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 Exam1. 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 GroupAlignment Limits, reactor power must be reduced within (1) hour(s).If NO operator actions are taken the runback signal will cause feedwater flow tolower (2)

.(1) 2(2) but the reactor will NOT trip(1) 6(2) but the reactor will NOT trip(1) 2(2) and the reactor will trip(1) 6(2) and the reactor will trip A.B.C.D. 1 NRC 2011 SRO Exam2. 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?Verify plant conditions are approaching stability and complete AP-545,Plant Runback.Enter AP-504, Integrated Control System Failure, take manual controlof FW and RX stations and lower power to 50%.Enter EOP-02, Vital System Status Verification, and depress themanual Rx trip push button and verify control rod groups 1 through 7are fully inserted.

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

If breaker 3305 does not open then open additional breakers as required to de-energize the CRDs. Enter EOP-02, Vital System Status Verification, and depress themanual Rx trip push button and verify control rod groups 1 through 7are fully inserted.

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

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

A.B.C.D. 2 NRC 2011 SRO Exam3. The following plant conditions exist:- The plant is at 100% power.- At 0900 DCP-1A and DCP-1B are declared inoperable due to a commoncause failure.- At 2200 RCS temperature is 320° F. At no later than (1) a(n) (2) must be declared IAW EM-202, Duties ofthe Emergency Coordinator.(1) 2215(2) Unusual Event(1) 2215(2) Site Area Emergency(1) 2230(2) Unusual Event(1) 2230(2) Site Area Emergency A.B.C.D. 3 NRC 2011 SRO Exam4. 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:NOT require entry into TS 3.4.8, Pressurizer. Normal Pressurizerheater capability still exists.NOT require entry into TS 3.4.8, Pressurizer. Emergency Pressurizerheater capability still exists.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 />.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 />.

A.B.C.D. 4 NRC 2011 SRO Exam5. 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 formaintaining core cooling for these plant conditions? As downcomer voiding rises, excore NI counts will start to (1)

.Core cooling will be maintained IAW (2)

. (1) rise (2) EM-225E, Guideline for Long Term Cooling(1) rise (2) EM-225F, Long Term Emergency Feedwater Management(1) lower (2) EM-225E, Guideline for Long Term Cooling(1) lower (2) EM-225F, Long Term Emergency Feedwater Management A.B.C.D. 5 NRC 2011 SRO Exam6. 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 bythe RO and the alarm does NOT clear.During the performance of the SP, AHF-1A was running in (1) speed. Thefan will be shut down AND the PPO will be directed to manually isolate coolingwater IAW (2)

.(1) low(2) OP-417A, Industrial Cooling System(1) high(2) OP-417A, Industrial Cooling System(1) low(2) OP-417, Containment Operating Procedure(1) high(2) OP-417, Containment Operating Procedure A.B.C.D. 6 NRC 2011 SRO Exam7. 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 sprayrequirements for these conditions?IAW EOP-08A, LOCA Cooldown, building spray may be secured.IAW EOP-03, Inadequate Subcooling Margin, building spray may be secured.IAW EOP-08A, LOCA Cooldown, building spray cannot be secured.IAW EOP-03, Inadequate Subcooling Margin, building spray cannot be secured.A.B.C.D. 7 NRC 2011 SRO Exam8. 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, RadiationInstrumentation 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 RBmini-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)

.(1) RB Purge Exhaust Fans (AHF-7A & 7B) tripping(2) OP-417, Containment Operating Procedure(1) RB Purge Exhaust Fans (AHF-7A & 7B) tripping(2) SP-335C, Radiation Instrumentation Functional Test of RM-A1,A2, A6, A11 and A12(1) Mini-Purge / Post Accident Hydrogen Purge Isolation Valves(LRV-70, 71, 72 & 73) closing(2) OP-417, Containment Operating Procedure(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 A.B.C.D. 8 NRC 2011 SRO Exam9. 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 followingidentifies the required OTSG steaming guidance and the basis for this requirement?Steam both OTSGs equally at the Emergency cooldown rate to preventoverfill.Preferentially steam the "A" OTSG at the Emergency cooldown rate toprevent overfill.Steam both OTSGs equally at the Normal cooldown rate to preventviolating TS cooldown rate limits.Preferentially steam the "A" OTSG at the Normal cooldown rate toprevent violating TS cooldown rate limits.

