ML112870572

Initial Exam 2011-301 Final SRO Written Exam

ML112870572
Person / Time
Site:	Crystal River
Issue date:	10/13/2011
From:	NRC/RGN-II
To:	Progress Energy Florida
References
50-302/11-301
Download: ML112870572 (28)

Text

NRC 2011 SRO Exam

1. The following plant conditions exist:

- The plant is at 100% power.

- A malfunction occurs and the Rx Demand station transferred to HAND.

- Prior to any operator action control rod 7-1 drops fully into the core.

In order to meet the REQUIRED ACTION of TS 3.1.4, Control Rod Group Alignment Limits, reactor power must be reduced within (1) hour(s).

If NO operator actions are taken the runback signal will cause feedwater flow to lower (2) .

A. (1) 2 (2) but the reactor will NOT trip B. (1) 6 (2) but the reactor will NOT trip C. (1) 2 (2) and the reactor will trip D. (1) 6 (2) and the reactor will trip 1

NRC 2011 SRO Exam

2. The following plant conditions exist:

- The plant was operating at 100% power when the "B" MFWBP tripped.

- AP-545, Plant Runback, was entered.

- During the runback the PORV opened and operated as designed.

Which ONE of the following describes the required actions to be performed?

A. Verify plant conditions are approaching stability and complete AP-545, Plant Runback.

B. Enter AP-504, Integrated Control System Failure, take manual control of FW and RX stations and lower power to 50%.

C. Enter EOP-02, Vital System Status Verification, and depress the manual Rx trip push button and verify control rod groups 1 through 7 are fully inserted.

If any control rod group has NOT fully inserted then open breakers 3305 and 3312.

If breaker 3305 does not open then open additional breakers as required to de-energize the CRDs.

D. Enter EOP-02, Vital System Status Verification, and depress the manual Rx trip push button and verify control rod groups 1 through 7 are fully inserted.

If any control rod group has NOT fully inserted then open breakers 3305 and 3312.

If breaker 3305 does not open then start emergency boration and ensure adequate primary to secondary heat transfer is maintained.

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NRC 2011 SRO Exam

3. The following plant conditions exist:

- The plant is at 100% power.

- At 0900 DCP-1A and DCP-1B are declared inoperable due to a common cause failure.

- At 2200 RCS temperature is 320° F.

At no later than (1) a(n) (2) must be declared IAW EM-202, Duties of the Emergency Coordinator.

A. (1) 2215 (2) Unusual Event B. (1) 2215 (2) Site Area Emergency C. (1) 2230 (2) Unusual Event D. (1) 2230 (2) Site Area Emergency 3

NRC 2011 SRO Exam

4. The following plant conditions exist:

- The plant is at 100% power.

- Breaker 3395, Reactor Aux Bus 3A to ES 480V Bus 3A Tie, closing mechanism has broken.

- Breaker 3305, Feed to Reactor Aux Bus 3A from 4160V Unit Bus 3A, remains operable.

Which ONE of the following describes the impact, if any, of this failure on the Pressurizer?

This failure will:

A. NOT require entry into TS 3.4.8, Pressurizer. Normal Pressurizer heater capability still exists.

B. NOT require entry into TS 3.4.8, Pressurizer. Emergency Pressurizer heater capability still exists.

C. require entry into TS 3.4.8, Pressurizer. Pressurizer heater capability must be restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

D. require entry into TS 3.4.8, Pressurizer. Pressurizer heater capability must be restored within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

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NRC 2011 SRO Exam

5. The following plant conditions exist:

- A LOCA is in progress.

- The Severe Accident Region of EOP-07, Inadequate Core Cooling, has been entered.

Which ONE of the following describes the impact that reactor vessel downcomer voiding will have on the excore NIs and the procedure that will be used for maintaining core cooling for these plant conditions?

As downcomer voiding rises, excore NI counts will start to (1) .

Core cooling will be maintained IAW (2) .

