the instrument air system at BO psig.
Service air should be restored by isolating control air to the Service Air Dryer and then resetting PV-9375 per Attachment B of AOP 1 B02B-C, "Loss of Instrument Air in Modes 4,5, and 6" to prevent excessive service air flow.
91
- 92.
HL~15R SRO NRC EXAM Which of the following describes the Refueling SRO responsibilities per the VEGP Technical Requirements Manual (TRM)?
The Refueling SRO must observe and directly supervise all...
A. fuel shuffle activities inside the FHB. Approve FME zone 2 entries while refueling is in progress.
B. all core alteration activities. Approve FME zone 2 entries while refueling is in progress.
C. fuel shuffle activities inside the FHB. No other concurrent duties are allowed.
D. core alteration activities. No other concurrent duties are allowed.
92
- 92.
(
(
HL-15R SRO NRC EXAM Which of the following describes the Refueling SRO responsibilities per the VEGP Technical Requirements Manual (TRM)?
The Refueling SRO must observe and directly supervise all...
A. fuel shuffle activities inside the FHB. Approve FME zone 2 entries while refueling is in progress.
B. all core alteration activities. Approve FME zone 2 entries while refueling is in progress.
C. fuel shuffle activities inside the FHB. No other concurrent duties are allowed.
D. core alteration activities. No other concurrent duties are allowed.
92
- 93.
HL... 15R SRO NRC EXAM Initial conditions:
- Core reload is in progress
- A once burned fuel assembly is in transent with the refueling machine Current conditions:
- A shift in CNMT HVAC drastically increased the noise level
- SRNI count rate is inaudible on the refueling machine The Fuel Handing Supervisor should...
A. verify that the control room can still hear the audible count rate. If the control room does not hear audible counts, then he should suspend all operations involving core alterations.
The FHS may direct that the assembly be placed into the reactor core.
B. assign a designee to monitor the audible count rate from containment. If the designee cannot hear an audible count rate then he should suspend all operations involving core alterations.
The FHS may direct that the assembly be placed into the reactor core.
C. verify that the control room can still hear the audible count rate. If the control room does not hear audible counts, then he should suspend all operations involving core alterations.
The FHS may direct that the assembly be placed in the containment upender.
D. assign a designee to monitor the audible count rate from containment. If the designee cannot hear an audible count rate then he should suspend all operations involving core alterations.
The FHS may direct that the assembly be placed in the containment upender.
93
- 93.
(
HL-15R SRO NRC EXAM Initial conditions:
- Core reload is in progress
- A once burned fuel assembly is in transent with the refueling machine Current conditions:
- A shift in CNMT HVAC drastically increased the noise level
- SRNI count rate is inaudible on the refueling machine The Fuel Handing Supervisor should...
A. verify that the control room can still hear the audible count rate. If the control room does not hear audible counts, then he should suspend all operations involving core alterations.
The FHS may direct that the assembly be placed into the reactor core.
B. assign a designee to monitor the audible count rate from containment. If the designee cannot hear an audible count rate then he should suspend all operations involving core alterations.
The FHS may direct that the assembly be placed into the reactor core.
C. verify that the control room can still hear the audible count rate. If the control room does not hear audible counts, then he should suspend all operations involving core alterations.
The FHS may direct that the assembly be placed in the containment upender.
D. assign a designee to monitor the audible count rate from containment. If the designee cannot hear an audible count rate then he should suspend all operations involving core alterations.
The FHS may direct that the assembly be placed in the containment upender.
93
- 94.
HL~15R SRO NRC EXAM-Initial conditions:
Unit 2 is at 100% power The regulating transformer associated with 2AY1A is danger tagged for maintenance The transformer has been. out of service for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Current conditions:
2AY1A has been de-energized due to inverter 2AD111 fault for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> The time to repair the inverter is estimated at 2*'-4 days The expected return to service time for the transformer is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
- 1) The SS should enter LCD
, and
- 2) due to this failure, and the Shift Manager should __ _
A. 1) 3.8.9
- 2) upgrade the work order for the regulated transformer to an emergency work order.
- 8. 1) 3.0.3
- 2) upgrade the work order for the regulated transformer to an emergency work order.
C. 1) 3.8.9
- 2) inform the work planners that the regulated transformer needs to be restored in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
D. 1) 3.0.3
- 2) inform the work planners that the regulated transformer needs to be restored in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
94
- 94.
(
HL-15R SRO NRC EXAM Initial conditions:
Unit 2 is at 100% power The regulating transformer associated with 2A Y1 A is danger tagged for maintenance The transformer has been out of service for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Current conditions:
2AY1A has been de-energized due to inverter 2AD111 fault for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> The time to repair the inverter is estimated at 2-4 days The expected return to service time for the transformer is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
- 1) The SS should enter LCO
, and
- 2) due to this failure, and the Shift Manager should __ _
A. 1) 3.8.9
- 2) upgrade the work order for the regulated transformer to an emergency work order.
B. 1) 3.0.3
- 2) upgrade the work order for the regulated transformer to an emergency work order.
C. 1) 3.8.9
- 2) inform the work planners that the regulated transformer needs to be restored in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
D. 1) 3.0.3
- 2) inform the work planners that the regulated transformer needs to be restored in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
94
- 95.
HL~15R SRO-NRC EXAM Initial conditions:
RCS T ave is 554°F T AVGITREF DEVIATION alarm is lit The UO is recording RCS loop Tave's every 15 minutes per 12003-C "Reactor Startup" The OATC has pulled control bank A rods to 50 steps Current conditions:
The OATC has pulled control bank B rods to 100 steps to continue the reactor startup The OATC is waiting for count rate stabilization T AVGITREF DEVIATION alarm is still lit The UO realizes his last set of RCS loop Tave readings were taken 45 minutes ago Which one of the following describes the actions the SS will take?
- 1) The SS will
, and
- 2) direct the OATC to ___ _
(
A. 1) declare LCO 3.4.2, "RCS Minimum Temperature for Criticality" not met
(
- 2) to insert the control bank rods within a MAXIMUM time of 60 minutes.
B. 1) declare LCO 3.4.2, "RCS Minimum Temperature for Criticality" not met
- 2) to insert the control bank rods within a MAXIMUM time of 30 minutes.
C. 1) direct the UO to record all four RCS loop Tave's within the delay period per SR 3.0.3
- 2) adjust RCS Tave to 557°F with the steam dumps prior to continuing the reactor startup if any RCS loop Tave is less than 551°F.
D. 1) direct the UO to record all four RCS loop Tave's within the delay period per SR 3.0.3
- 2) pull control rods to restore Tave to 557°F if any RCS loop Tave is less than 551°F.
95
- 95.
HL~15R SRO NRC EXAM Initial conditions:
RCS Tave is 554°F T AVGITREF DEVIATION alarm is lit The UO is recording RCS loop Tave's every 15 minutes per 12003-C "Reactor Startup" The OATC has pulled control bank A rods to 50 steps Current conditions:
The OATC has pulled control bank B rods to 100 steps to continue the reactor startup The OATC is waiting for count rate stabilization T AVG/TREF DEVIATION alarm is still lit The UO realizes his last set of RCS loop Tave readings were taken 45 minutes ago Which one of the following describes the actions the SS will take?
- 1) The SS will
,and
- 2) direct the OATC to ___ _
(
A. 1) declare LCO 3.4.2, "RCS Minimum Temperature for Criticality" not met
(
- 2) to insert the control bank rods within a MAXIMUM time of 60 minutes.
B. 1) declare LCO 3.4.2, "RCS Minimum Temperature for Criticality" not met
- 2) to insert the control bank rods within a MAXIMUM time of 30 minutes.