A.B.C.D. 9 NRC 2011 SRO Exam10. The following plant conditions exist:- The plant is at 75% power.- AP-607, Loss of Condenser Vacuum, has been entered.Time Condenser Vacuum Hotwell Temperature0900 28 In-Hg 110° F 0905 27 In-Hg 113° F 0910 26 In-Hg 116° F 0915 25 In-Hg 119° FWhich ONE of the following identifies the actions required to be taken IAWAP-607?Immediately trip the reactor and enter EOP-02, Vital System StatusVerification, due to condenser vacuum exceeding limits.

Immediately trip the reactor and enter EOP-02, Vital System StatusVerification, due to hotwell temperature exceeding limits.Ensure the SG/RX Demand station is in HAND and concurrentlyperform AP-510, Rapid Power Reduction, due to limits expected to be exceeded.Ensure the SG/RX Demand station is in AUTO and concurrentlyperform AP-510, Rapid Power Reduction, due to limits expected to be exceeded.A.B.C.D. 10 NRC 2011 SRO Exam11. 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)

.(1)

ICS(2) ONLY VBIT-1C must be declared inoperable(1)

ICS(2) VBIT-1A AND VBIT-1C must be declared inoperable(1)

NNI-X(2) ONLY VBIT-1C must be declared inoperable(1)

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

11 NRC 2011 SRO Exam12. 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)(1) 390° F(2) is(1) 390° F(2) is NOT(1) 405° F(2) is(1) 405° F(2) is NOT A.B.C.D. 12 NRC 2011 SRO Exam13. 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; whenis RWP-2B required to be restored to prevent a TS requiredshutdown? (1) SW-RW flow has NOT been lost. (2) 1000 on March 10 (1) SW-RW flow has NOT been lost. (2) 1000 on March 12 (1) SW-RW flow has been lost until restored by the operator.(2) 1000 on March 10(1) SW-RW flow has been lost until restored by the operator.(2) 1000 on March 12 A.B.C.D. 13 NRC 2011 SRO Exam14. The primary plant operator stops a WDT-1B ("B" Waste Gas Decay Tank) releasewhen WD-19-FQI (release flow monitor) fails low.Which ONE of the following actions must be taken to re-initiate the release?The release flow rate must be estimated at least once per four hours.The release may not be re-initiated until the flow monitor is repaired. Grab samples must be collected and analyzed at least once per fourhours.Two independent samples and an independently verified discharge valvealignment must be performed.

A.B.C.D. 14 NRC 2011 SRO Exam15. 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 StartupTransformer.- 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 KVWhich ONE of the following actions, if any, are required IAW SP-321, PowerDistribution Breaker Alignment and Power Availability Verification? (reference provided) NO action is required since all voltages are above their requiredminimum values.Recalibrate the affected ES bus voltage meters since the 230 KVSwitchyard voltage is above its required minimum value. Declare BOTH AC electrical power distribution subsystems inoperableIAW TS 3.8.9, Distribution Systems - Operating, and immediately enterLCO 3.0.3.

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

A.B.C.D. 15 NRC 2011 SRO Exam16. The plant is in Mode 1 with the ES Actuated Fast Start of the "A" EDG beingconducted IAW SP-354A, Monthly Functional Test of the Emergency DieselGenerator 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 reachrated 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 bedelivered to the core in a maximum of (2) seconds following actuation of theES signal coincident with a loss of off-site power. (1) "RUN"(2) 35(1) "RUN"(2) 20(1) "READY"(2) 35(1) "READY"(2) 20 A.B.C.D. 16 NRC 2011 SRO Exam

17. After the completion of the EOP-02, Vital System Status Verification, ImmediateActions 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 andrising with ARP-1B ("B" Air Removal pump) in service. Which ONE of the following transitions should be made, if any? (reference provided)None. Remain in EOP-02.EOP-05, Excessive Heat Transfer EOP-06, Steam Generator Tube RuptureEOP-09, Natural Circulation Cooldown A.B.C.D. 17 NRC 2011 SRO Exam18. 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 CoreCooling, to (1)

