Text

VC Summer 2015-301 Initial Exam Final SRO Written Exam
	ML15173A439
Person / Time
Site:	Summer
Issue date:	05/20/2015
From:	Gerald Mccoy; NRC/RGN-II
To:	; South Carolina Electric & Gas Co
References
	50-395/15-301
	Download: ML15173A439 (119)
	v • d • e

Mr. Gerald J. McCoy USNRC, Region II CR-14-O1 708 RC-1 5-0076 ENCLOSURE 2 The master examinations and answer keys

ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date:

5/20/15 Facility/Unit: V.C. Summer Unit 1 Region:

I II Ill IV Reactor Type: W CE BW EjGE D Start Time:

Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to complete the combined examination, and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 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.

Applicants Signature Res u Its RO/SRO-Only/Total Examination Values I

/

Points Applicants Scores I

/

Points Applicants Grade

/

Percent ES-401, Page 31 of 33

1. Initial conditions:

90% power.

Reactor protection testing is in progress.

Reactor Trip Breaker RTA is closed.

Reactor Trip Breaker RTB is open.

Reactor Trip Bypass Breaker BYB is closed.

Current conditions:

Reactor Trip Bypass Breaker BYA is inadvertently racked in and pushbutton RX TRIP BYPASS BKR A CLOSE was depressed.

Which ONE of the following describes the breaker alignment following the automatic plant response?

ASSUME NO OTHER OPERATOR ACTIONS RTA RTB BYA BYB A.

open open open closed B.

open open closed closed C.

open open open open D.

closed open open closed Saturday, May 16, 2015 10:53:11 AM

2. Initial conditions:

100% power initially.

A Pressurizer safety valve spuriously lifted and failed to reseat.

A Reactor Trip and Safety Injection occurred Current conditions:

All RCPs are stopped.

Pressurizer level is 60% and slowly rising.

RCS pressure is 1310 psig, stable.

RCS Subcooling is 0°F, stable.

The Pressurizer safety valve has 12 reseated.

Which ONE of the choices below completes the following statement?

If RCS pressure were to lower, Reactor Vessel level would _(1), and Pressurizer level would (2).

Reactor Vessel Pressurizer Level Level A. remain the same continue to rise at the same rate B. remain the same rise faster C.

lower continue to rise at the same rate D.

lower rise faster Saturday, May 16, 2015 10:53:11 AM 2

3. Given the following plant conditions:

100% power initially.

A LOCA occurred.

All offsite power (115KV and 230KV) was lost.

No Charging Pumps started automatically or manually.

RCS pressure is 1800 psig, rising.

Core Exit TCs are 730 °F, rising.

RVLIS Narrow Range Level is 44%, lowering.

Which ONE of the choices below completes the following statements?

The CORE COOLING status tree of EOP-12.0, MONITORING OF CRITICAL SAFETY FUNCTIONS, will direct operators to GO TO fi)

When reflux boiling is the dominant mode of heat transfer in the steam generators, the principal RCS heat removal flow path is as follows:

Hot RCS exits the reactor vessel via the hot leg nozzles

Flows through the hot leg piping due to natural circulation

Condenses in the U-tubes before flowing f)

A.

1) EOP-14.0, FR-Cl, RESPONSE TO INADEQUATE CORE COOLING

2) through the cold leg piping, the idle RCPs and into the reactor vessel via the cold leg nozzles B.

1) EOP-14.0, FR-Cl, RESPONSE TO INADEQUATE CORE COOLING

2) back down through the hot leg piping and into the reactor vessel via the hot leg nozzles C.

1) EOP-14.1, FR-C.2, RESPONSE TO DEGRADED CORE COOLING

2) through the cold leg piping, the idle RCPs and into the reactor vessel via the cold leg nozzles D.

1) EOP-14.1, FR-C.2, RESPONSE TO DEGRADED CORE COOLING

2) back down through the hot leg piping and into the reactor vessel via the hot leg nozzles Saturday, May 16, 2015 10:53:11 AM 3

4. Given the following plant conditions:

Time 1200:

100% power.

A large break LOCA occurred.

All offsite power (115KV and 230KV) was lost.

Time 1230:

RB Pressure peaked at 23.0 psig.

Time now 1500:

RB Pressure is 1.0 psig and slowly lowering.

Which ONE of the choices below completes the following statements?

The plant Emergency Core Cooling system is currently in a (1) recirculation alignment.

RB Spray (2) required to be in service.

A.

1) hot leg

2) is B.

1) hot leg

2) is C.

1) cold leg

2) is D.

1) cold leg

2) is not Saturday, May 16, 2015 10:53:11 AM 4

5. Given the following plant conditions:

100% power.

A sudden failure of the C RCP #2 seal has occurred.

The C RCP #1 and #3 seals are unaffected.

Which ONE of the following identifies how the C RCP #2 seal failure would affect the C RCP #1 seal leakoff flow indication and the C RCP standpipe level alarm?

1 Seal Leakoff RCP Standpipe Flow Indication Level Alarm A.

Increases Alarm due to low level B.

Increases Alarm due to high level C.

Decreases Alarm due to low level D.

Decreases Alarm due to high level Saturday, May 16, 2015 10:53:11 AM 5

the following plant conditions:

The reactor is tripped.

A loss of charging occurred.

All actions of AOP-1 02.2, LOSS OF CHARGING, are complete.

All RCPs are running with the following parameters:

RCP A Lower seal water bearing temperature 198°F Lower seal water outlet temperature 231°F RCP frame composite vibration 2.2 mils RCP shaft composite vibration 14 mils

6. Given RCP B 220°F 227°F 1.8 mils 20 mils RCP C 227°F 229°F 1.5 mils 12 mils Which ONE of the choices below completes the following statement?

Based on the current conditions, RCP trip criteria of SOP-i 01, REACTOR COOLANT SYSTEM, are met for A. the A and B RCPs; trip conditions do not exist for the C RCP B. the B and C RCPs; trip conditions do exist for the A RCP C. the A and C RCPs; trip conditions do not exist for the B RCP D. all three RCPs Saturday, May 16,201510:53:11 AM 6

7. Given the following plant conditions:

Unit 1 core off-load is in progress.

Water level is 23.5 above the Reactor Pressure Vessel (RPV) flange.

Operators are preparing to move fuel located in the vicinity of the RPV hot legs.

Which ONE of the choices below completes the following statements?

Based on the current conditions, Technical Specification 3.9.7, RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL, jJ allow operators to remove all RHR loop(s) from operation for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8-hour period.

The ACTION statement of TS 3.9.7 specifies that, among other actions, operators are required to immediatePy initiate J2L when no RHR loop(s) are OPERABLE and in operation.

A.

1) does

2) corrective action to return the required RHR loop to OPERABLE and operating status as soon as possible B.

1) does not

2) corrective action to return the required RHR loop to OPERABLE and operating status as soon as possible C.

1) does

2) action to close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere D.

1) does not

2) action to close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere Saturday, May 16, 2015 10:53:11 AM 7

8. Given the following plant conditions:

100% power.

XCP607, 2-5, INSTR AIR PRESS LO FLO HI is in alarm.

XCP-607, 2-6, SERV AIR PRESS [0 is in alarm.

P1-8342, INST AIR HDR PRESS PSIG reads 55 psig.

Which ONE of the choices below completes the following statements?

1PV08324-SA, STATION AIR SUPPLY HDR PRESS CONT VALVE is (1).

Turbine Group A and Group B drain valves will trip (2) on low air pressure.

A.

1) open.

2) open B.

1) open.

2) closed C.

1) closed.

2) open D.

1) closed.

2) closed Saturday, May 16, 2015 10:53:11 AM 8

9. Given the following plant conditions:

100% power, stable.

Pressurizer Pressure Control was in AUTO.

Pressurizer pressure was 2235 psig, stable.

PT-444, PZR Pressure Transmitter instantly failed to an output corresponding to 2280 psig.

Which ONE of the choices below completes the following statement?

Immediately after the PT-444 failure, the Master Pressure Controller will demand the sprayvalvestobe (1)

As time continues, the spray valves will (2)

ASSUME NO OPERATOR ACTIONS A.

1) fully closed

2) remain fully closed.

B.

1) 40% open

2) open more than 40% open as integral action takes effect.

C.

1) 40% open

2) close to less than 40% open as integral action takes effect.

D.

1) 60% open

2) open more than 60% open as integral action takes effect.

Saturday, May 16, 2015 10:53:11 AM 9

10. initial conditions:

90% power.

A spurious automatic Phase B isolation actuation occurred.

The operators attempted to trip the reactor manually.

The reactor failed to trip.