A. (1) rise (2) EM-225E, Guideline for Long Term Cooling B. (1) rise (2) EM-225F, Long Term Emergency Feedwater Management C. (1) lower (2) EM-225E, Guideline for Long Term Cooling D. (1) lower (2) EM-225F, Long Term Emergency Feedwater Management 5

NRC 2011 SRO Exam

6. The following plant conditions exist:

- The plant is in Mode 4.

- AHF-1A has just been started for the performance of SP-344C, Containment Cooling System Fan and Valve Surveillance, following motor bearing replacement.

Ten minutes later:

- Annunciator B-02-04, RB Fan A Vibration High, alarms.

- The "AHF-1A Vibra Switch Reset" pushbutton is immediately depressed by the RO and the alarm does NOT clear.

During the performance of the SP, AHF-1A was running in (1) speed. The fan will be shut down AND the PPO will be directed to manually isolate cooling water IAW (2) .

A. (1) low (2) OP-417A, Industrial Cooling System B. (1) high (2) OP-417A, Industrial Cooling System C. (1) low (2) OP-417, Containment Operating Procedure D. (1) high (2) OP-417, Containment Operating Procedure 6

NRC 2011 SRO Exam

7. The following plant conditions exist:

- A large break LOCA is in progress.

- Building Spray was actuated 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ago.

- RB pressure is 8 psig and stable.

- RB atmosphere I-131 is 17 µCi/cc.

- TSC has approved securing building spray if all other requirements are met.

Which ONE of the following choices represents the correct building spray requirements for these conditions?

A. IAW EOP-08A, LOCA Cooldown, building spray may be secured.

B. IAW EOP-03, Inadequate Subcooling Margin, building spray may be secured.

C. IAW EOP-08A, LOCA Cooldown, building spray cannot be secured.

D. IAW EOP-03, Inadequate Subcooling Margin, building spray cannot be secured.

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NRC 2011 SRO Exam

8. The following conditions exist:

- The plant is in Mode 4 with an RB mini-purge in progress.

- The functional test of RM-A1 is being conducted IAW SP-335C, Radiation Instrumentation Functional Test of RM-A1, A2, A6, A11 and A12.

- A high radiation alarm on RM-A1 is received due to the testing.

Which ONE of the following describes the impact this will have on the RB mini-purge and the procedure that will be used to restore the purge?

The RB mini-purge will be secured due to (1) and can be restored using (2) .

A. (1) RB Purge Exhaust Fans (AHF-7A & 7B) tripping (2) OP-417, Containment Operating Procedure B. (1) RB Purge Exhaust Fans (AHF-7A & 7B) tripping (2) SP-335C, Radiation Instrumentation Functional Test of RM-A1, A2, A6, A11 and A12 C. (1) Mini-Purge / Post Accident Hydrogen Purge Isolation Valves (LRV-70, 71, 72 & 73) closing (2) OP-417, Containment Operating Procedure D. (1) Mini-Purge / Post Accident Hydrogen Purge Isolation Valves (LRV-70, 71, 72 & 73) closing (2) SP-335C, Radiation Instrumentation Functional Test of RM-A1, A2, A6, A11 and A12 8

NRC 2011 SRO Exam

9. The following plant conditions exist:

- A tube rupture has occurred in the "A" OTSG.

- The reactor has been manually tripped.

- RCS Tave is 520° F with a cooldown in progress at a rate of 50° F/1/2 hr.

- "A" OTSG level is at 80% and rising due to the tube rupture.

- "B" OTSG level is at LLL.

IAW EOP-06, Steam Generator Tube Rupture, which ONE of the following identifies the required OTSG steaming guidance and the basis for this requirement?

A. Steam both OTSGs equally at the Emergency cooldown rate to prevent overfill.

B. Preferentially steam the "A" OTSG at the Emergency cooldown rate to prevent overfill.

C. Steam both OTSGs equally at the Normal cooldown rate to prevent violating TS cooldown rate limits.

D. Preferentially steam the "A" OTSG at the Normal cooldown rate to prevent violating TS cooldown rate limits.

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NRC 2011 SRO Exam

10. The following plant conditions exist:

- The plant is at 75% power.