C. 1) direct the UO to record all four RCS loop Tave's within the delay period per SR 3.0.3
- 2) adjust RCS Tave to 557°F with the steam dumps prior to continuing the reactor startup if any RCS loop Tave is less than 551°F.
D. 1) direct the UO to record all four RCS loop Tave's within the delay period per SR 3.0.3
- 2) pull control rods to restore Tave to 557°F if any RCS loop Tave is less than 551°F.
95
- 96.
HL~15R SRO-NRC EXAM Given the following:
- Reactor Trip and Safety Injection on low PRZR pressure
- RCS pressure is now 23 psig
- CNMT pressure is now 23 psig
- CNMT radiation monitors RE-005 and RE-006 read 5.3 E+5 mRlhr
- Plant Vent Radiogas Effluent monitor RE-12444C has been reading 1.2 E+3 I-ICi/cc since the event initiation 10 minutes ago.
Determine the appropriate emergency classification based on the conditions listed above.
REFERENCES PROVIDED A. General, PAR's required on declaration message.
B. Site Area, PARs required on declaration message.
C. General, PARs NOT required on declaration message.
D. Site Area, PARs NOT required on declaration message.
96
- 96.
(
(
HL-15R SRO NRC EXAM Given the following:
- Reactor Trip and Safety Injection on low PRZR pressure
- RCS pressure is now 23 psig
- CNMT pressure is now 23 psig
- CNMT radiation monitors RE-005 and RE-006 read 5.3 E+5 mR/hr
- Plant Vent Radiogas Effluent monitor RE-12444C has been reading 1.2 E+3 IJCilcc since the event initiation 10 minutes ago.
Determine the appropriate emergency classification based on the conditions listed above.
REFERENCES PROVIDED A. General, PAR's required on declaration message.
B. Site Area, PARs required on declaration message.
C. General, PARs NOT required on declaration message.
D. Site Area, PARs NOT required on declaration message.
96
- 97.
\\.
HL~15R SRO NRC EXAM A confirmed fire in the DG-2B room has occurred. Ten minutes later the Fire Team Captain reports that the emergency diesel generator building is "Fully Involved."
- 1) The Shift Manager shall immediately notify
, and
- 2) declare a(n) ___ _
A. 1) the Burke County Emergency Management Agency (BCEMA) by dialing 911 using the Waynesboro line.
- 2) Alert.
B. 1) the Burke County Emergency Management Agency (BCEMA) by dialing 911 using the Waynesboro line, only if the Fire Team Captain requests assistance.
- 2) Notification of an Unusual Event.
C. 1) the Burke County Emergency Management Agency (BCEMA) by dialing 911 using the SouthernLinc system.
- 2) Alert.
D. 1) the Burke County Emergency Management Agency (BCEMA) by dialing 911 using the SouthernLinc system, only if the Fire Team Captain requests assistance.
- 2) Notification of an Unusual Event.
97
- 97.
(
HL~15R SRO NRC EXAM A confirmed fire in the DG-2B room has occurred. Ten minutes later the Fire Team Captain reports that the emergency diesel generator building is "Fully Involved."
- 1) The Shift Manager shall immediately notify
, and
- 2) declare a(n) ___ _
A. 1) the Burke County Emergency Management Agency (BCEMA) by dialing 911 using the Waynesboro line.
- 2) Alert.
B. 1) the Burke County Emergency Management Agency (BCEMA) by dialing 911 using the Waynesboro line, only if the Fire Team Captain requests assistance.
- 2) Notification of an Unusual Event.
C. 1) the Burke County Emergency Management Agency (BCEMA) by dialing 911 using the SouthernLinc system.
- 2) Alert.
D. 1) the Burke County Emergency Management Agency (BCEMA) by dialing 911 using the SouthernLinc system, only if the Fire Team Captain requests assistance.
- 2) Notification of an Unusual Event.
97
HL-15R*SRO NRC EXAM
- 98.
(
Initial conditions:
- An RCS leak has occurred
- The DATC had to start the second charging pump to maintain PRZR level Which of the following completes the sentences below?
- 1) The Shift Manager will declare a(n)
, and
- 2) Faxing of the ENN form by the emergency communicator _~_
A. 1) Notification of Unusal Event
- 2) is required to be performed in parallel with the ENN notification.
B. 1) Alert
- 2) is performed in parallel with the ENN notification only if time permits.
C. 1) Alert
- 2) is required to be performed in parallel with the ENN notification.
D. 1) Notification of Unusal Event
- 2) is performed in parallel with the ENN notification only if time permits.
98 HL-15RSRO NRC EXAM
- 98.
Initial conditions:
- An RCS leak has occurred
- The OATC had to start the second charging pump to maintain PRZR level Which of the following completes the sentences below?
- 1) The Shift Manager will declare a(n)
, and
- 2) Faxing of the ENN form by the emergency communicator __ _
A. 1) Notification of Unusal Event
- 2) is required to be performed in parallel with the ENN notification.
B. 1) Alert
- 2) is performed in parallel with the ENN notification only if time permits.
C. 1) Alert
- 2) is required to be performed in parallel with the ENN notification.
D. 1) Notification of Unusal Event
- 2) is performed in parallel with the ENN notification only if time permits.
98
HL-15R SR,O NRC-EXAM
- 99.
The crew is implementing EOP 19112-C, "ECA-1.2 LOCA Outside Containment".
- The COLD LEG INJECTION FROM SIS HV-8835 has been closed.
- The SS determines the leak is now isolated.
The SS will transition to... _
A. 19011-C, "ES-1.1 SI Termination".
B. 19010-C, "E-1 Loss of Reactor or Secondary Coolant".
C. 19111-C, "ECA-1.1 Loss of Emergency Coolant Recirculation".
D. 19012-C, "ES-1.2 Post-LOCA Cooldown and Depressurization".
99 HL-15R SRO NRC EXAM
- 99.
The crew is implementing EOP 19112-C, "ECA-1.2 LOCA Outside Containment".
- The COLD LEG INJECTION FROM SIS HV-8835 has been closed.
- The SS determines the leak is now isolated.
The SS will transition to...
A. 19011-C, "ES-1.1 SI Termination".
B. 19010-C, "E-1 Loss of Reactor or Secondary Coolant".
C. 19111-C, "ECA-1.1 Loss of Emergency Coolant Recirculation".
D. 19012-C, "ES-1.2 Post-LOCA Cooldown and Depressurization".
99
100.
HL~15R SRONRC EXAM-Initial conditons:
An'RCS cooldown at 500 F/hr per 19002-C, "ES-0.2 Natural Circulation Cooldown" is in progress Current conditions:
- PSMS train A DPU is inoperable
- RCS pressure is 1200 psig and lowering.
- RCS cold leg temperatures are 4500 F and lowering
., SG pressures are 435 psig and lowering
- PRZR level is 35% and rising The RCS temperature must be < 3500 F in the next 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 30 minutes to comply with a technical specification action requirement.
The correct action to take for these condtions is to...
A. continue the cooldown at the present rate. Declare an Alert emergency due to the inability to cool down the RCS to < 3500F within the technical specification LCO action time limit.
B. repressurize the RCS within the limits of LCO 3.4.3 to collapse potential voids while increasing the cooldown rate to 700 F/hr to meet the technical specification time limit.
C. transition to 19003-C; "ES-0.3 Natural Circulation Cooldown with Void in Vessel (With RVLlS)" and increase the cooldown rate to 700 F/hr to meet the technical specification time limit.