Current conditions:

EOP-13.0, RESPONSE TO ABNORMAL NUCLEAR POWER GENERATION, in progress.

TAVG is 14°F higher than TREF.

Reactor Power is 10% and lowering.

AlT RCPs are running.

The NROATC has just completed fully inserting all Control Bank rods.

All Shutdown Bank rods are fully withdrawn.

Which ONE of the choices below completes the following statements in accordance with EOP-13.0?

Based on the current conditions, operators (1) required to immediately trip all RCPs.

To provide the fastest negative reactivity insertion rate, operators will (2)

A.

1) are

2) allow Shutdown banks to insert automatically.

B.

1) are

2) manually insert Shutdown banks.

C.

1) are not

2) allow Shutdown banks to insert automatically.

D.

1) are not

2) manually insert Shutdown banks.

Saturday, May 16, 2015 10:53:11 AM 10

11. Given the following plant conditions:

Time 0420:

A tube rupture occurred in the C Steam Generator (SG).

The Reactor was manually tripped.

All offsite power (115KV and 230KV) was lost at the time of trip.

All systems responded as designed.

Time 0425:

EOP-1.0, REACTOR TRIP OR SAFETY INJECTION ACTUATION in progress.

C SG NR level is 22% and slowly rising.

Time 0435:

EOP-4.0, STEAM GENERATOR TUBE RUPTURE is in progress.

Operators isolated EFW flow to the C SG by closing the appropriate FCVs.

C SG NR level is 28% and stable.

Time 0440:

RCS cooldown in accordance with EOP-4.0 in progress.

C SG NR level is 24% and slowly lowering.

A and B SG NR levels are 55% and stable.

Which ONE of the choices below completes the following statements?

Based on the given sequence of events, EOP-4.0 Li) require operators to secure the Turbine-driven EFW pump.

At time 0440, operators are required to fj

, in accordance with EOP-4.0.

A.

1) does

2) maintain EFW isolated to the C SG.

B.

1) does

2) restore feeding the C SG with EFW.

C.

1) does not

2) maintain EFW isolated to the C SG.

D.

1) does not

2) restore feeding the C SG with EFW.

Saturday, May 16, 2015 10:53:11 AM ii

12. Given the following plant conditions:

A large steam break occurred downstream of the Main Steam Isolation Valves (MS lVs).

An automatic reactor trip and safety injection occurred.

Ji MSIVs failed OPEN and could be manually closed.

EOP-3.1. ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS (SG), is in progress.

Which ONE of the choices below completes the following sentence?

The reason for the CAUTION in EOP-3. 1 that requires a minimum EFW flow be maintained to each SG that has a Narrow Range level LESS THAN 26% is A.

to minimize thermal shock to SG components B. to maintain the ability to diagnose a subsequent SG tube rupture C. to maintain a cooldown rate in the RCS Cold Legs LESS THAN 100°F/hr D. to prevent damage to EFW pumps due to operating for long periods of time at low flow conditions Saturday, May 16, 2015 10:53:11 AM 12

13. Given the following plant conditions:

The plant was operating at 100%.

All offsite power (115KV and 230KV) was lost.

A and B Emergency Diesels failed to start.

EOP-6.0, LOSS OF ALL ESF AC POWER is in progress.

Operators have just begun depressurizing all intact Steam Generators (SGs) to 240 psig.

Which ONE of the choices below completes the following statements, in accordance with EOP-6.0?

Operators are required to maintain the cooldown rate in RCS Cold Legs below a maximum of (1)

If Pressurizer level is lost and Reactor Vessel Head voiding begins to occur during the cooldown, operators (2) required to stop the SG depressurization.

A.

1) 50°F/hr

2) are B.

1) 50°F/hr

2) are not C.

1) 100°F/hr

2) are D.

1) 100°F/hr

2) are not Saturday, May 16, 2015 10:53:11 AM 13

14. Given the following plant conditions:

100% power initially.

All offsite power (115KV and 230KV) was lost.

A and B Emergency Diesels failed to start.

EOP-6.0, LOSS OF ALL ESF AC POWER is in progress.

Operators are at step 8 of EOP-6.0 which reads as follows:

Place the switches for the following equipment in PULL TO LK NON-A to prevent auto start:

Which ONE of the choices below completes the following statement?

A (1) will be kept available during the performance of step 8 of EOP-6.0 to provide cooling for (2) upon restoration of power.

A.

1) CCW pump

2) RCP thermal barriers B.

1) CCW pump

2) Spent Fuel heat exchangers C.

1) Service Waterpump

2) Diesel Generators D.

1) Service Water pump

2) CCW heat exchangers Saturday, May 16, 2015 10:53:11 AM 14

15. Given the following plant conditions:

Mode 3.

Battery charger XBC lA-i B was in service on battery XBA1A.

The Static Switch for APN59O1 was in NORMAL.

Battery Charger XBC1A is ready for service.

An uninsulated tool was inadvertently dropped on the XBA1A battery terminals.

The following events occurred:

The XBA1A battery lead terminals to 1 HA vaporized and separated from the battery.

Battery charger XBC1A-1 B deenerciized.

Motor Control Center 1 DA2Y deenerciized.

Bus 1HA has remained intact.

Which ONE of the choices below completes the following statement regarding power to APN59O1?

APN59O1 is currently:

ASSUME NO OPERATOR ACTIONS A. deenergized; power can be restored by manually aligning the static switch for APN59O1 to BYP TO PREF.

B. deenergized; power can be restored by manually aligning XBC1A to 1 HA.

C. energized via the static switch and APN1 FA.

D. energized via bus 1 DA1 and inverter X1T5901.

Saturday, May 16, 2015 10:53:11 AM 15

16. Given the following plant conditions:

100% power initially.

A grid disturbance was reported by the System Controller.

AOP-301.1, RESPONSE TO ELECTRICAL GRID ISSUES, in progress.

Grid frequency is lowering linearly and slowly.

Which ONE of the choices below completes the following statements?

RCP supply breakers will automatically trip open if their associated motor frequency goes below a setpoint of (1).

(2) will open automatically as a direct result of grid frequency lowering to a specified setpont.

A.

1) 57.5 HZ 2)

XCBOO1O, MAIN GENERATOR CIRCUIT BREAKER B.

1) 57.5 HZ 2)

OCB 8902, MAIN XFMR FEED C.

1) 58.5 HZ 2)

XCBOO1O, MAIN GENERATOR CIRCUIT BREAKER D.

1) 58.5 HZ 2)

OCB 8902, MAIN XFMR FEED Saturday, May 16, 2015 10:53:11 AM 16

17. Given the following plant conditions:

A small break LOCA has occurred.

RB Pressure peaked at 2.8 psig and is slowly lowering.

No EFW pumps are available.

EOP-150, RESPONSE TO LOSS OF SECONDARY HEAT SINK is in progress.

Plant parameters are as follows:

Time PZR pressure SG A WR level SG B WR level SG C WR level 0400 2250 and rising 11%

22%

24%

0410 2300 and rising 8

11 22 0420 2340 and rising 7

10 20 0430 2345 and rising 6

8 10 Of the choices below, which ONE of the following is the time conditions are met to initiate bleed and feed cooling, in accordance with EOP-1 5.0?

A. 0400 B. 0410 C. 0420 D. 0430 Saturday, May 16, 2015 10:53:11 AM 17

18. Initial Conditions:

A small break LOCA has occurred.

A rupture of the RWST occurred.

Operators entered EOP-2.4, LOSS OF EMERGENCY COOLANT RECIRCULATION.

Charging and RHR pumps were placed in PULL TO LK NON-A as directed by EOP-2.4.

Current Conditions:

RCS pressure is 450 psig and stable.

The RWST rupture has been temporarily repaired.

Operators have established makeup to the RWST.

The Technical Support Center (TSC) has determined that RWST level can be maintained without further loss of volume from the rupture.

RWST level is 20%, increasing.

RHR sump level is 412 ft, stable.

MVG-8706A(B), RHR LP A(B) TO CHG PP are closed.

Which ONE of the choices below completes the following statement in accordance with EOP-2.4?

Based on the current conditions, operators will:

A. leave Charging Pumps in PULL TO LK NON-A and start jjy one RHR Pump to provide maximum cooling flow to the core.

B. leave RHR pumps in PULL TO LK NON-A and start 2flJY one Charging Pump to establish core cooling and conserve RWST inventory.

C. maintain Charging and RHR Pumps in PULL TO LK NON-A to avoid running with inadequate net positive suction head.

D. start one Charging Pump and one RHR pump in the same train to prepare for restoration of recirculation capability.

Saturday, May 16, 2015 10:53:11 AM 18

19. Given the following plant conditions:

A reactor trip occurred from 100% power.

