ML072390373
| ML072390373 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/22/2007 |
| From: | Florida Power & Light Energy Seabrook |
| To: | Caruso J NRC Region 1 |
| Sykes, Marvin D. | |
| Shared Package | |
| ML062050109 | List: |
| References | |
| 50-244/07-301 50-244/07-301 | |
| Download: ML072390373 (5) | |
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2007 Seabrook Station Written NRC Examination Ouestion Worksheet RO SRO 1
Examination Outline Cross-reference:
Level Tier #
KIA #
os I AA2.02 Question # 21 Group #
2 Importance Rating 3.9 4.1 Proposed Question:
The plant was at 100% power. The following plant conditions currently exist:
Condenser Vacuum is 22.5 in. hg and slowly decreasing Turbine load reduction is in progress.
Turbine load is 360 MWE.
Which of the following actions should be taken by the crew?
A. Immediately hip the turbine and verify all stop valves close and the generator breaker opens B. Continue the load reduction to increase condenser vacuum to > 25 in. hg.
C. Immediately trip the reactor and go to E-0, REACTOR TRIP OR SAFETY INJECTION.
D. Continue the load reduction and if vacuum remains > 22.4 in. hg. remove the turbine generator from service per OS1000.06, POWER DECREASE.
Proposed Answer:
C -
A is incorrect. The Loss of Condenser Vacuum ahnormal procedure calls for a manual reactor trip, not a manual turbine trip. Answer is plausible as the megawatt load in the stem is just above the P-9 setpoint, when the turbine could he tripped without a reactor hip.
B is incorrect. The conditions in the question stem call for a reactor hip.
C is correct. Load is 360 MWE which is the maximum load reduction allowed by ON1233.01. Procedure directs manual RX trip if vacuum continues to degrade when load had been decreased to this point.
D is incorrect. A load decrease helow 360 MWE should not he conducted. A reactor trip is required Technical Reference(s):
ON1233.01 Loss of Condenser Vacuum Proposed references to be provided to applicants during examination:
KIA
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Vacuum:
Question Source:
Direct from hank. Last used Seahrook 1996 Question Cognitive Level:
Application 10 CFR Part 55 Content:
43.5145.13 Learning Objective:
Lesson L11881, Objective L1188108 None 051AA2.02, Ability to determine and interpret the following as they apply to the Loss of Condenser Conditions requiring reactor andlor turbine trip.
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2007 Seabrook Station Written NRC Examination Question Worksheet Examination Outline Cross-reference:
2 KIA #
G 2.1.28 Question # 33 Group #
1 Importance Rating 3.2 3.3 Proposed Question:
Which of the following is a potential consequence if no RHR pumps are available during a large break LOCA?
A. DBNR decreases to less than 1.3 B. No long term cooling for decay heat removal C. No immediate injection flow is available to begin refilling the reactor vessel D. Insufficient injection flow is available to remove decay heat upon break initiation.
Proposed Answer:
B B is correct. The RHR pumps provide flow when RCS pressure decreases below their shutoff head. At least one train of RHR is assumed to be available to provide long term decay heat removal and are used when the plant switches over to recirculation.
A is incorrect but plausible. It is likely that DNBR may increase below the Technical Specification limit during a large LOCA but that is not the primary concern if no RHR pumps are available.
C is incorrect hut plausible. RCS pressure could drop below the shutoff head of the RHR pumps, however it is the function of the accumulators to refill the vessel.
D is incorrect but plausible. Heat removal would he accomplished out of the break with ECCS injection via the SI pumps and CCPs.
Technical Reference(s):
FSAR section 6.3 Proposed references to be provided to applicants during examination:
KIA
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controls.
Question Source:
Question Cognitive Level:
Memory 10 CFR Part 55 Content:
Learning Objective:
None G 2.1.28 Knowledge of the purpose and hnction ofmajor system components and Direct from bank. Last used Seahrook 1998 Company exam CFR 41.7 Lesson L80341, Objective L8034106 Lesson LX0331, Objective L8033101
2007 Seabrook Station Written NRC Examination Question Worksheet Examination Outline Cross-reference:
Level Tier #
Question # 36 Group #
1 KIA #
008AI.04 lmportance Rating 3.1 3.2 Proposed Question:
Given the following:
The plant is at 80% power.
The level in the A Primary Component Cooling Water Head Tank is increasing.
Which of the following is the potential source of leakage?