D. transition to 19004-C, "ES-O.4 Natural Circulation Cooldown with Void in Vessel (Without RVLlS)" and increase the cooldown rate to 700 F/hr to meet the technical specification time limit.
100 100.
I.
HL~15R SRO NRC EXAM Initial conditons:
An'RCS cooldown at 500 F/hr per 19002-C, "ES-0.2 Natural Circulation Cooldown" is in progress Current conditions:
- PSMS train A DPU is inoperable
- RCS pressure is 1200 psig and lowering
- RCS cold leg temperatures are 450°F and lowering
- SG pressures are 435 psig and lowering
- PRZR level is 35% and rising The RCS temperature must be < 350°F inthe next 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 30 minutes to comply with a technical specification action requirement.
The correct action to take for these condtions is to...
A. continue the cooldown at the present rate. Declare an Alert emergency due to the inability to cool down the RCS to < 350°F within the technical specification LCO action time limit.
B. repressurize the RCS within the limits of LCO 3.4.3 to collapse potential voids while increasing the cooldown rate to 700 F/hr to meet the technical specification time limit.
C. transition to 19003-C; "ES-0.3 Natural Circulation Cooldown with Void in Vessel (With RVLlS)" and increase the cooldown rate to 700 F/hr to meet the technical specification time limit.
D. transition to 19004-C, "ES-O.4 Natural Circulation Cooldown with Void in Vessel (Without RVLlS)" and increase the cooldown rate to 700F/hr to meet the technical specification time limit.
100
1 001K2.052 D
2 002A2.032 C
3 003AK3.10 2 A
4 003G2.4.35 2 C
5 004G2.1.23 1 B
6 004K6.311 C
7 005K2.033 D
8 005K6.032 C
9 006K6.022 C
10 007EG2.4.31 3 D
11 007Kl.032 A
12 007K4.011 C
13 008AAl.041 B
14 008K2.021 A
f5 009EK2.03 *1 C
16 010Kl.082 C
1'7 0IIEG2.2.38 1 A
18 012Kl.051 B
19 012K5.011 C
20 013K5.023 D
21 015AK2.071 C
22 016Kl.08 1 D
23 022Al.Ol 1 A
24 022A2.031 C
25 022AKl.Oli D
26 025AA1.191 D
27 026A3.023 D
28 027AAl.052 B
29 028K5.012 A
30 032AA2.071 C
31 033Al.021 C
32 035G2.2.40 1 C
33 038EKl.043 A
34 039A2.012 C
35 051AAl.042 B
36 054AKl.012 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 061Al.Ol 1 A
44 061AK2.011 B
45 062AA2.021 D
46 062G2.l.27 1 B
47 063K2.011 B
48 063K4.021 D
page?Of3 3/3/2010
/
Answers 001K2.0S 2 D
2 002A2.032 C
3 003AK3.10 2 A
4 003G2.4.3S 2 C
S 004G2.1.23 1 B
6 004K6.31 1 C
7 00SK2.033 D
8 00SK6.032 C
9 006K6.022 C
10 007EG2.4.313 D
11 007Kl.032 A
12 007K4.011 C
13 008AAl.041 B
14 008K2.021 A
IS 009EK2.031 C
16 010K1.082 C
17 01IEG2.2.38 1 A
18 012K1.0S 1 B
19 012KS.Ol 1 C
20 013KS.023 D
21 O1SAK2.071 C
22 016K1.08 1 D
23 022A1.01 1 A
24 022A2.031 C
2S 022AK1.011 D
26 02SAA1.191 D
27 026A3.023 D
28 027AA1.0S 2 B
29 028KS.012 A
30 032AA2.071 C
31 033Al.021 C
32 03SG2.2.40 1 C
33 038EK1.043 A
34 039A2.012 C
3S OS1AAl.042 B
36 OS4AKl.012 A
37 OSSEG2.4.02 1 A
38 OSSK3.012 A
39 OS6AK3.012 B
40 OS7AA2.0S 1 A
41 OS9A3.021 A
42 060AG2.1.2S 2 B
43 061A1.01 1 A
44 061AK2.01 1 B
4S 062AA2.021 D
46 062G2.1.27 1 B
47 063K2.01 1 B
48 063K4.021 D
page:rf3 3/312010
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 G2.2.421 B
67 G2.3.042 D
68 G2.3.13 2 B
69 G2.4.30 1 A
70 G2.4.35 1 C
71 WE01EK1.21 C
n WE04EK2.21 B
73 WE05EK3.21 A
74 WE13EAl.1 1 C
75 WE16EKl.1 2 D
76 003AG2.1.30 1 C
77 003G2.4.41 1 A
78 007A2.031 B
79 008AA2.281 C
80 010G2.1.20 1 B
81 01lEG2.4.11 2 D
82 025AG2.4.31 1 C
83 026A2.031 B
84 028AG2.4.20 1 C
85 034G2.4.20 1 A
86 056AA2.731 A
87 065AG2.1.30 3 B
88 068AA2.031 B
89 OnA2.032 B
90 073A2.022 A
91 079A2.01 1 C
92 G2.1.35 1 D
93 G2.1.40 1 D
94 G2.2.193 A
95 G2.2.352 C
96 G2.3.051 A
Page: 2 of3 3/312010 Answers 49 064A2.13 1 B
50 065AA2.031 D
51 068AK3.021 C
52 071K4.061 B
53 073A4.021 C
54 073K3.01 2 C
55 076K3.021 B
56 077AK3.022 A
57 078K4.01 1 A
58 079A4.01 1 A
59 086K6.042 C
60 103A4.03 1 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 G2.2.421 B
67 G2.3.042 D
68 G2.3.13 2 B
69 G2.4.30 1 A
70 G2.4.35 1 C
71 WE01EK1.21 C
72 WE04EK2.21 B
73 WE05EK3.21 A
74 WE13EA1.11 C
75 WE16EKl.1 2 D
76 003AG2.1.30 1 C
77 003G2.4.41 1 A
78 007A2.03 1 B
79 008AA2.281 C
80 010G2.1.20 1 B
81 011EG2.4.112 D
82 025AG2.4.31 1 C
83 026A2.031 B
84 028AG2.4.20 1 C
85 034G2.4.20 1 A
86 056AA2.731 A
87 065AG2.1.30 3 B
88 068AA2.031 B
89 072A2.032 B
90 073A2.022 A
91 079A2.01 1 C
92 G2.1.351 D
93 G2.1.40 1 D
94 G2.2.193 A
95 G2.2.352 C
96 G2.3.051 A
Page: 2 of3 3/3/2010
97 98 99 100 G2.4.27 3 G2.4.392 WE04EA2.11 WE10EA2.1 1 Page: 3 of3 A
B B
C 3/312010 Answers 97 G2.4.27 3 A
98 G2.4.392 B
99 WE04EA2.11 B
100 WE10EA2.11 C
Page: 3 of 3 3/3/2010
AwrovedBy J. O. Williams GASEOUS RELEASES*
DATA SHEET 1 TANK BEING RELEASED UNIT ().
TANK {,
INITIAL HOURLY HOURLY TIME AI 060 0 0700 OATE UNIT 1 GOT 4
s~
$8 TANK #1 PSIG UNIT 1 GOT aI 6\\
31 TANK #2 PSIG UNIT 1 GOT d
2cq
'-S4 TANK #3 PSIG UNIT 1 GOT iJI t...J6 4 5 TANK #4 PSIG UNIT 1 GOT
~
- )..6
{).6 TANK #5 PSIG UNIT 1 GOT 41 70 70 TANK #6 PSIG UNIT 1 GOT d
6Cf 6Cf TANK #7 PSIG SDT #9 PSIG 4
So So SOT #10 PSIG 4
61 b(
UNIT 2 GOT d
4 5
<..;3 TANK #1 PSIG UNIT 2 GOT
~
SJ.