Shutdown Bank A rod J3 is stuck at its fully withdrawn position.

Control Bank C rod D12 is stuck at 70 steps withdrawn.

All other Shutdown and Control rods are completely inserted.

Which ONE of the following identifies how the manual Shutdown Margin (SDM) calculation of STP-134.001, SHUTDOWN MARGIN VERIFICATION accounts for the stuck rods in the conditions above?

A. The two stuck rods do not affect the post-trip SDM calculation because refueling boron concentration is used as the reference condition.

B. The position of rod J3 does not affect the SDM calculation. A positive reactivity value is assessed for rod D12 and the boron concentration is adjusted to compensate for one stuck rod.

C. The position of rod Dl 2 does not affect the SDM calculation. A positive reactivity value is assessed for rod J3 and the boron concentration is adjusted to compensate for one stuck rod.

D. A positive reactivity value is assessed for both rods J3 and D12 in the SDM calculation. The boron concentration is adjusted to compensate for two stuck rods.

Saturday, May 16, 2015 10:53:12AM 19

20. Initial conditions:

MODE 1.

Pressurizer heaters BU GRP 1 control switch is in AFTER CLOSE.

Pressurizer heaters BU GRP 2 control switch is in AFTER TRIP.

Current conditions:

A malfunction of FCV-122 has caused Pressurizer level to lower.

Actual Pressurizer level is 45% decreasing.

Pressurizer program level is 51 %.

Pressurizer pressure is 2219 psig, lowering.

Which ONE of the choices below completes the following statements?

XCP-616, 1-5, PZR LCS DEV HI/LO (1) in alarm.

All Pressurizer backup heaters (2) energized.

ASSUME NO OPERATOR ACTIONS A.

1) is

2) are B.

1) is

2) are not C.

1) is not

2) are D.

1) is not

2) are not Saturday, May 16, 2015 10:53:12 AM 20

21. Given the following plant conditions:

MODE 6 with core off-load in progress.

The Fuel Handling Building (FHB) SRO reports that a fuel bundle was binding while inserting into the rack, and is now stuck approximately 50% inserted.

The fuel bundle cannot be fully inserted or removed.

All radiation monitors in both the RB and the FHB are reading the same normal levels as before the report of the stuck fuel bundle.

Which ONE of the following choices below completes the following statement?

Based on the given conditions, entry conditions for AOP-123.3, POTENTIAL FUEL ASSEMBLY DAMAGE WHILE HANDLING FUEL, A. are not met, because AOP-1 23.3 only mitigates potential fuel handling accidents in the RB, not the FHB.

B. are not met, because there are no radiation monitors in the RB or FHB that are indicating increasing radiation levels.

C. are met, and AOP-1 23.3 will require evacuation of unnecessary personnel from the FHB because the stuck fuel assembly could be potentially damaged.

D. are met, but AOP-1 23.3 will not require evacuation of unnecessary personnel from the FHB because FHB radiation levels are jj increasing.

Saturday, May 16, 2015 10:53:12 AM 21

22. Which ONE of the choices below completes the following statement?

A CAUTION in AOP-206.1, DECREASING MAIN CONDENSER VACUUM, states that if Main Condenser pressure is GREATER THAN (1)

, Main Turbine load must NOT be reduced to LESS THAN (2), to prevent Turbine damage.

A.

1) 5 inches Hg absolute

2) 30%

B.

1) 5 inches Hg absolute

2) 50%

C.

1) 7.5 inches Hg absolute

2) 30%

D.

1) 7.5 inches Hg absolute

2) 50%

Saturday, May 16, 2015 10:53:12AM 22

23. Given the following plant conditions:

Operators manually tripped the Reactor from the Main Control Board before evacuating the Control Room.

Two (2) control rods did not fully insert on the Reactor trip.

a AOP-600.1, CONTROL ROOM EVACUATION is in progress.

Operators are referring to AOP-106.1 EMERGENCY BORATION and aligning for boration in Step 4, Emergency Borate by gravity drain of the Boric Acid Tank.

Which ONE of the choices below completes the following statements?

Based on the given conditions, AOP-600.1 requires operators to borate fjJ The Operators are cautioned in AOP-1 06.1 to monitor Charging pump amps and flow carefully while performing the gravity drain alignment because (2) must be closed.

A.

1) a fixed amount of 2500 gallons.

2) LCV-1 15C(E), VCT OUTLET ISOL valves B.

1) a fixed amount of 2500 gallons.

2) XVD08329-CS, CHARGING/SI PUMPS SUCTION HEADER VALVE and XVD08331-CS, CHARGING/SI PUMPS SUCT HDR ISOL VALVE C.

1) an amount determined by a Shutdown Margin calculation based on temperature.

2) LCV-1 1 5C(E), VCT OUTLET ISOL valves D.

1) an amount determined by a Shutdown Margin calculation based on temperature.

2) XVD08329-CS, CHARGING/SI PUMPS SUCTION HEADER VALVE and XVD08331-CS, CHARGING/SI PUMPS SUCT HDR ISOL VALVE Saturday, May 16, 2015 10:53:12AM 23

24. Initial Conditions:

A Small-break LOCA with multiple coincident equipment failures occurred.

Operators entered EOP-14.0, FR-Cl, RESPONSE TO INADEQUATE CORE COOLING.

No RCPs are running.

Current Conditions:

Operators are performing continuous action step 13, Check INTACT SG Levels, of EOP-14.0.

XCP-621, 3-5 EFP SUCT HDR PRESS LO XFER TO SW has just alarmed.

Ll-3621A, CST LEVEL FEET, is reading 6.0 feet, slowly lowering.

P1-3632, EF PP SUCT PRESS, is reading 12.1 psig, slowly lowering.

Which ONE of the choices below completes the following statements?

Based on the current conditions, the automatic signal to transfer EFW suction to Service Water (1) actuated.

A NOTE in EOP-14.0 states that the preferred RCP starting sequence under Inadequate Core Cooling conditions is (2).

A.

1) has

2) B, C, A B.

1) has

2) C, B, A C.

1) has not

2) B,C,A D.

1) has not

2) C, B, A AM U/REA1T fLI PuMP vcno PESsURE 5

/ (, /

Saturday, May 16, 2015 10:53:12AM 24

25. Given the following plant conditions:

Time 0700:

100% power.

An HP technician notifies the control room that radiation surveys in the vicinity of the letdown piping were unexpectedly high and increasing.

Normal letdown is in service at a flow rate of 105 gpm and stable.

Time 0705:

XCP-642, 4-3, RC LTDN LO RNG RM-L1 HI RAD (XCP-642 4-3) is in alarm.

Which ONE of the choices below completes the following statement?

As a result of the RM-L1 high radiation alarm, A. letdown flow will automatically isolate.

B. letdown flow will automatically divert away from the VCT.

C. operators will take manual actions to maximize letdown flow by placing only the two 60 gpm letdown orifices in service.

D. operators will take manual actions to minimize letdown flow by placing only the 45 gpm letdown orifice in service.

Saturday, May 16, 2015 10:53:12AM 25

26. Given the following plant conditions:

100% power initially.

A LOCA has occurred.

Operators are performing EOP-2.i, ES-i.2, POST-LOCA 000LDOWN AND DEPRESS U R IZAT ION.

A RCS cooldown at a rate less than 100 °FIhr on RCS Cold Legs is in progress.

RCP A is the jy running RCP.

Plant parameters are as follows:

SI flow is indicated on FF943, CHG LOOP B CLD/HOT LG FLOW GPM.

Subcooling is 49.5 °F and lowering.

RCS Pressure is 1410 psig and lowering.

Tcold is 540 °F and lowering.

Which ONE of the choices below completes the following statements?

Based on the current conditions, operators _(1)_ required to secure the A RCP.

If no additional accident or failure occurs, EOP-2.1 (2)_ contain the procedural guidance that will lower RCS temperature and pressure to the values necessary to place RHR cooling in service.

A.

1) are not

2) does B.

1) are not

2) does not C.

1) are

2) does D.

1) are

2) does not f4oiIiFY r

ttEA CS ooL

/-;sj 1

ç Saturday, May 16, 2015 10:53:12 AM 26

27. Given the following plant condition:

Operators have entered EOP-16.0, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK, following an automatic Reactor trip and Safety Injection.

Which ONE of the choices below completes the following statements?

EOP-1 6.0 directs the operators to check if SI can be terminated using the following parameters: RCS subcooling(,)

fjJ After the temperature soak period has been completed in accordance with EOP-16.0, operators are required to limit the subsequent cooldown rate in the RCS Cold Legs to a maximum of in jy one hour period.