- AP-607, Loss of Condenser Vacuum, has been entered.

Time Condenser Vacuum Hotwell Temperature 0900 28 In-Hg 110° F 0905 27 In-Hg 113° F 0910 26 In-Hg 116° F 0915 25 In-Hg 119° F Which ONE of the following identifies the actions required to be taken IAW AP-607?

A. Immediately trip the reactor and enter EOP-02, Vital System Status Verification, due to condenser vacuum exceeding limits.

B. Immediately trip the reactor and enter EOP-02, Vital System Status Verification, due to hotwell temperature exceeding limits.

C. Ensure the SG/RX Demand station is in HAND and concurrently perform AP-510, Rapid Power Reduction, due to limits expected to be exceeded.

D. Ensure the SG/RX Demand station is in AUTO and concurrently perform AP-510, Rapid Power Reduction, due to limits expected to be exceeded.

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NRC 2011 SRO Exam

11. The following plant conditions exist:

- The plant was in Mode 1.

- A loss of the DC input to the "C" inverter (VBIT-1C) has occurred.

- Subsequently a Loss of Offsite Power (LOOP) occurs and the "A" EDG failed to start.

The (1) Power Failure alarm is annunciated. With respect to the VBITs (Vital Bus Inverters) (2) .

A. (1) ICS (2) ONLY VBIT-1C must be declared inoperable B. (1) ICS (2) VBIT-1A AND VBIT-1C must be declared inoperable C. (1) NNI-X (2) ONLY VBIT-1C must be declared inoperable D. (1) NNI-X (2) VBIT-1A AND VBIT-1C must be declared inoperable 11

NRC 2011 SRO Exam

12. The plant was operating at 75% power when the "A" MFWP tripped.

Following the runback, FW temperature will stabilize at (1) .

Selection of the EFIC MFW isolation pump trip switches to "BOTH" (2) required to maintain operability of the Main Feedwater Isolation Valves (MFIVs).

(reference provided)

A. (1) 390° F (2) is B. (1) 390° F (2) is NOT C. (1) 405° F (2) is D. (1) 405° F (2) is NOT 12

NRC 2011 SRO Exam

13. The following plant conditions exist at 1000 on March 9:

- Mode 1 with the Startup Transformer supplying the Unit buses.

- The "B" EDG is out-of-service for maintenance.

- Backup ES Transformer (BEST) is lost due to all sudden pressure relays actuating.

Which ONE of the following:

(1) describes the status of SW-RW flow, and (2) with respect to TS 3.7.9, Nuclear Services Seawater System; when is RWP-2B required to be restored to prevent a TS required shutdown?

A. (1) SW-RW flow has NOT been lost.

(2) 1000 on March 10 B. (1) SW-RW flow has NOT been lost.

(2) 1000 on March 12 C. (1) SW-RW flow has been lost until restored by the operator.

(2) 1000 on March 10 D. (1) SW-RW flow has been lost until restored by the operator.

(2) 1000 on March 12 13

NRC 2011 SRO Exam

14. The primary plant operator stops a WDT-1B ("B" Waste Gas Decay Tank) release when WD-19-FQI (release flow monitor) fails low.

Which ONE of the following actions must be taken to re-initiate the release?

A. The release flow rate must be estimated at least once per four hours.

B. The release may not be re-initiated until the flow monitor is repaired.

C. Grab samples must be collected and analyzed at least once per four hours.

D. Two independent samples and an independently verified discharge valve alignment must be performed.

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NRC 2011 SRO Exam

15. The following conditions exist:

- CR Unit 3 is operating at 100% power.

- CR Units 1 & 2 are shutdown due to a recent fire in Unit 1's Startup Transformer.

- CR Units 4 & 5 are operating at 100% power.