S;A TANK #2 PSIG UNIT 2 GOT
,:at 71 7\\
TANK #3 PSIG UNIT 2 GOT 4/
66
{;6 TANK #4 PSIG UNIT 2 GOT I¥ 64 64 TANK #5 PSIG UNIT 2 GOT
¢:l/
78 SA TANK #6 PSIG UNIT 2 GOT 41
~,
S7 TANK #7 PSIG AI2006201868 HOURLY Procedure Number Rev 13202-2 11 Page Number 14 of 28 Sheet 1 of 1 HOURLY HOURLY FINAL Approved By
-=::F:/{",:;¥~~4~"i,~E~\\~tff:it~:~~'~~r~~:~R:~"~:l~;rili~C~~~~tj;~rsr; ProcedtJFe Number Rev J. O. Williams 13202-2 11 Date Ap proved RELEASES Page Number
'1\\ 3/18/08 GASEOUS 14 of 28 I.
P Sheet 1 of 1 DATA SHEET 1 TANK BEING RELEASED UNIT ~ TANK {,
INITIAL HOURLY HOURLY HOURLY HOURLY HOURLY FINAL TIME PI OGOO 0)00 DATE UNIT 1 GOT PI St?
!;8 TANK #1 PSIG UNIT 1 GOT a!
b \\
'3 !
TANK #2 PSIG UNIT 1 GOT 41
~q
'S'9 TANK #3 PSIG UNIT 1 GOT 4-yb 4 5 TANK #4 PSIG UNIT 1 GOT I<IL
')..6
'"'>6 TANK #5 PSIG t7\\
£6
~o l
SOT #10 PSIG 4
6 i b (
(
UNIT 2 GOT at 4 5
<-,3 TANK #1 PSIG UNIT 2 GOT PI SJ.
S;;..
TANK #2 PSIG UNIT 2 GOT Rf 7 I 7 \\
TANK #3 PSIG UNIT 2 GOT 4/
6,
bb TANK #4 PSIG UNIT 2 GOT 4/
64 04 TANK #5 PSIG UNIT 2 GOT
¢:(/
78 G7-.
TANK #6 PSIG UNIT 2 GOT 41
[;)
~ 7 TANK #7 PSIG AI2006201868
(
~.
Approved By Procedure Number Rev J.D. Williams 91001-C
.32 Date Approved 05/28/2009 Page Number 10 of 108 EMERGENCY CLASSIFICATION AND IMPLEMENTING INSTRUCTIONS
[-REFERENCE**USE
- 1. and 3.
y OR CORE COOLING I (p.32)
CSFST N
LOSS of
- 2. Coolant Activity Sample> 300 IlCi/gm Equivalent I -131 OR I CLAD BARRIER I
~
- 5. Containment Radiation Monitors RE-005/006 > 6.0 E+6 mr/hr _(~p;,;.;.3:.:3:.-'., _____ _
- 1. and 4.
CORE COOLING CSFST
- 1.
HEAT SINK CSFST y
...---'1 (p.32)
E I N y
(p.32)
N OR POTENTIAL LOSS of OR I CLAD BARRIER
- 7. Judgment:
Judgment by the ED that the Fuel Clad Barrier is Lost or Potentially Lost. Consider conditions not addressed and inability to determine the status of the Fuel Clad Barrier (p.33)
FIGURE 1 - FUEL CLADDING INTEGRITY (Modes 1, 2, 3 and 4 only)
February 25, 2010 at 13:39 OR Approved By?
..... Procedure Number Rev J.D. Williams b\\;u Vogtl~ EleCtric Generating Plant
,,\\..
',3:, 91001-C
.32 Date Approved EMERGENCY CLASSIFICATION AND IMPLEMENTING INSTRUCTIONS Page Number 05/28/2009 REFERENCE USE
- 1. and 3.
y OR CORE COOLING 1----1 (p.32)
CSFST RED N
- 2. Coolant Activity Sample> 300 JlCi/gm Equivalent 1-131 __ (u;;IP,;.;;.3;.;;;;2J-) _______
O_R-f OR
- 5. Containment Radiation Monitors RE-005/006 > 6.0 E+6 mr/hr (p.33)
~~~-----~
LOSS of CLAD BARRIER
- 1. and 4.
y CORE COOLING CSFST t~
lh..,.h N
- 1.
Y HEAT SINK CSFST RED N
OR (p.32)
(p.32)
OR POTENTIAL 1--_-1.....
LOSS of CLAD BARRIER
- 7. Judgment Judgment by the ED that the Fuel Clad Barrier is Lost or Potentially Lost. Consider conditions not addressed and inability to determine the status of the Fuel Clad Barrier (p.33)
FIGURE 1 - FUEL CLADDING INTEGRITY (Modes 1, 2, 3 and 4 only)
Pnnted February 25, 2010 at 13:39 10 of 108 OR
Approved By J.D. Williams Date Approved 05/28/2009 EMERGENCY CLASSIFICATION AND IMPLEMENTING INSTRUCTIONS REFERENCE USE
[38 ° F ADVERSE] (p.33
- 4. Containment Radiation Monitors RE-005/006 > 2.0 E+4 mr/hr (p.34)
- 1.
I : I (p. 33)
- 1.
I : I (p. 33)
- 2. NON-Isolable RCS leak (including SG tube leakage) GREATER THAN the Capacity of One Charging Pump in the normal charging mode (p.34)
- 5. Unexplained level rise in any of the following: containment sump, Reactor Coolant Drain Tank (RCDT),
Waste Holdup Tank (WHT) (p.34)
- 6. Judgment: Judgment by the ED that the RCS Barrier is Lost or Potentially Lost. Consider conditions not addressed and the inability to determine the status of the RCS Barrier (p. 34)
LOSS of RCS BARRIER Procedure Number Rev 91001.. C 32 Page Number 11 of 108 OR POTENTIAL LOSS of RCS BARRIER FIGURE 2 - REACTOR COOLANT SYSTEM (RCS) INTEGRITY (Modes 1, 2, 3 and 4 only)
Approved By j.'
Vogtle Electric Generating~l~rif:/:A :"u Procedure Number Rev J.D. Williams 1<:';
91001-C 32 Date Approved EMERGENCY CLASSIFICATION AND IMPLEMENTING INSTRUCTIONS Page Number 05/28/2009 11 of 108 I
REFERENCE USE I
[38 ° F ADVERSE] (p.33)
- 4. Containment Radiation Monitors RE-005/006 > 2.0 E+4 mr/hr (p.34)
- 1.
Y OR HEAT SINK (p.33)
POTENTIAL CSFST N
LOSS of
~
- 1.