A.

1) and RVLIS level

2) 25°F B.

1) and RVLIS level

2) 50°F C.

1) total EFW flow or SG narrow range level, RCS pressure, and PZR level.

2) 25°F D.

1) total EFW flow or SG narrow range level, RCS pressure, and PZR level.

2) 50°F Saturday, May 16, 2015 10:53:12AM 27

28. Given the following plant conditions:

Time 0100:

Operators have entered EOP-6.0, LOSS OF ALL ESF AC POWER, following a large seismic event.

Alternate Seal Injection (ASI) is inoperable and out of service.

Time 0115.

The control room operators are at the step in EOP-6.0 to depressurize all intact Steam Generators (SGs) to 240 psig.

The ASI system is available to be manually started.

Which ONE of the choices below completes the following statement?

In accordance with a CAUTION in EOP-6.0, operators (1) manually start the ASI system, because (2)

A.

1) should

2) re-establishing seal injection in a controlled manner would result in limiting the potential that a RCP seal LOCA could occur.

B.

1) should

2) re-establishing seal injection would add both inventory and boron to the RCS that would help establish stable conditions (such as shutdown margin) during the imminent cool down.

C.

1) should not

2) if the ASI system is in operation, then Pressurizer level will likely be increasing, and EOP-6.0 has directed operators to isolate letdown.

D.

1) should not

2) thermal shock to the RCP seals could result in a RCP seal LOCA with significant increase in RCS water loss.

Saturday, May 16, 2015 10:53:12 AM 28

29. Given the following:

Operators are placing Auxiliary Spray in service in accordance with SOP-i 02, CHEMICAL AND VOLUME CONTROL SYSTEM, Section 111.0, PRESSURIZER AUXILIARY SPRAY OPERATION.

Which ONE of the choices below completes the following statements?

A NOTE in SOP-i 02, Section 111.0. states that Tl-140, REGEN HX OUT TEMP °F, should be maintained less than (1).

LCO 3.4.9.2, PRESSURIZER, statement c., requires that the pressurizer temperature shall be limited to a maximum auxiliary spray water differential of (2).

A. i) 350°F

2) 320 °F B.

1) 350°F

2) 625 °F C.

1) 400°F

2) 320°F D.

1) 400°F

2) 625 °F Saturday, May 16, 2015 10:53:12 AM 29

30. Initial conditions:

75% power.

VCT level is 30%, stable.

TCV-143, LTDN TO VCT OR DEMIN control switch is in the AUTO position.

Current condition:

A 10 gpm tube leak has developed in the Letdown Heat Exchanger.

Which ONE of the choices below completes the following statements?

The leak in the Letdown Heat Exchanger will cause VCT level to initially trend (1)

TCV-143, will automatically shift to the VCT position when the Letdown Heat Exchanger outlet coolant temperature reaches the high temperature setpoint of

_(2)_.

ASSUME NO OPERATOR ACTIONS A.

1) lower.

2) 135°F.

B.

1) lower.

2) 155°F.

C.

1) higher.

2) 135°F.

D.

1) higher.

2) 155°F.

Saturday, May 16, 2015 10:53:12AM 30

31 Given the following plant conditions Plant cooldown is in progress in accordance with GOP-6, PLANT SHUTDOWN FROM HOT STANDBY TO COLD SHUTDOWN MODE 3 TO MODE 5.

RCS temperature is 330°F and lowering.

Which ONE of the chOices below completes the following statements?

The highest RCS temperature at which Cold Overpressure Protection is required to be placed in service is (1) in accordance with 3.4.9.3, REACTOR COOLANT SYSTEM

- OVERPRESSURE PROTECTION SYSTEMS.

When XVR08708A-RH, RH INLET HEADER A RELIEF VALVE is placed in service, it will lift at a setpoint of(2).

A. 2) 200° F.

1) 450 psig B.

1) 200°F.

2) 600 psig C. 2) 300°F.

1) 450 psig D.

1) 300°F.

2) 600 psig Saturday, May 16, 2015 10:53:12AM 31

32. Given the following plant conditions:

Time 1600:

A large-break LOCA has occurred.

EOP-2.0, LOSS OF REACTOR OR SECONDARY COOLANT in progress.

EOP-17.0, RESPONSE TO HIGH REACTOR BUILDING PRESSURE was entered due to an ORANGE path on the CONTAINMENT Critical Safety Function (CSF).

All other safety functions are GREEN.

Time 1610:

The actions of EOP-17.0 have !2.Q been completed.

An ORANGE path for INTEGRITY is now indicated.

All other CSF statuses are GREEN.

Time 1615:

The EOP in progress is still j complete.

The INTEGRITY CSF status just turned GREEN.

All other CSF statuses have remained GREEN since 1610.

Which ONE of the following describes the correct procedural implementation in accordance with OAP-103.4, EOP/AOP USERS GUIDE?

Note: EOP-16.0 is RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK.

A. At 1610, operators will suspend performance of EOP-17.0 and enter EOP-16.0.

At 1615, operators will continue in EOP-16.0 until all actions are complete.

B. At 1610, operators will suspend performance of EOP-17.0 and enter EOP-16.0.

At 1615, operators will stop actions of any EOP entered for a CSF status and return to EOP-2.0.

C. At 1610, operators will continue in EOP-17.0.

At 1615, Operators will continue until actions in EOP-17.0 are complete and then transfer to EOP-16.0.

D. At 1610, operators will continue in EOP-17.0.

At 1615, operators will continue until the actions of EOP-17.0 are complete and then return to EOP-2.0.

Saturday, May 16, 2015 10:53:12 AM 32

33. Given the following plant conditions:

Time 0900:

100% power initially.

A LOCA occurred with multiple equipment failures.

EOP-14.0, FR-Cl, RESPONSE TO INADEQUATE CORE COOLING in progress.

The operators were unable to establish safety injection flow to the RCS.

Time 0920:

When operators attempted to close SI Accumulator discharge isolation valves, both MVG-8808A, A DISCH ISOL; and MVG-8808C, C DISCH ISOL, failed to close.

Which ONE of the choices below completes the following statements in accordance with EOP-14.0?

After attempting to re-establish safety injection flow at 0900, the next major action category of EOP-14.0 directed operators to (1)

At 0920, operators are required to vent Nitrogen (N2) from (2)

A.

1) start RCPs and open all RCS vent paths to containment.

2) aN SI Accumulators.

B.

1) start RCPs and open all RCS vent paths to containment.

2) the two affected SI Accumulators.

C.

1) rapidly depressurize Steam Generators (SGs) to depressurize the RCS

2) all SI Accumulators.

D.

1) rapidly depressurize Steam Generators (SGs) to depressurize the RCS

2) the two affected SI Accumulators.

Saturday, May 16, 2015 10:53:12 AM 33

34. Given the following plant conditions:

100% power.

PRT level has been unexpectedly rising over the last few weeks.

Which ONE of the following is a potential source of leakage into the PRT?

A. XVR081 17-CS, LETDOWN FLOW CONTROL HDR RELIEF VALVE (RB 412)

B. XVR-8121, RC PUMP SEAL RETURN HEADER RELIEF VALVE (RB 412)

C. MVG-8095A, RX HEAD VENT VLV (RB 463)

D. XVN-8032, RV FLNGE LKOFF (RB 412)

Saturday, May 16, 2015 10:53:12 AM 34

35. Which ONE of the following describes the maximum time limit, if any, for operation of RHR pumps without CCW flow to the RHR Heat Exchangers In accordance with AOP-118.1, TOTAL LOSS OF COMPONENT COOLING WATER?

A.

10 minutes B. 20 minutes C. 90 minutes D. no time limit, as long as y maximum temperature is not exceeded Saturday, May 16, 2015 10:53:12AM 35

36. Initial conditions:

MODE 3 at normal operating pressure.

Pressurizer Pressure Control is in AUTO.

Current conditions:

The following Pressurizer Pressure Channel indications are noted:

P1-444 = 2050 psig

P1-445 = 2500 psig

P1-455 = 2000 psig

P1-456 = 1950 psig

P1-457 = 2050 psig Based on the current conditions, which ONE of the following describes the positions of Pressurizer PORVs (PCV-444B, PCV-445A, and PCV-445B)?

ASSUME NO OPERATOR ACTION PCV-444B PCV-445A PCV-445B A.

OPEN OPEN OPEN B.

CLOSED OPEN OPEN C.

OPEN OPEN CLOSED D.