A. Letdown Heat Exchanger B. A PCCW Heat Exchanger C. Spent Fuel heat exchanger.
D. Excess Letdown Heat Exchanger.
Proposed Answer:
A -
A is correct. CVCS pressure at the letdown heat exchanger is approx. 350 psig which is higher than Train A PCCW pressure which is approx. 105 psig. The letdown heat exchanger is cooled by Train A PCCW.
B is incorrect but plausible. SW pressure through the Train A PCCW heat exchanger is approx. 49.5 psig. Train A PCCW system pressure is approx 105 psig.
C is incorrect but plausible. Train A PCCW does supply cooling to the A Spent Fuel Cooling heat exchanger, however, SF Cooling pressure is approx. 20 psig. Train A PCCW pressure is approx 105 psig.
D is incorrect but plausible. The excess letdown heat exchanger, when in service, would be at approx. 125 psig. This pressure is slightly higher than PCCW system pressure and could lead to in leakage, however, the heat exchanger is cooled from train B PCCW.
Technical Reference(s):
OS1212.01, PCCW SYSTEM MALFUNCTION Proposed references to be provided to applicants during examination:
WA
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controls including:
Question Source:
Direct from bank.
Question Cognitive Level:
Knowledge 10 CFR Part 55 Content:
Learning Objective:
None A1.04, Ability to predict andor monitor changes in parameters associated with operating the CCWS Surge Tank Level CFR 41345.5 Lesson L80361, Objective L8036112
2007 Seabrook Station Written NRC Examination Question Worksheet Examination Outline Cross-reference:
2 Question # 89 Group #
1 WA #
G 2.1.28 Knowledge ofthe purpose and function of major system components and con(ro1s.
Importance Rating 3.3 Proposed Question:
Per Technical Specification 3.8.1.1, Electrical Power Sources, AC Systems, which ofthe following describes the functional basis of the Supplemental Emergency Power System (SEPS)?
A. Supply 4.16kv power to either emergency Bus E5 or E6 in the event of a loss of offsite power with both Emergency Diesel Generators failing to start and/or load, provided there is no concurrent seismic event or an event that requires safeguards actuation.
Provide backup power to either emergency bus E5 or E6 when both Emergency Diesel Generators are out of service in MODES 1 through 4.
C. Supply 4.16kv power to either emergency Bus E5 or E6 in the event of a loss of offsite power concurrent with a seismic event or an event that requires safeguards actuation.
D. Provide backup power to both emergency busses E5 and E6 when both Emergency Diesel Generators are out of service in MODES 1-4, provided there is no concurrent seismic event or an event that requires safeguards actuation.
B.
Proposed Answer:
A -
This question addresses a specific Seabrook Station priority. 03DCR002, SEPS System. This priority is specifically described in the Tech. Spec. bases and is SRO only knowledge as required by 10CFR55.43 (2).
A is correct. The SEPS is designed to Supply 4.16kv power to Emergency Busses 5 or 6 in the event of a loss of offsite power with both Emergency Diesel Generators failing to start and/or load. Provided there is no concurrent seismic event or an event that requires safeguards actuation.
B is incorrect. Per Tech Spec. 3.8.1.1, Electrical Power Systems, AC Sources, with a single Emergency Diesel Generator out of service in Modes 1 through 4, SEPS allows the Tech. Spec. requirement to restore at least two Emergency Diesel Generators to operable status to he extended from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 14 days. The basis states The SEPS is designed to provide backup power to either emergency bus whenever one of the emergency diesel generators is out of service.
C is incorrect. SEPS is designed to provide loss-of-power to bus 5 or 6 in the event of a loss-of-offsite-power alone, not with a concurrent seismic event or an event that requires safeguards actuation.
emergency diesel generator being out of service in Modes 1-4.
Technical Reference(s):
DCR 03-002, SEPS System License Amendment Request 03-01, Inclusion of the Supplemental Emergency Power System.
Technical Specification, Bases, B314, Typs 4 D is incorrect. SEPS is not designed to provide power to both emergency busses. Additionally, it only applies to one Tech Spec. 3.8.1.1, Electrical Power Systems, AC Sources page 8-2.
Proposed references to he provided to applicants during examination:
WA
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controls.
Question Source:
New Question Cognitive Level:
Knowledge 10 CFR Part 55 Content:
None 2.1.28 Knowledge of the purpose and function of major system components and CFR: 41.7