BARRIER CSFST N
- 2. NON-Isolable RCS leak (including SG tube leakage) GREATER THAN the Capacity of One Charging Pump in the normal charging mode (p.34)
- 5. Unexplained level rise in any of the following: containment sump, Reactor Coolant Drain Tank (RCDT),
Waste Holdup Tank (WHT) (p.34)
- 6. Judgment: Judgment by the ED that the RCS Barrier is Lost or Potentially Lost. Consider conditions not addressed and the inability to determine the status of the RCS Barrier (p. 34)
FIGURE 2 - REACTOR COOLANT SYSTEM (RCS) INTEGRITY (Modes 1, 2, 3 and 4 only)
Pnnted February 25, 2010 at 13.39
Approved By J.D. Williams Date Approved 05/28/2009 EMERGENCY CLASSIFICATION AND IMPLEMENTING INSTRUCTIONS REFERENCE USE
- 2. Rapid Unexplained Containment Pressure Decrease Following Initial Pressure Increase (p.35)
- 2. Intersystem LOCA indicated by Containment Pressure or Sump Level Response Not Consistent With a Loss of Primary or Sec;ondary Co()lant (p. 35
- 4. Ruptured SG is also Faulted Outside of Containment (p. 36)
- 4. Primary-to-Secondary Leakage> 10 gpm AND a Non-Isolable Steam Release of Contaminated Secondary Coolant is Occurring to the Environment (p. 36)
- 5. Containment Isolation Valve(s) or Damper(s) are NOT Closed Resulting in a Direct Pathway to the Environment After Containment Isolation is Required (p. 37)
- 7. Pathway to the environment exists based on VALID RE-2562C, RE-12444C, OR RE-12442C Alarms. (p.37
- 1. CONTAINMENT CSFST RED y
N (p.35)
four CTMT fan coolers AND one train of CTMT spray (p.35
<62% (p.37
- 2. Containment Hydrogen Concentration> 6% (p.35)
- 2. Containment Pressure> 43 psig (p.35)
- 6. Containment Radiation Monitors RE-005/006 > 2.4 E+8 mr/hr (p.37)
- 8. Judgment: Judgment by the ED that the CNTMT Barrier is Lost or Potentially Lost. Consider conditions not addressed and inability to determine the status of the CTMT Barrier (p. 37)
FIGURE 3 - CONTAINMENT INTEGRITY (Modes 1, 2, 3 and 4 only)
Printed February 25,2010 at 13:39 t-'ror:p.nllrp. Number Rev 32 Page Number 12 of 108 LOSS of CNTMT BARRIER OR POTENTIAL LOSS of CNTMT BARRIER
- Approved By
'~<'}:
VogfleElectric Generating Plant,A
"/ Procedure Number Rev J.D. Williams
~; ~" 91001-C 32 Date Approved EMERGENCY CLASSIFICATION AND IMPLEMENTING INSTRUCTIONS Page Number 05/28/2009 12 of 1018 I
REFERENCE USE I
- 2. Rapid Unexplained Containment Pressure Decrease Following Initial Pressure Increase (p.35)
OR LOSS
- 2. Intersystem LOCA indicated by Containment Pressure or Sump Level Response Not Consistent OR of With a Loss of Primary or Secondary Coolant (p. 35) r+
- 4. Ruptured SG is also Faulted Outside of Containment (p. 36)
OR CNTMT
- 4. Primary-to-Secondary Leakage> 10 gpm AND a Non-Isolable Steam Release of Contaminated OR BARRIER Secondary Coolant is Occurring to the Environment (p. 36)
- 5. Containment Isolation Valve(s) or Damper(s) are NOT Closed Resulting in a Direct Pathway to the OR Environment After Containment Isolation is Required (p. 37)
- 7. Pathway to the environment exists based on VALID RE-2562C, RE-12444C, OR RE-12442C Alarms. (p.37)
- 1. CONTAINMENT y
(p. 35)
POTENTIAL OR LOSS of
CNTMT
~
four CTMT fan coolers AND one train of CTMT spray (p.35)
BARRIER
> 15 minutes AND RVLS FULL RANGE LEVEL OR
<62% (p.37)
- 2. Containment Hydrogen Concentration> 6% (p.35)
- 2. Containment Pressure> 43 psig (p.35)
- 6. Containment Radiation Monitors RE-005/006 > 2.4 E+8 mr/hr (p.37)
- 8. Judgment: Judgment by the ED that the CNTMT Barrier is Lost or Potentially Lost. Consider conditions not addressed and inability to determine the status of the CTMT Barrier (p. 37)
FIGURE 3 - CONTAINMENT INTEGRITY (Modes 1, 2, 3 and 4 only)
Printed February 25, 2010 at 13:39
Number Rev 22 Date Approved FR-P.1 RESPONSE TO IMMINENT Page Number 7/11/08 PRESSURIZED THERMAL SHOCK CONDITION 17 of 34 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE The Upper Head region of the vessel may void during RCS depressurization if RCPs are NOT running. This will result in a rapidly rising PRZR level.
CAUTION RCS depressurization may result in RCP seal ~P lowering to less than 200 psid. Shutdown of Reps is required in this case.
- 23.
Depressurize ReS to lower RCS subcooling:
- a. Check if ANY of the following
- a. Go to Step 23.c.
conditions are satisfied:
ReS subcooling -
24°F to 34°F
[38°F to 48°F ADVERSE].
-OR-PRZR level-GREATER THAN 75%
[52% ADVERSE].
-OR-Res pressure - LESS THAN 125 PSIG.
- b. Go to Step 27.
o Step 23 continued on next page
(
(
Approved By J. B. Stanley Date Approved 7/11/08 FR-P.1 RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION Page Number 17 of 34 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE The Upper Head region of the vessel may void during RCS depressurization if RCPs are NOT running. This will result in a rapidly rising PRZR level.
CAUTION RCS depressurization may result in RCP seal ~P lowering to less than 200 psid. Shutdown of RCPs is required in this case.
- 23.
Depressurize RCS to lower RCS subcooling:
- a. Check if ANY of the following
- a. Go to Step 23.c.
conditions are satisfied:
RCS subcooling -
24°F to 34°F
[38°F to 48°F ADVERSE].
-OR-PRZR level-GREATER THAN 75%
[52% ADVERSE].
-OR-RCS pressure - LESS THAN 125 PSIG.
- b. Go to Step 27.
o Step 23 continued on next page Printed February 25, 2010 at 13.39
3.3 INSTRUMENTATION Cbntainmenl Ventilation Isolation Instrumentation 3.3.6 3.3.6 Containment Ventilation Isolation Instrumentation LCO 3.3.6 The Containment Ventilation Isolation instrumentation for each Function in Table 3.3.6-1 shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.6-1.
ACTIONS
NOTE--------------------------------------------------------
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A.
Only one radiation monitoring channel OPERABLE.
A.1 Restore at least two channels 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to OPERABLE status.
Vogtle Units 1 and 2 3.3.6-1 (continued)
Amendment No. 105 (Unit 1)
Amendment No. 83 (Unit 2)
(
3.3 INSTRUMENTATION Containment Ventnation Isolation Instrumentation 3.3.6 3.3.6 Containment Ventilation Isolation Instrumentation LCO 3.3.6 The Containment Ventilation Isolation instrumentation for each Function in Table 3.3.6-1 shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.6-1.
ACTIONS
N OTE --------------------------------------------------------
Separate Condition entry is allowed for each Function.
CONDITION A.
Only one radiation monitoring channel OPERABLE.
Vogtle Units 1 and 2 REQUIRED ACTION A.1 Restore at least two channels to OPERABLE status.
COMPLETION TIME 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
( continued) 3.3.6-1 Amendment No. 105 (Unit 1)
Amendment No. 83 (Unit 2)
(
ACTIONS (continued)
CONDITION B.
NOTE--------------
B.1 Only applicable in MODE 1, 2, 3, or4.
One or more Functions with one or more manual or automatic actuation channels inoperable.
No radiation monitoring channels OPERABLE.
Required Action and associated Completion Time of Condition A not met.
Vogtle Units 1 and 2 Containment Ventilation Isolation Instrumentation 3.3.6 REQUIRED ACTION Enter applicable Conditions and Required Actions of LCO 3.6.3, "Containment Isolation Valves," for containment purge supply and exhaust isolation valves made inoperable by isolation instrumentation.