CLOSED CLOSED CLOSED Saturday, May 16, 2015 10:53:12 AM 36

37. Initial Conditions:

100% power.

Train B SSPS testing in accordance with STP-345.074, SSPS ACTIVATION LOGIC AND MASTER RELAY TEST FOR TRAIN B is in progress.

Reactor Trip breaker A (RTA) is CLOSED Bypass breaker A (BYA) is OPEN.

Reactor Trip breaker B (RTB) is CLOSED.

Bypass breaker B (BYB) is CLOSED.

Current conditions:

The input supply breaker on DPN1 HA to DPN1 HAl tripped open.

Control power to the associated train of Reactor trip and bypass breakers has been lost.

Power to Safeguards Cabinet Channel A is !Q affected.

Which ONE of the following describes the current Reactor Trip and Bypass breaker positions and the next required operator action(s) to address this event?

A. Trip and Bypass breaker positions have not changed; Manually trip the reactor and perform the immediate operator actions of EOP-1.0, Reactor Trip or Safety Injection.

B. Only RTA has opened; dispatch an operator to investigate and reset the tripped breaker at DPN1 HA per the applicable ARP.

C. Only RTA and BYB have opened; perform the immediate operator actions of EOP-1.0, Reactor Trip or Safety Injection.

D. Trip and Bypass breaker positions have not changed; dispatch an operator to investigate and reset the tripped breaker at DPNI HA per the applicable ARP.

Saturday, May 16, 2015 10:53:12 AM 37

38. Given the following plant conditions:

Time 0500:

100% power.

A malfunction caused a loss of output voltage from Inverter XIT-5903.

Time 0510:

Personnel installing scaffolding inadvertently trip open the 1 DB bus normal feed breaker.

operator actions have occurred.

Any designed automatic actions have occurred.

Which ONE of the choices below completes the following statement?

Based on the current conditions, the B Emergency Diesel Generator will automatically

start, A. but its output breaker will j close.

B.

its output breaker will close, but no loads will automatically start.

C. its output breaker will close, and all loads that were energized prior to the 1 DB undervoltage will re-energize simultaneously.

D. its output breaker will close, and 1i required loads will automatically start sequentially via the blackout sequencer.

Saturday, May 16, 2015 10:53:12AM 38

39. Given the following plant conditions:

Time 0320:

100% power initially.

lA, 1B, and 2A RBCUs were running in NORM (fast speed).

The RBCU TRAIN A EM ERG switch is selected to XFN 64A.

The RBCU TRAIN B EM ERG switch is selected to XFN 64B.

An automatic Safety Injection (SI) occurs.

Time 0322:

RBCU 1 B tripped on overload.

Time at 0330:

No operator actions have occurred relating to the RBCU systems.

The operator performing Attachment 3, SI EQUIPMENT VERIFICATION, of EOP-1.0, E-0 REACTOR TRIP OR SAFETY INJECTION, is at the step to ensure proper RBCU system alignment.

Which ONE of the choices below completes the following statements?

At time 0330, before taking any manual actions, the operator performing SI equipment verification will find the 2A RBCU (1).

If 2B RBCU is started at 0331 in slow speed with the RBCU TRAIN B EM ERG switch aligned to the XFN 65B position, this (2) satisfy the Attachment 3 requirement for running RBCUs.

A.

1) running

2) will not B.

1) running

2) will C.

1) fl2 running

2) will not D.

1) not running

2) will Saturday, May 16, 2015 10:53:12AM 39

40. Given the following plant conditions:

MODE 1.

iA RBCU is being returned to service following bearing replacement.

Mechanical Maintenance requested that the fan be started in NORM.

After running for two (2) minutes, Maintenance requested that the fan be stopped.

Current conditions:

35 minutes after the fan was stopped, Maintenance requests that the fan be restarted.

Which ONE of the choices below completes the following statements?

In accordance with SOP-i 14, REACTOR BUILDING VENTILATION SYSTEM, when starting the fan in NORM, the control switch must be held in START until the RED breaker closed light is lit

______(I)______

Based on the current conditions, operators (2) allowed to immediately restart the lA RBCU in accordance with SOP-I 14.

A.

1) starting current is indicated on the fans amp meter

2) are B.

1) starting current is indicated on the fans amp meter

2) are riot C. i) annunciator XCP-606 (1-1), RBCU 1AJ2A FAN TRIP, clears

2) are D.

1) annunciator XCP-606 (1-i), RBCU 1A/2A FAN TRIP, clears

2) are not Saturday, May 16, 2015 10:53:12AM 40

41. Which ONE of the choices below completes the following statements?

Sodium Hydroxide (NaOH) is added to Reactor Building (RB) Spray flow in order to reduce the concentration of(1) in the RB atmosphere after a LOCA.

MVG-3002A and MVG-3002B, NaOH suction line isolation valves, are directly interlocked to automatically open in response to a (2)

A.

1) explosive hydrogen

2) RB spray actuation signal B.

1) explosive hydrogen

2) phase A containment isolation signal C.

1) radioactive iodine

2) RB spray actuation signal D.

1) radioactive iodine

2) phase A containment isolation signal Saturday, May 16, 2015 10:53:12 AM 41

42. Given the following plant conditions:

100% power initially.

Cold weather has caused RWST level indicators Ll-991, Ll-992, and Ll-993 to freeze and they are unable to respond to level changes.

RWST level indicator LI-990 remained OPERABLE.

A large-break LOCA occurred causing an automatic Reactor trip, automatic Safety Injection, and automatic RB Spray actuation.

Which ONE of the choices below completes the following statements?

When actual RWST level lowers below 18%,

(1)

Valve XVG-3001A, RWST TO SPRAY PUMP A SUCT, will not automatically close because (2)

ASSUME NO OPERATOR ACTIONS A.

1) valve XVG-3005A, SUMP ISOL LOOP A, will have received an automatic open signal; valve XVG-3004A, SUMP ISOL LOOP A, will not have received an automatic open signal.

2) it is directly interlocked to close on a RWST level signal, and the required coincidence is not met due to the frozen RWST level instruments B.

1) valve XVG-3005A, SUMP ISOL LOOP A, will have received an automatic open signal; valve XVG-3004A, SUMP ISOL LOOP A, will not have received an automatic open signal

2) it is directly interlocked to close when both XVG-3004A and XVG-3005A are fully open, and the required coincidence is not met due to the valve positions C.

1) both valves XVG-3005A, SUMP ISOL LOOP A, and XVG-3004A, SUMP ISOL LOOP A, will not have received an automatic open signal.

2) it is directly interlocked to close on a RWST level signal, and the required coincidence is not met due to the frozen RWST level instruments D.

1) both valves XVG-3005A, SUMP ISOL LOOP A, and XVG-3004A, SUMP ISOL LOOP A, will not have received an automatic open signal

2) it is directly interlocked to close when both XVG-3004A and XVG-3005A are fully open, and the required coincidence is not met due to the valve positions Saturday, May 16, 2015 10:53:12 AM 42

43. Initial conditions:

45% power.

The STM DUMP MODE SELECT Switch is in TAVG.

Current condition:

Operators manually tripped the Main Turbine to address an oscillating Turbine control valve.

C7-B status light is bright.

Which ONE of the following is the TAVG deviation band (TAVG TREE) within which the Atmospheric Steam Dump Valves (IFV-2006, IFV-2016, IFV-2026) will actuate?

FULL CLOSE FULL OPEN A. <2°F

>5.7°F B.

5.7°F

> 16.9°F C. <16.9 °E

> 22.4 °F D. <22.4°F

>28°F Saturday, May 16, 2015 10:53:12 AM 43

44. Given the following initial conditions:

50% power.

B and C Feedwater Pumps running.

A Feedwater Pump being returned to service in accordance with SOP-210, FEEDWATER SYSTEM, following emergent maintenance.

The pump was running at a stable speed of 4200 RPM with the DOS M/A station in Auto.

Current conditions:

The A Feedwater Pump speed begins to increase uncontrollably at a rate of approximately 100 RPM per minute.

Which ONE of the choices below completes the following statement?

As A Feedwater Pump speed continues to increase, either the overspeed setpoint of (1) or the high discharge pressure setpoint of _(2)_ could cause the pump to trip.

A.

1) 5670 rpm

2) 1660 psig B.

1) 5670 rpm

2) 1720 psig C.

1) 6380 rpm

2) 1660 psig D.

1) 6380 rpm

2) 1720 psig Saturday, May 16, 2015 10:53:12AM 44

45. Given the following plant conditions:

Time 0605:

90% power.

B emergency diesel generator is tagged out for maintenance.

Time 0607:

Normal feed breaker to Bus I DA automatically trips open.