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

.(1) EOP-08A, LOCA Cooldown(2) the risk of losing additional RCS inventory has been determinedto be unacceptable if Region 3 has been previously entered due to documented PORV failures in the industry(1) EOP-08A, LOCA Cooldown(2) gas bubbles would form in the RCS loops faster than they could beremoved resulting in non-condensible gases collecting in the hot legs and blocking natural circulation(1) EOP-08B, HPI Cooldown(2) the risk of losing additional RCS inventory has been determinedto be unacceptable if Region 3 has been previously entered due to documented PORV failures in the industry(1) EOP-08B, HPI Cooldown(2) gas bubbles would form in the RCS loops faster than they could beremoved resulting in non-condensible gases collecting in the hot legs and blocking natural circulation A.B.C.D. 18 NRC 2011 SRO Exam19. During a plant startup the Supt-Environmental and Chemistry approaches theCRS about issuing a Standing Instruction concerning FW chemistry. Which ONE of the following identifies an administrative requirement for issuanceof a Standing Instruction IAW OPS-NGGC-1000, Conduct of Operations?Inform the Supt-Environmental and Chemistry that:a procedure change will be required to implement the guidance.he has the authority to prepare and approve the Standing Instruction.he must submit a request to the Operations Department and the SM ordesignee can approve the Standing Instruction.he has the authority to prepare the Standing Instruction but it cannotbe issued without concurrence of the Supt-Systems Engineering.

A.B.C.D.

19 NRC 2011 SRO Exam20. TS 3.4.11, Low Temperature Overpressure Protection (LTOP) System, requiresthe PORV to be OPERABLE with a lift setpoint

< 454 psig when in Mode 4 withRCS temperature

< 264° F.Which ONE of the following describes the basis IAW TS 3.4.11 for selecting thePORV 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 preventexceeding LTOP limits due to a(an)

(2)

.(1) in NNI Cabinet #3(2) inadvertent CFT discharge(1) on the MCB (ICS Section)(2) inadvertent CFT discharge(1) in NNI Cabinet #3(2) stuck open makeup control valve with one MUP running(1) on the MCB (ICS Section)(2) stuck open makeup control valve with one MUP running A.B.C.D. 20 NRC 2011 SRO Exam21. IAW WCP-NGGC-0300, Work Request Initiation, Screening, Prioritization andClassification, an approved work order package (1) required for Priority 1(Emergency) maintenance prior to performing work and authorization to beginthe work must be approved by the (2)

.(1) is(2) Shift Manager(1) is NOT(2) Shift Manager(1) is(2) Station Duty Manager(1) is NOT(2) Station Duty Manager A.B.C.D. 21 NRC 2011 SRO Exam22. 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 (IPTEManager)?Site Vice PresidentPlant General Manager Station Duty ManagerHuman Performance Program Manager A.B.C.D. 22 NRC 2011 SRO Exam23. The following plant conditions exist:- A General Emergency has been declared.- An operator must be dispatched to the Aux Building to protect valuableproperty.- 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 dosethe operator is allowed to receive for this entry?9 rem 10 rem 24 rem 25 rem A.B.C.D. 23 NRC 2011 SRO Exam24. 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 theevacuation.RSP Indications: 24 NRC 2011 SRO Exam

24. Based on the RSP indications given, which ONE of the following actions will bedirected by the CRS, if any? Open all CRD breakers locally to shutdown the reactor ONLY.Take manual control of EFW to feed BOTH OTSGs to the NAT CIRCsetpoint ONLY.NO actions are required for the indications given. The Rx is shutdownand BOTH OTSGs are at their required levels.Open all CRD breakers locally to shutdown the reactor AND takemanual control of EFW to feed BOTH OTSGs to the NAT CIRC setpoint.

A.B.C.D.

25 NRC 2011 SRO Exam25. 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 initiallyperformed?AP-470, Loss of Instrument AirAP-880, Fire Protection EOP-12, Station BlackoutEOP-12 ONLYEOP-12 and AP-470 ONLY EOP-12 and AP-880 ONLY EOP-12, AP-470 and AP-880 A.B.C.D.You have completed the test!

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