COMPLETION TIME Immediately
( continued) 3.3.6-2 Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
(
ACTIONS (continued)
CONDITION B.
NOTE--------------
B.1 Only applicable in MODE 1, 2, 3, or 4.
One or more Functions with one or more manual or automatic actuation channels inoperable.
No radiation monitoring channels OPERABLE.
OR Required Action and associated Completion Time of Condition A not met.
Vogtle Units 1 and 2 Containment Ventilation Isolation Instrumentation 3.3.6 REQUIRED ACTION COMPLETION TIME Enter applicable Immediately Conditions and Required Actions of LCO 3.6.3, "Containment Isolation Valves," for containment purge supply and exhaust isolation valves made inoperable by isolation instrumentation.
( continued) 3.3.6-2 Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
(
. ACTIONS (continued)
CONDITION C.
NOTE--------------
C.1 Only applicable during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment.
OR No radiation monitoring C.2 channels OPERABLE.
Required Action and associated Completion Time for Condition A not met.
Vogtle Units 1 and 2 Containment Ventilation tsotation*1 nstrumentatron 3.3.6 REQUIRED ACTION Place and maintain containment purge and exhaust valves in closed position.
COMPLETION TIME Immediately Enter applicable Immediately Conditions and Required Actions of LCO 3.9.4, "Containment Penetrations," for containment purge supply and exhaust isolation penetrations not in required status.
3.3.6-3 Amendment No. 105 (Unit 1)
Amendment No.
83 (Unit 2)
(
(
ACTIONS (continued)
CONDITION C.
NOTE--------------
C.1 Only applicable during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment.
No radiation monitoring channels OPERABLE.
Required Action and associated Completion Time for Condition A not met.
Vogtle Units 1 and 2 C.2 Containment Ventilation Isolation Instrumentation 3.3.6 REQUIRED ACTION Place and maintain containment purge and exhaust valves in closed position.
Enter applicable Conditions and Required Actions of LCO 3.9.4, "Containment Penetrations," for containment purge supply and exhaust isolation penetrations not in required status.
COMPLETION TIME Immediately Immediately 3.3.6-3 Amendment No. 105 (Unit 1)
Amendment No.
83 (Unit 2)
.. Containment Ventilation l$OratiOri fnstrumentation 3.3.6 SURVEILLANCE REQUIREMENTS
NOTE---------------------------------------------------------
Refer to Table 3.3.6-1 to determine which SRs apply for each Containment Purge and Exhaust Isolation Function.
SURVEILLANCE FREQUENCY SR 3.3.6.1 Perform CHANNEL CHECK.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.2 Perform ACTUATION LOGIC TEST.
92 days on a STAGGERED TEST BASIS SR 3.3.6.3 Perform MASTER RELAY TEST.
92 days on a STAGGERED TEST BASIS SR 3.3.6.4 Perform COT.
92 days SR 3.3.6.5 Perform SLAVE RELAY TEST.
18 months SR 3.3.6.6
NOT E------------------------------------
Verification of setpoint not required.
Perform T ADOT.
18 months SR 3.3.6.7 Perform CHANNEL CALIBRATION.
18 months SR 3.3.6.8 Verify RESPONSE TIMES are within limits.
18 months on a STAGGERED TEST BASIS Vogtle Units 1 and 2 3.3.6-4 Amendment No. 145 (Unit 1)
Amendment No. 125 (Unit 2)
(
(
Containment Ventilation IsctatiOri Instrumentation 3.3.6 SURVEILLANCE REQUIREMENTS
NOT E ---------------------------------------------------------
Refer to Table 3.3.6-1 to determine which SRs apply for each Containment Purge and Exhaust Isolation Function.
SURVEILLANCE FREQUENCY SR 3.3.6.1 Perform CHANNEL CHECK.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.2 Perform ACTUATION LOGIC TEST.
92 days on a STAGGERED TEST BASIS SR 3.3.6.3 Perform MASTER RELAY TEST.
92 days on a STAGGERED TEST BASIS SR 3.3.6.4 Perform COT.
92 days SR 3.3.6.5 Perform SLAVE RELAY TEST.
18 months SR 3.3.6.6
NOT E ------------------------------------
Verification of setpoint not required.
Perform TADOT.
18 months SR 3.3.6.7 Perform CHANNEL CALIBRATION.
18 months SR 3.3.6.8 Verify RESPONSE TIMES are within limits.
18 months on a STAGGERED TEST BASIS Vogtle Units 1 and 2 3.3.6-4 Amendment No. 145 (Unit 1)
Amendment No. 125 (Unit 2)
- 1.
- 2.
- 3.
- 4.
FUNCTION Manual Initiation Automatic Actuation Logic and Actuation Relays Containment Radiation
- a.
Gaseous (RE-2565C)
- b.
Particulate (RE-2565A)
- c.
Iodine (RE-2565B)
- d.
Area Low Range (RE-0002, RE-0003)
Safety Injection(d)
Containment Ventilation-Isolatron Instrumentation 3.3.6 Table 3.3.6-1 (page 1 of 1)
Containment Ventilation Isolation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 1,2,3,4 1,2,3,4 1,2,3,4,6(c) 1,2,3,4 REQUIRED CHANNELS 2
2 SURVEILLANCE REQUIREMENTS SR 3.3.6.6 SR 3.3.6.2 SR 3.3.6.3 SR 3.3.6.5 SR 3.3.6.1 SR 3.3.6.4 SR 3.3.6.7 SR 3.3.6.8 TRIP SETPOINT NA NA (b)
(b)
(b)
~ 15 mr/h(c)
~ 50x background(d)
Refer to LCO 3.3.2, "ESFAS Instrumentation,"Function 1, for all initiation functions and requirements.
(a)
Containment ventilation radiation (RE-2565) is treated as one channel and is considered OPERABLE if the particulate (RE-2565A) and iodine monitors (RE-2565B) are OPERABLE or the noble gas monitor (RE-2565C) is OPERABLE.
(b)
Setpoints will not exceed the limits of Specifications 5.5.4.h and 5.5.4.i of the Radioactive Effluent Controls Program.
(c)
During CORE ALTERATIONS and movement of irradiated fuel assemblies within containment.
(d)
During MODES 1, 2, 3, and 4.
Vogtle Units 1 and 2 3.3.6-5 Amendment No.
Amendment No.
105 (Unit 1) 83 (Unit 2)
- 1.
- 2.
- 3.
(
- 4.
(
FUNCTION Manual Initiation Automatic Actuation Logic and Actuation Relays Containment Radiation
- a.
Gaseous (RE-2565C)
- b.
Particulate (RE-2565A)
- c.
Iodine (RE-2565B)
- d.
Area Low Range (RE-0002, RE-0003)
Safety Injection(d)
Containment Ventilation Isolation Instrumentation 3.3.6 Table 3.3.6-1 (page 1 of 1)
Containment Ventilation Isolation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 1,2,3,4 1,2,3,4 1,2,3,4,6(c) 1,2,3,4 REQUIRED CHANNELS 2
2 SURVEILLANCE REQUIREMENTS SR 3.3.6.6 SR 3.3.6.2 SR 3.3.6.3 SR 3.3.6.5 SR 3.3.6.1 SR 3.3.6.4 SR 3.3.6.7 SR 3.3.6.8 TRIP SETPOINT NA NA (b)
(b)
(b) s 15 mr/h(c) s 50x background(d)
Refer to LCO 3.3.2, "ESFAS Instrumentation,"Function 1, for all initiation functions and requirements.