All Main Feed Water pumps automatically trip.

Time 0610:

Steam Generator (SIG) narrow range levels have decreased steadily after the trip to the following values:

A S/G is 28%.

B S/G is 40%. C S/G is 37%.

Which ONE of choices below completes the following statement?

At time 0610, both motor-driven EFW pumps (1) be running, and the turbine-driven EFW pump (2) be running.

ASSUME NO OPERATOR ACTIONS Lfl A.

will will not B.

will not will not C.

will will D.

will not will Saturday, May 16, 2015 10:53:12 AM 45

46. Which ONE of the choices below completes the following statements?

The opening force for 1FV02030-MS, EF PUMP TURB STEAM SUPPLY FLOW CONT VLV, to permit TD EFW Pump operation is __fiL_.

1FV02030-MS (2) equipped with an attached air accumulator.

A.

1) spring pressure

2) is B.

1) spring pressure

2) is not C.

1) air pressure

2) is D.

1) air pressure

2) is Saturday, May 16, 2015 10:53:12AM 46

47. Which ONE of the choices below completes the following statements?

With the Turbine Driven (TD) EFW Pump in service with flow control valves closed, the pumps recirculation flow line directs flow back to the (1)

Per SOP-21 1, EMERGENCY FEEDWATER, operation of EFW pumps with flow control valves closed is limited to a maximum duration of f

A.

1) suction of the TD EFW pump.

2) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

B.

1) suction of the TD EFW pump.

2) 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

C.

1) Condensate Storage Tank.

2) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

D.

1) Condensate Storage Tank.

2) 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Saturday, May 16, 2015 10:53:12AM 47

48. Initial Conditions:

100% power initially.

All offsite power (115KV and 230KV) was lost.

A and B Emergency Diesel Generators (EDG5) failed to start.

Current Conditions:

EOP-6.0, LOSS OF ALL ESF AC POWER in progress.

Operators have started the A EDG.

Which ONE of the choices below completes the following statements?

In accordance with a CAUTION in EOP-6.0, A EDG can be loaded up to a limit of

_(1)_ KW for a seven (7) day period.

The A EDG fuel rack stop setting will prevent loading of that diesel in excess of

_(2)_ KW.

A.

1) 4250

2) 4760 B.

1) 4250

2) 5100 C.

1) 4676

2) 4760 D.

1) 4676

2) 5100 Saturday, May 16, 2015 10:53:12AM 48

49. Given the following plant conditions:

100% power.

XCP-637, 4-5, DC SYS TRAIN B GND TRBL, unexpectedly alarms.

In accordance with the appropriate ARP, an operator was dispatched to XPN5440 (IB-41 2).

Which ONE of the choices below completes the following statements?

The ground trouble alarm above (1) cause an automatic action (or actions).

XCP-637, 4-5 annunciates when the ground current setting in milliamperes for the alarm is met (2).

A.

1) does

2) for a specified time delay in seconds.

B.

1) does

2) without a time delay (immediately).

C.

1) does not

2) for a specified time delay in seconds.

D.

1) does not

2) without a time delay (immediately).

Saturday, May 16, 2015 10:53:12AM 49

50. Given the following plant conditions:

Operators are placing battery charger XBC1X-2X in service per SOP-311, 125 VDC SYSTEM,Section IV. M. PLACING BATTERY CHARGER XBC1X-2X IN SERVICE.

The following breakers have just been closed on the front of XBC1X-2X:

CB2, DC OUPUT CB1,AC INPUT Which ONE of the choices below completes the following statement in accordance with SOP-311?

A note in SOP-31 1 specifically states that, to allow capacitors to fully charge and the battery charger to stabilize, an operator is required to wait at least (1).

After that time has elapsed, then (2).

REFERENCE PROVIDED A.

1) five to ten (5-10) seconds after closing CB1.

2) 1 DPN1 HX M4 can be closed.

B.

1) five (5) minutes after closing CB1 2) 1 DPN1 HX M4 can be closed.

C.

1) five to ten (5-10) seconds after closing 1DPN1HXM4.

2) 1DPNIHX M2 can be opened.

D.

1) five (5) minutes after closing 1DPN1HX M4.

2) 1 DPN1 HX M2 can be opened.

Saturday, May 16, 2015 10:53:12AM 50

12OY t8436 APN IFX1

50 120V 27 436 lx 13 CB436 I

I I

I 125Y siSTATION DPN lS F20v CB 434 APN 5@6 PARTIAL COPY OF E-205-006 436 120V1 PN

51. Given the following plant conditions:

100% power.

An automatic Safety Injection (SI) occurred.

Offsite power to bus 1 DA was lost.

The A Emergency Diesel Generator (EDG) automatically started and restored power to bus iDA.

The following annunciators are in alarm in the Control Room:

XCP-636, 1-2, HIGH LUBE OIL TEMPERATURE XCP-636, 6-3, DG A ENG TEMP TRBL An operator reports the following local conditions at the A EDG.

XCX-5201, 1-2, HIGH LUBE OILTEMPERATURE is in alarm.

Lube Oil Temperature is reading 180°F and rising.

There is no Service Water flow to the A DG.

Which ONE of the choices below completes the following statement?

Based on the current conditions, DG A (1) have automatically tripped; and Fire Service Water aligned to the DG A lube oil cooler.

A.

1) should

2) must be manually B.

1) should not

2) must be manually C.

1) should

2) will be automatically D.

1) should not

2) will be automatically Saturday, May 16, 2015 10:53:12 AM 51

52. Which ONE of the following sets of valves will re-position as indicated on a sensed Hi Radiation signal generated by detector RM-L3, STEAM GENERATOR BLOWDOWN LIQUID MONITOR?

A.

PVT-524, TO CW will close.

PVG-525, DIVERT TO NB will open.

B.

PVT-524, TO CW will close.

PVG-525, DIVERT TO NB will close.

C. PVD-6121, NUC BLOWDOWN DISCHARGE will close.

PVG-525, DIVERT TO NB will close.

D. PVD-6121, NUC BLOWDOWN DISCHARGE will close.

PVG-525, DIVERT TO NB will open.

Saturday, May 16, 2015 10:53:12 AM 52

53. Given the following plant conditions:

100% power initially.

A Large break LOCA occurs.

A loss of 115 Ky power occurred at the same time as the LOCA.

Which ONE of the choices below completes the following statements?

MOV XVB-3106A-SW, VLV ISOL REAC BLDG INLET A, the discharge isolation valve of the A Service Water Booster Pump, is supplied power directly from (1).

Three (3) minutes after the Large Break LOCA event occurs, MOV XVB-31 06A-SW (2) be open.

ASSUME NO OPERATOR ACTIONS A.

1) XMC1DA2Z

2) will B.

1) XMCIDA2X

2) will C.

1) XMC1DA2Z

2) will not D.

1) XMC1DA2X

2) will not Saturday, May 16, 2015 10:53:12AM 53

54. Which ONE of the choices below completes the following statements?

During a refueling outage, Nitrogen (1) be aligned via permanently installed Nitrogen system piping to operate Main Steam Isolation Valves.

A MSIV is closed by (2).

A.

1) can

2) spring pressure acting on the associated valve stem.

B.

1) can

2) air pressure applied to the associated operating cylinder.

C.

1) cannot

2) air pressure applied to the associated operating cylinder.

D.

1) cannot

2) spring pressure acting on the associated valve stem.

Saturday, May 16, 2015 10:53:12 AM 54

55. Given the following plant conditions:

Mode6 Reactor Building Purge is in progress in accordance with SOP-114, REACTOR BUILDING VENTILATION SYSTEM.

A circuit card malfunction of RM-A4, REACTOR BUILDING PURGE EXHAUST MONITOR, causes a spurious RM-A4 High Radiation Alarm.

NOTE:

XVB-1A, RB PURGE SUPPLY ISOLATION VALVE XVB-1 B, RB PURGE SUPPLY ISOLATION VALVE XVB-2A, RB PURGE EXHAUST ISOLATION VALVE XVB-2B, RB PURGE EXHAUST ISOLATION VALVE Which ONE of the following identifies the valves that automatically close directly from the spurious RM-A4 High Radiation Alarm?

A. jy XVB-2A and XVB-2B B. pjjjy XVB-1A and XVB-2A C. 2jyXVB-1B and XVB-2B D. XVB-1A, XVB-1 B, XVB-2A, and XVB-2B all close Saturday, May 16, 2015 10:53:12 AM 55

56. Which ONE of the choices below completes the following statements?

The CRDM Cooling Water System includes the component FT75025, CRDM LEAK DETECTION DRAIN LINE FLOW TRANSMITTER associated with the CRDM Cooler inside containment that (1)

In the event of degraded CRDM Cooling Water System capacity, the system (2) have the availability to be manually aligned to the Industrial Cooling Water System, in accordance with SOP-i 25, INDUSTRIAL COOLING WATER.