Following a grid disturbance the following voltages exist:

- 230 KV Switchyard - 231 KV (verified by dispatcher)

- "A" ES 4160V bus - 4.18 KV

- "B" ES 4160V bus - 4.15 KV Which ONE of the following actions, if any, are required IAW SP-321, Power Distribution Breaker Alignment and Power Availability Verification?

(reference provided)

A. NO action is required since all voltages are above their required minimum values.

B. Recalibrate the affected ES bus voltage meters since the 230 KV Switchyard voltage is above its required minimum value.

C. Declare BOTH AC electrical power distribution subsystems inoperable IAW TS 3.8.9, Distribution Systems - Operating, and immediately enter LCO 3.0.3.

D. Declare ONLY ONE AC electrical power distribution subsystem inoperable IAW TS 3.8.9, Distribution Systems - Operating, and restore to operable status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

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NRC 2011 SRO Exam

16. The plant is in Mode 1 with the ES Actuated Fast Start of the "A" EDG being conducted IAW SP-354A, Monthly Functional Test of the Emergency Diesel Generator EDG-1A.

When the RO simulates the ES signal, by selecting the ES A "HPI AUTO TEST -

GRP 2" switch to the "TEST" position, the "A" EDG is required to start and reach rated voltage and frequency within 9.5 seconds as indicated by illumination of the (1) light on the MCB.

Per TS Bases for the large break LOCA analysis this ensures LPI flow will be delivered to the core in a maximum of (2) seconds following actuation of the ES signal coincident with a loss of off-site power.

A. (1) "RUN" (2) 35 B. (1) "RUN" (2) 20 C. (1) "READY" (2) 35 D. (1) "READY" (2) 20 16

NRC 2011 SRO Exam

17. After the completion of the EOP-02, Vital System Status Verification, Immediate Actions the following conditions exist:

- Both 6900V unit buses have been de-energized due to a common fault.

- RCS pressure is 2000 psig and slowly lowering.

- "B" OTSG pressure is 1029 psig and stable.

- "A" OTSG pressure is 890 psig and lowering.

- Tincore has lowered from 555° F to 548° F in the last 3 minutes.

- RM-A12 (Condenser Vacuum Pump Off Gas Exhaust) is 5000 cpm and rising with ARP-1B ("B" Air Removal pump) in service.

Which ONE of the following transitions should be made, if any?

(reference provided)

A. None. Remain in EOP-02.

B. EOP-05, Excessive Heat Transfer C. EOP-06, Steam Generator Tube Rupture D. EOP-09, Natural Circulation Cooldown 17

NRC 2011 SRO Exam

18. The following plant conditions exist:

- A LOCA has occurred.

- ICC Region 3 was previously entered.

- OTSG heat transfer has now been restored and saturated RCS conditions exist.

As the Procedure Director you will transition from EOP-07, Inadequate Core Cooling, to (1) .

IAW the EOP Cross-Step document the PORV must NOT be used for depressurization once adequate SCM is restored because (2) .

A. (1) EOP-08A, LOCA Cooldown (2) the risk of losing additional RCS inventory has been determined to be unacceptable if Region 3 has been previously entered due to documented PORV failures in the industry B. (1) EOP-08A, LOCA Cooldown (2) gas bubbles would form in the RCS loops faster than they could be removed resulting in non-condensible gases collecting in the hot legs and blocking natural circulation C. (1) EOP-08B, HPI Cooldown (2) the risk of losing additional RCS inventory has been determined to be unacceptable if Region 3 has been previously entered due to documented PORV failures in the industry D. (1) EOP-08B, HPI Cooldown (2) gas bubbles would form in the RCS loops faster than they could be removed resulting in non-condensible gases collecting in the hot legs and blocking natural circulation 18

NRC 2011 SRO Exam

19. During a plant startup the Supt-Environmental and Chemistry approaches the CRS about issuing a Standing Instruction concerning FW chemistry.

Which ONE of the following identifies an administrative requirement for issuance of a Standing Instruction IAW OPS-NGGC-1000, Conduct of Operations?