(a)
Containment ventilation radiation (RE-2565) is treated as one channel and is considered OPERABLE if the particulate (RE-2565A) and iodine monitors (RE-2565B) are OPERABLE or the noble gas monitor (RE-2565C) is OPERABLE.
(b)
Setpoints will not exceed the limits of Specifications 5.5.4.h and 5.5.4.i of the Radioactive Effluent Controls Program.
(c)
During CORE ALTERATIONS and movement of irradiated fuel assemblies within containment.
(d)
During MODES 1, 2, 3, and 4.
Vogtle Units 1 and 2 3.3.6-5 Amendment No.
Amendment No.
105 (Unit 1) 83 (Unit 2)
(
(
\\
Res Leakage Detection Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation sh.all be OPERABLE:
- a.
The containment normal sumps level and reactor cavity sump monitors;
- b.
One containment atmosphere radioactivity monitor (gaseous or particulate); and
- c.
Either the containment air cooler condensate flow rate or a containment atmosphere gaseous or particulate radioactivity monitoring system not taken credit for in item b.
APPLI CABI LlTY:
MODES 1, 2, 3, and 4.
ACTIONS CONDITION A.
One containment sump A.1 monitor inoperable.
B.
Two or more B.1 containment sump monitors inoperable AND B.2 Vogtle Units 1 and 2 REQUIRED ACTION COMPLETION TIME Perform SR 3.4.13.1.
Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Perform SR 3.4.13.1 Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Restore at least two 30 days containment sump monitors to OPERABLE status.
3.4.15-1 (contmued)
Amendment No. 137 (Unit 1)
Amendment No. 116 (Unit 2)
(
(
RCS Leakage Detection Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:
- a.
The containment normal sumps level and reactor cavity sump monitors;
- b.
One containment atmosphere radioactivity monitor (gaseous or particulate); and
- c.
Either the containment air cooler condensate flow rate or a containment atmosphere gaseous or particulate radioactivity monitoring system not taken credit for in item b.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS CONDITION A.
One containment sump A.1 monitor inoperable.
B.
Two or more B.1 containment sump monitors inoperable AND B.2 Vogtle Units 1 and 2 REQUIRED ACTION COMPLETION TIME Perform SR 3.4.13.1.
Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Perform SR 3.4.13.1 Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Restore at least two 30 days containment sump monitors to OPERABLE status.
3.4.15-1 (continued)
Amendment No. 137 (Unit 1)
Amendment No. 116 (Unit 2)
(
ACTIONS ( continued)
CONDITION C.
Required containment atmosphere radioactivity monitor(s) inoperable.
D.
Required containment air cooler condensate flow rate monitor inoperable.
Vogtle Units 1 and 2 Res Leakage Detection Instrumentation 3.4.15 REQUIRED ACTION COMPLETION TIME C.1.1 OR C.1.2 AND C.2.1 OR C.2.2 D.1 OR D.2 Analyze grab samples of Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the containment atmosphere.
Perform SR 3.4.13.1.
Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Restore required 30 days containment atmosphere radioactivity monitor(s) to OPERABLE status.
Verify containment air 30 days cooler condensate flow rate monitor is OPERABLE.
Perform SR 3.4.15.2.
Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Perform SR 3.4.13.1.
Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (continued) 3.4.15-2 Amendment No. 137 (Unit 1)
Amendment No. 116 (Unit 2)
ACTIONS (continued)
CONDITION C.
Required containment atmosphere radioactivity monitor(s) inoperable.
(
D.
Required containment air cooler condensate flow rate monitor inoperable.
(
Vogtle Units 1 and 2 RCS Leakage Detection Instrumentation 3.4.15 REQUIRED ACTION COMPLETION TIME C.1.1 OR C.1.2 AND C.2.1 OR C.2.2 D.1 OR D.2 Analyze grab samples of Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the containment atmosphere.
Perform SR 3.4.13.1.
Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Restore required 30 days containment atmosphere radioactivity monitor(s) to OPERABLE status.
Verify containment air 30 days cooler condensate flow rate monitor is OPERABLE.
Perform SR 3.4.15.2.
Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Perform SR 3.4.13.1.
Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (continued) 3.4.15-2 Amendment No. 137 (Unit 1)
Amendment No. 116 (Unit 2)
(
ACTIONS (continued)
CONDITION E.
Required containment E.1 atmosphere radioactivity monitor inoperable.
AND OR Required containment air cooler condensate E.2 flow rate monitor inoperable.
F.
Required Action and F.1 associated Completion Time not met.
AND F.2 G.
All required leakage G.1 detection systems inoperable.
SURVEILLANCE REQUIREMENTS Res Leakage Detection Instrumentation 3.4.15 REQUIRED ACTION COMPLETION TIME Restore required 30 days containment atmosphere radioactivity monitor to OPERABLE status.
Restore required 30 days containment air cooler condensate flow rate monitor to OPERABLE status.
Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Enter LCO 3.0.3.
Immediately SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of containment 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> normal sumps level and reactor cavity sump level monitors.
( continued)
Vogtle Units 1 and 2 3.4.15-3 Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
(
(
ACTIONS (continued)
CONDITION E.
Required containment E.1 atmosphere radioactivity monitor inoperable.
AND OR Required containment air cooler condensate E.2 flow rate monitor inoperable.
F.
Required Action and F.1 associated Completion Time not met.
AND F.2 G.
A" required leakage G.1 detection systems inoperable.
SURVEILLANCE REQUIREMENTS RCS Leakage Detection Instrumentation 3.4.15 REQUIRED ACTION COMPLETION TIME Restore required 30 days containment atmosphere radioactivity monitor to OPERABLE status.
Restore required 30 days containment air cooler condensate flow rate monitor to OPERABLE status.
Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Enter LCO 3.0.3.
Immediately SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of containment normal sumps level and reactor cavity sump level monitors.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
( continued)
Vogtle Units 1 and 2 3.4.15-3 Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
RCS Leakage Detection fnstrumenfation.
3.4.15 SURVEILLANCE REQUIREMENTS (continued)
SR 3.4.15.2 SR 3.4.15.3 SR 3.4.15.4 SR 304.15.5 SR 3.4.15.6 SURVEILLANCE Perform CHANNEL CHECK of the required containment atmosphere radioactivity monitor.
Perform COT of the required containment atmosphere radioactivity monitor.
Perform CHANNEL CALIBRATION of the containment sump monitors.
Perform CHANNEL CALIBRATION of the required containment atmosphere radioactivity monitor.
Perform CHANNEL CALIBRATION of the required containment air cooler condensate flow rate monitor.
Vogtle Units 1 and 2 3.4.15-4 FREQUENCY 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 92 days 18 months 18 months 18 months Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
(
(
Res Leakage Detection Instrumentation 3.4.15 SURVEILLANCE REQUIREMENTS (continued)
SR 3.4.15.2 SR 3.4.15.3 SR 3.4.15.4 SR 3.4.15.5 SR 3.4.15.6 SURVEILLANCE Perform CHANNEL CHECK of the required containment atmosphere radioactivity monitor.
Perform COT of the required containment atmosphere radioactivity monitor.
Perform CHANNEL CALIBRATION of the containment sump monitors.
Perform CHANNEL CALIBRATION of the required containment atmosphere radioactivity monitor.
Perform CHANNEL CALIBRATION of the required containment air cooler condensate flow rate monitor.
Vogtle Units 1 and 2 3.4.15-4 FREQUENCY 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 92 days 18 months 18 months 18 months Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
3.6 CONTAINMENT SYSTEMS 3.6.3 Containment Isolation Valves Containment Isolation Valves 3.6.3 LCO 3.6.3 Each containment isolation valve shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS
NOTES-----------------------------------------------------------
- 1.