A.

1) generates an IPCS alarm to alert operators of potential RCS leakage.

2) does B. i) generates an IPCS alarm to alert operators of potential RCS leakage.

2) does not C.

1) provides input to the RCS Leakrate Program to allow quantification of RCS leakage.

2) does D.

1) provides input to the RCS Leakrate Program to allow quantification of RCS leakage.

2) does not Saturday, May 16, 2015 10:53:12AM 56

57. Given the following plant conditions:

Time 1200:

100% power.

A review of calibration paperwork for Pressurizer Code Safety Valves was performed.

The lift setpoints were determined to be as follows:

2385 psig.

2430 psig 2485 psig Which ONE of the choices below answers both of the following questions in accordance with T.S. 3.4.2.2, REACTOR COOLANT SYSTEM

- OPERATING?

1) How many Pressurizer Code Safety Valves are currently OPERABLE?

2) Based on the given conditions, what is the earliest action required by T.S. 3.4.2.2, if any?

A.

1) 2

2) No action is required.

B.

1) 3

2) No action is required.

C.

1) 2

2) restore the Inoperable valve to OPERABLE status within 15 minutes.

D.

1) 2

2) restore the Inoperable valve to OPERABLE status within one (1) hour.

Saturday, May 16, 2015 10:53:12 AM 57

58. Given the following conditions:

Unit 1 is returning to power following a refueling outage.

Operators have taken the Reactor critical and have slowly raised power to 8%.

Intermediate Range N-35 experienced a loss of control power.

Which ONE of the choices following completes the statements below?

The Intermediate Range N-35 High Flux trip bistable is in a (1) condition and an automatic Reactor Trip _(2) occurred.

A.

1) tripped

2) has B.

1) tripped

2) has not C.

1) flQfl-tripped

2) has D.

1) flQfl-tripped

2) has not Saturday, May 16, 2015 10:53:12 AM 58

59. Which ONE of the choices below completes the following statements?

PT-446, TURBINE 1ST STAGE PRESSURE, (1) provide an input to an actuation circuit required by T.S. 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.

The PT-446 circuit (2) use an isolation amplifier to separate control functions and protection functions that utilize its output.

A.

1) does

2) does B.

1) does

2) does not C.

1) does not

2) does D.

1) does not

2) does not Saturday, May 16, 2015 10:53:12AM 59

60. Given the following plant conditions:

Mode 6.

A leak has begun on the suction of the in-service Spent Fuel Cooling Pump (at the 454 elevation).

IJ-7431, POOL LEVEL, and LI-7433, POOL LEVEL, both currently indicate 461 3 and slowly lowering.

Which of the choices below answer both of the following question?

1) Are both XCP-608 1-2, SFP LVL HI/LO, and XCP-609 1-2, SFP LVL HI/LO currently in alarm?

2) Which of the elevations listed below is closest to the expected level to which the Spent Fuel Pool will drain due to the leak?

ASSUME NO OPERATOR ACTIONS A.

1) No.

2) 454 B.

1) Yes.

2) 454 C.

1) No.

2) 460 D.

1) Yes.

2) 460 Saturday, May 16, 2015 10:53:12 AM 60

61. Given the following:

Unit 1 is in MODE 6 performing a core re-load.

The JOG PERMISSIVE switch is OFF.

Based on the given conditions, which ONE of the following would render the manipulator crane bridge and trolley inoperative simultaneously?

A. The trolley bypass is engaged.

B. The hoist is being operated or the gripper tube is down.

C. The Reactor Building Upender is in the vertical position (FRAME UP).

D. The Manipulator load cell indicates 100 pounds more than the fuel assembly.

Saturday, May 16, 2015 10:53:12AM 61

62. Given the following plant conditions:

Time 1000:

100% power.

Charging Pump A is in service.

Time 1010:

Pressurizer level is falling.

VCT level is rising.

XCP-614, Annunciator Point 5-1, CHG LINE FLO HI/LO is in alarm.

XCP-614, Annunciator Point 5-2, SL WTR INJ FLOW LO is in alarm.

XCP-613, Annunciator Point 1-4, REGEN HX LTDN OUT TEMP HI is in alarm.

Which ONE of the following events has occurred to cause the conditions at 10:10?

A. Charging Pump A has tripped.

B.

FCV-122, CHG FLOW, has failed CLOSED.

C. PCV-145, LO PRESS LTDN, has failed OPEN.

D. A spurious automatic charging pump suction transfer to the RWST has occurred.

Saturday, May 16, 2015 10:53:12AM 62

63. Which ONE of the following buses directly provides power to Service Water Pump C

(XPP-0039C) when aligned to Service Water Loop B per SOP-i i 7, SERVICE WATER SYSTEM?

A. 7200Vbus lEA B. 7200VbuslEB C. 7200VbusiDB D. 7200VbuslC Saturday, May 16, 2015 10:53:12 AM 63

64. Given the following plant conditions:

100% power.

A failure of the in-service air compressor, XAC-3A occurs.

Instrument Air pressure is currently 88 psig and lowering.

All Main Steam Isolation Valves are fully open.

No Feedwater Flow Control valve is closed.

No other significant erratic valve operation is noted.

Which ONE of the following completes the below statements?

Instrument Air Header Pressure (1) lowered to less than automati st

)

setpoint of the Standby Instrument Air Compressor. (,fr 3i3)4i If valve positions do not change, the Reactor is required to be manually tripped as soon as Instrument Air Header pressure is LESS THAN (2) psig in accordance with AOP-220.1, LOSS OF INSTRUMENT AIR.

ASSUME NO OPERATOR ACTIONS A.

1) has

2) 50 B.

1) has not

2) 50 C.

1) has

2) 55 D.

1) has not

2) 55 Saturday, May 16, 2015 10:53:12AM 64

65. Given the following plant conditions:

Time 10:00:

100% power.

Neither the electric, nor the diesel fire pump is running.

Fire header pressure is 112 psig.

Time 10:05:

A plant fire is reported.

A Reactor Trip has been initiated.

Fire header pressure is 98 psig.

Time 10:05 and 15 seconds:

XSWi 02 is deenergized.

Fire service water header pressure is 90 psig.

Time 10:06:

XSW1C2 is still deenergized.

Fire service water header pressure is 90 psig.

Which ONE of the choices below completes the following statements?

At Time 10:05:00, the electric fire pump (1) running.

At Time 10:06:00, the diesel fire pump (2) running.

ASSUME NO OPERATOR ACTIONS A.

1) is

2) is B.

1) is not

2) is C.

1) is

2) 5fl2 D.

1) is not

2) is Saturday, May 16, 2015 10:53:12 AM 65

66. Given the following plant conditions:

Unit 1 is in a refueling outage.

Non-licensed operators report that they are unable to complete a Lockout-Tagout of a condensate isolation valve in the gland sealing system because the valve is leaking by.

In accordance with OAP-100.5, GUIDELINES FOR CONFIGURATION CONTROL AND OPERATION OF PLANT EQUIPMENT, permission is obtained from the Shift Supervisor (SS) to use the appropriate sized valve wrench, the leakage is stopped, and the tagout is completed.

Based on the given conditions, operators are required to enter the affected valve in the (1)

Log.

In addition to entering the affected valve in the above log, operators (2) also required to generate both a Work Order and a Condition Report describing the details surrounding the need to use a valve wrench on the affected valve.

Which ONE of the following choices completes the above statements, in accordance with OAP-1 00.5?

A.

1) R&R

2) are B.

1) R&R

2) are not C.

1) Equipment Misalignment Status

2) are D.

1) Equipment Misalignment Status

2) are not Saturday, May 16, 2015 10:53:12AM 66

67. Given the following plant conditions:

Mode 6.

Fuel assemblies are being moved into the Reactor Vessel.

Which ONE of the following conditions would not require stopping the reload of fuel assemblies into the reactor vessel in accordance with V.C. Summer Technical Specifications?

A. The result of the latest RCS boron sample is 1900 ppm.

B. The Excore Nuclear Instrument Audio Countrate circuit is lost.

C. The NROATC is the only licensed operator in the Control Room.

D. Communications are lost between the Control Room and the Reactor Building.

Saturday, May 16, 2015 10:53:12 AM 67

68. Given the following conditions:

100% power for the last 45 days.

A NROATC has worked the following schedule:

NOTE: The times listed below do not include turnover time.