Inform the Supt-Environmental and Chemistry that:

A. a procedure change will be required to implement the guidance.

B. he has the authority to prepare and approve the Standing Instruction.

C. he must submit a request to the Operations Department and the SM or designee can approve the Standing Instruction.

D. he has the authority to prepare the Standing Instruction but it cannot be issued without concurrence of the Supt-Systems Engineering.

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NRC 2011 SRO Exam

20. TS 3.4.11, Low Temperature Overpressure Protection (LTOP) System, requires the PORV to be OPERABLE with a lift setpoint < 454 psig when in Mode 4 with RCS temperature < 264° F.

Which ONE of the following describes the basis IAW TS 3.4.11 for selecting the PORV to its "LOW" setpoint and identifies the location where this would be done?

The PORV is selected to "LOW" using a switch located (1) to prevent exceeding LTOP limits due to a(an) (2) .

A. (1) in NNI Cabinet #3 (2) inadvertent CFT discharge B. (1) on the MCB (ICS Section)

(2) inadvertent CFT discharge C. (1) in NNI Cabinet #3 (2) stuck open makeup control valve with one MUP running D. (1) on the MCB (ICS Section)

(2) stuck open makeup control valve with one MUP running 20

NRC 2011 SRO Exam

21. IAW WCP-NGGC-0300, Work Request Initiation, Screening, Prioritization and Classification, an approved work order package (1) required for Priority 1 (Emergency) maintenance prior to performing work and authorization to begin the work must be approved by the (2) .

A. (1) is (2) Shift Manager B. (1) is NOT (2) Shift Manager C. (1) is (2) Station Duty Manager D. (1) is NOT (2) Station Duty Manager 21

NRC 2011 SRO Exam

22. IAW OPS-NGGC-1315, Conduct of Infrequently Performed Tests or Evolutions, which ONE of the following positions designates the individual responsible for management oversight of Infrequently Performed Tests or Evolutions (IPTE Manager)?

A. Site Vice President B. Plant General Manager C. Station Duty Manager D. Human Performance Program Manager 22

NRC 2011 SRO Exam

23. The following plant conditions exist:

- A General Emergency has been declared.

- An operator must be dispatched to the Aux Building to protect valuable property.

- The operator has received 1000 mrem TEDE this year but has received NO dose during this event.

IAW EM-202, Duties of the Emergency Coordinator, what is the maximum dose the operator is allowed to receive for this entry?

A. 9 rem B. 10 rem C. 24 rem D. 25 rem 23

NRC 2011 SRO Exam

24. The following plant conditions exist:

- AP-990, Shutdown from Outside the Control Room, is in progress and transfer to the Remote Shutdown Panel (RSP) is complete.

- ALL AP-990 required actions were completed in the MCR prior to the evacuation.

RSP Indications:

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NRC 2011 SRO Exam 24.

Based on the RSP indications given, which ONE of the following actions will be directed by the CRS, if any?

A. Open all CRD breakers locally to shutdown the reactor ONLY.

B. Take manual control of EFW to feed BOTH OTSGs to the NAT CIRC setpoint ONLY.

C. NO actions are required for the indications given. The Rx is shutdown and BOTH OTSGs are at their required levels.

D. Open all CRD breakers locally to shutdown the reactor AND take manual control of EFW to feed BOTH OTSGs to the NAT CIRC setpoint.

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NRC 2011 SRO Exam

25. The following plant conditions exist:

- The plant was operating at 100% RTP.

- IAP-4 is removed from service for overhaul.

- The "A" EDG is removed from service for maintenance.

- A weather related event has caused a loss of ALL offsite power.

- A fire in the "B" ES 4160V switchgear room prevents the "B" ES Diesel from energizing "B" ES 4160V bus.

Which ONE of the following describes the procedure(s) that is/are initially performed?

AP-470, Loss of Instrument Air AP-880, Fire Protection EOP-12, Station Blackout A. EOP-12 ONLY B. EOP-12 and AP-470 ONLY C. EOP-12 and AP-880 ONLY D. EOP-12, AP-470 and AP-880 You have completed the test!

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