Penetration flow path(s) (except for 24 inch purge valves) may be unisolated intermittently under administrative controls.
- 2.
Separate Condition entry is allowed for each penetration flow path.
- 3.
Enter applicable Conditions and Required Actions for systems made inoperable by containment isolation valves.
- 4.
Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when isolation valve leakage results in exceeding the overall containment leakage rate acceptance criteria.
CONDITION A.
One or more penetration A.1 flow paths with one containment isolation valve inoperable except for purge valve leakage not within limit.
Vogtle Units 1 and 2 REQUIRED ACTION COMPLETION TIME Isolate the affected 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.
3.6.3-1
( continued)
Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
(
(
3.6 CONTAINMENT SYSTEMS 3.6.3 Containment Isolation Valves Containment Isolation Valves 3.6.3 LCO 3.6.3 Each containment isolation valve shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS
NOTES-----------------------------------------------------------
- 1.
Penetration flow path(s) (except for 24 inch purge valves) may be unisolated intermittently under administrative controls.
- 2.
Separate Condition entry is allowed for each penetration flow path.
- 3.
Enter applicable Conditions and Required Actions for systems made inoperable by containment isolation valves.
- 4.
Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when isolation valve leakage results in exceeding the overall containment leakage rate acceptance criteria.
CONDITION A.
One or more penetration A.1 flow paths with one containment isolation valve inoperable except for purge valve leakage not within limit.
Vogtle Units 1 and 2 REQUIRED ACTION COMPLETION TIME Isolate the affected 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.
3.6.3-1
( continued)
Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
ACTIONS
. CONDITION A.
( continued)
A.2 B.
One or more penetration B.1 flow paths with two containment isolation valves inoperable except for purge valve leakage not within limit.
Vogtle Units 1 and 2 Containment Isoration Valves 3.6.3 REQUIRED ACTION COMPLETION TIME
NOT E ---------------
Isolation devices in high radiation areas may be verified by use of administrative means.
Verify the affected Once per 31 days for penetration flow path is isolation devices isolated.
outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment Isolate the affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
( continued) 3.6.3-2 Amendment No. 96 (Unit 1)
Amendment NO.7 4 (Unit 2)
ACTIONS
- CONDITION A.
( continued)
A.2
(
B.
One or more penetration B.1 flow paths with two containment isolation valves inoperable except for purge valve leakage not within limit.
(
Vogtle Units 1 and 2 Containment Isoration Valves 3.6.3 REQUIRED ACTION COMPLETION TIME
N OT E ---------------
Isolation devices in high radiation areas may be verified by use of administrative means.
Verify the affected Once per 31 days for penetration flow path is isolation devices isolated.
outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment Isolate the affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
( continued) 3.6.3-2 Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
(
ACTIONS (continued)
CONDITION REQUIRED ACTION Containment Isolation Valves 3.6.3 COMPLETION TIME C.
One or more penetration C.1 flow paths with one or Isolate the affected 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> penetration flow path by more containment purge valves not within purge valve leakage limits.
Vogtle Units 1 and 2 use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
AND C.2
N 0 T E -------------
Isolation devices in high radiation areas may be verified by use of administrative means.
Verify the affected penetration flow path is isolated.
Once per 31 days for isolation devices outside containment Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment
( continued) 3.6.3-3 Amendment No. 96 (Unit 1)
Amendment NO.7 4 (Unit 2)
(
ACTIONS (continued)
CONDITION REQUIRED ACTION Containment Isolation Valves 3.6.3 COMPLETION TIME C.
One or more penetration C.1 flow paths with one or Isolate the affected 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> penetration flow path by more containment purge valves not within purge valve leakage limits.
Vogtle Units 1 and 2 use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
AND C.2
NOT E -------------
Isolation devices in high radiation areas may be verified by use of administrative means.
Verify the affected penetration flow path is isolated.
Once per 31 days for isolation devices outside containment Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment (continued) 3.6.3-3 Amendment No. 96 (Unit 1)
Amendment NO.7 4 (Unit 2)
Containment Isolation Valves 3.6.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D.
Required Action and associated Completion Time not met.
0.1 AND 0.2 SURVEILLANCE REQUIREMENTS Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE FREQUENCY SR 3.6.3.1 SR 3.6.3.2 SR 3.6.3.3 Verify each 24 inch purge valve is sealed closed, 31 days except for one purge valve in a penetration flow path while in Condition C of this LCO.
Verify each 14 inch purge valve is closed, except 31 days when the associated penetration(s) is (are) permitted to be open for purge or venting operations and purge system surveillance and maintenance testing under administrative control.
NOTE----------------------------
Valves and blind flanges in high radiation areas may be verified by use of administrative controls.
Verify each containment isolation manual valve 31 days and blind flange that is located outside containment and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.
( continued)
Vogtle Units 1 and 2 3.6.3-4 Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
(
(
Containment Isolation Valves 3.6.3 ACTIONS icontinued)
CONDITION D.
Required Action and associated Completion Time not met.
0.1 AND 0.2 SURVEILLANCE REQUIREMENTS REQUIRED ACTION Be in MODE 3.
Be in MODE 5.
SURVEILLANCE SR 3.6.3.1 Verify each 24 inch purge valve is sealed closed, except for one purge valve in a penetration flow path while in Condition C of this LCO.
COMPLETION TIME 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours FREQUENCY 31 days SR 3.6.3.2 Verify each 14 inch purge valve is closed, except 31 days SR 3.6.3.3 when the associated penetration(s) is (are) permitted to be open for purge or venting operations and purge system surveillance and maintenance testing under administrative control.
NOT E ----------------------------
Valves and blind flanges in high radiation areas may be verified by use of administrative controls.
Verify each containment isolation manual valve and blind flange that is located outside containment and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.
31 days
( continued)
Vogtle Units 1 and 2 3.6.3-4 Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
Containment Isolation Varves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)
SR 3.6.3.4 SR 3.6.3.5 SR 3.6.3.6 SR 3.6.3.7 SURVEILLANCE
NOTES----------------------------
- 1.
Valves and blind flanges in high radiation areas may be verified by use of
. administrative means.
- 2.
The fuel transfer tube blind flange is only required to be verified closed once after refueling prior to entering MODE 4 from MODE 5.
Verify each containment isolation manual valve and blind flange that is located inside containment and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.
FREQUENCY Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days Verify the isolation time of each power operated In accordance and each automatic containment isolation valve is. with the Inservice within limits.
Testing Program Perform leakage rate testing for containment 18 months purge valves with resilient seals.
Verify each automatic containment isolation valve 18 months that is not locked, sealed, or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.
Vogtle Units 1 and 2 3.6.3-5 Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
(
(
Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)
SR 3.6.3.4 SR 3.6.3.5 SR 3.6.3.6 SR 3.6.3.7 SU RVEI LLANCE
NOT E S----------------------------
- 1.
Valves and blind flanges in high radiation areas may be verified by use of administrative means.
- 2.
The fuel transfer tube blind flange is only required to be verified closed once after refueling prior to entering MODE 4 from MODE 5.
Verify each containment isolation manual valve and blind flange that is located inside containment and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.
Verify the isolation time of each power operated and each automatic containment isolation valve is within limits.
FREQUENCY Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days I n accordance with the Inservice Testing Program Perform leakage rate testing for containment 18 months purge valves with resilient seals.
Verify each automatic containment isolation valve 18 months that is not locked, sealed, or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.
Vogtle Units 1 and 2 3.6.3-5 Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)