4/23 to 4/26 OFF 4/270700 to 1900 4/28 OFF 4/290700 to 1900 4/30 0700 to 2030 5/1 0600 to 1900 5/2 OFF 5/31000 to 2100 5/40400 to 1730 5/5 OFF No special accommodations were granted to the NROATC.

In accordance with SAP-152, FATIGUE MANAGEMENT AND WORK HOUR LIMITS, the t((t work hour limit reached by the NROATC was at Which ONE of the following completes the statement above?

A. 0600 on 5/1 B. 19000n5/1 C. 0400 on 5/4 D. 0900 on 5/4 Saturday, May 16, 2015 10:53:12 AM 68

69. Given the following Conditions:

MODE3 Rod drop time testing is in progress in accordance with Surveillance 4.1.3.4 to satisfy T.S. LCO 3.1.3.4, ROD DROP TIME.

Which ONE of the choices below completes the following statement?

In accordance with the TS 3.1.3.4., ROD DROP TIME, the rod drop time must be met with TAVG greater than or equal to (1) and a minimum of (2)

Reactor Coolant Pumps operating.

A.

1) 500°F

2) two (2)

B.

1) 551 °F

2) two (2)

C.

1) 500°F

2) three (3)

D.

1) 551 °F

2) three (3)

Saturday, May 16, 2015 10:53:12AM 69

70. Given the following plant conditions:

Mode 3.

A Lockout-Tagout is being hung on the A Feedwater Booster Pump for maintenance.

A Red Danger Tag has just been attached to the pump motor breaker.

Which ONE of the choices below completes the following statements?

In accordance with SAP-201, EQUIPMENT TAGGING AND LOCKOUT-TAGOUT, a (1) was placed on the A Feedwater Booster Pump control switch in the Control Room.

In accordance with OAP-1 00.5, GUIDELINES FOR CONFIGURATION CONTROL AND OPERATION OF PLANT EQUIPMENT, the next Red Danger Tag that is required to be hung, after the pump motor breaker, will be on the (2)

A.

1) Hold tag

2) discharge valve.

B.

1) Hold tag

2) suction valve.

C.

1) Caution tag

2) discharge valve.

D.

1) Caution tag

2) suction valve.

Saturday, May 16, 2015 10:53:12AM 70

71 Which ONE of the choices below completes the following statements?

EOP-1.0, E-0 REACTOR TRIP OR SAFETY INJECTION, requires that operators reduce Control Room emergency ventilation to one train in operation within a MAXIMUM of JL of actuation.

Control Room emergency ventilation is designed such that access to and occupancy of the Control Room under accident conditions and for the duration of the accident does not result in personnel exposures in excess of a maximum f

whole body.

A.

1) 30 minutes

2) 10 Rem B.

1) 30 minutes

2) 5 Rem C.

1) one hour

2) 10 Rem D.

1) one hour

2) 5 Rem Saturday, May 16, 2015 10:53:12AM 71

72. Given the following plant conditions:

Operators will be performing work in the room containing B RHR Heat Exchanger on AB-412.

Which one of the choices below completes the following statements?

The highest level of contamination in the room in which the work will be performed, based on survey readings, was found (1)

The highest contact reading indicated in the room in which work will be performed, based on survey readings, is _(2)........ mrem/hr.

REFERENCE PROVIDED A.

1) by the end of the B RHR heat Exchanger closest to the entrance.

2) 175 B.

1) by the end of the B RHR heat Exchanger closest to the entrance.

2) 40 C.

1) on piping in the area of AB 12-05 farthest from the entrance to the room.

2) 175 D.

1) on piping in the area of AB 12-05 farthest from the entrance to the room.

2) 40 Saturday, May 16, 2015 10:53:12AM 72

CD C

CD C,0 CD C)

CDa)

C.

p CD CDC D

CC Cl, D

3 C

CD ci, to 0

CD Ci)

CD D0 CDC-t%)0000 r.)000 (10 C0 rJ000 U,

A C0 0

z z

z A

C C

C 0

0 a)3 z

0) 0

-00 C,

3 z

> z z z N)

c.

0 C

0 C,0 Cz z

I)

CD Ci)

(C C,0 C

S.

-I 0.

C C

C-f)

CD 0,

0)

Co C.)

C.)

C,)

CD z

-I 3

CD r.)

C 0

In

-1 CD CD C0 CD C

CD 0.

C z

-I CD C.)

CD CD CD.

C I

C,)

I-CD a)

C.

CD 6

C 3

CD C.)

C,,

Cc 0)

CD I-)

Co 0)

CD N)

Co CD 0) 0)

Co 0)

C C.)

73. Given the following plant conditions:

Time 03:45 A LOCA has occurred.

Time 0400:

Containment radiation level is 1200 R/hr and increasing slowly.

Containment pressure is 2.8 psig and increasing.

IPCS is not available, and engineering can not determine integrated dose.

Time 0600:

Containment radiation level is 900 R/hr and decreasing slowly.

Containment pressure peaked at 12 psig, and is now 2.8 psig and decreasing.

IPCS is not available, and engineering can not determine integrated dose.

Which ONE of the choices below complete the following statements in accordance with OAP-1 03.4, EOP/AOP USERS GUIDE?

At 0400, adverse containment setpoint values (1) required to be used in the Emergency Operating Procedures (EOPs) for designated parameters.

At 0600, adverse containment setpoint values (2) required to be used in the EOPs for designated parameters.

A.

1) are

2) are B.

1) are

2) are not C.

1) are not

2) are D.

1) are not

2) are not Saturday, May 16, 2015 10:53:12 AM 73

74. Given the following plant conditions:

The control room was evacuated due to a fire in the Main Control Board.

The crew is implementing FEP-4.O, CONTROL ROOM EVACUATION DUE TO FIRE.

The reactor has been tripped.

All actions of FEP-4.O, Enclosure B, DUTIES OF THE REACTOR OPERATOR are complete.

The Control Room Evacuation Panel (CREP) has been manned.

Based on the given conditions, which ONE of the following statements identifies how RCS pressure will be controlled in accordance with FEP-4.O?

A. Group 1 pressurizer backup heaters will be cycled locally at XSW 1 DA.

B. Group 2 pressurizer backup heaters will be cycled locally at XSW 1 DB.

C. Group 1 pressurizer backup heaters will be continuously energized at XSW 1 DA.

D. Group 2 pressurizer backup heaters will be continuously energized at XSW I DB.

Saturday, May 16, 2015 10:53:12AM 74

75. Initial conditions:

A SITE AREA EMERGENCY (SAE) has been declared.

The time for the initial notifications to all appropriate offsite agencies is 1000.

Current conditions:

At 1030, the Emergency Director (ED) declared an upgrade to a General Emergency.

Which ONE of the choices below completes the following statements?

Based on the current conditions, the next notification to be provided to state and local governments is required by jJ EPP-02, COMMUNICATION AND NOTIFICATION, states that the Emergency Response Data System (ERDS) must be activated as soon as possible, but not greater than one hour from the declaration of an or higher emergency classification.

A.

1) 1045

2) Unusual Event B.

1) 1045

2) Alert C.

1) 1100

2) Unusual Event D.

1) 1100

2) Alert Saturday, May 16, 2015 10:53:12 AM 75

76. Initial conditions:

100% power initially.

A Pressurizer Code Safety Valve lifts and remains stuck in the full open position.

An automatic Reactor Trip and Safety Injection occur.

The crew has stopped all RCPs.

Current conditions:

The crew has entered EOP-2. 1, ES-i.2 POST-LOCA 000LDOWN AND DEPRESSURIZATION, and has just completed step 4 to check intact SG levels.

All SG narrow range levels are 50%.

RCS subcooling is 20°F.

The Pressurizer is water solid at 1000 psig.

The condenser is available for steam dumps.

Based on the current conditions, which ONE of the following identifies the next required action, and the reason for that action, in accordance with EOP-2.i and its associated background document?

A.

Initiate a RCS cooldown at the maximum achievable rate with Bank 1 Steam Dump Valves fully open to quickly establish conditions for reducing ECCS injection.

B.

initiate a RCS cooldown at less than 100 °F/hr, to establish the subcooling necessary for reducing ECCS injection.

C. Restart RCP A, to mix the RCS to a uniform temperature and prevent localized boron stratification before initiation of a RCS cooldown.

D. Restart RCP A, to ensure that normal PZR spray is available for RCS pressure control before initiation of a RCS cooldown.

Saturday, May 16, 2015 10:53:12 AM 76

77. Which ONE of the choices below completes the following statements?

The Anticipated Transient Without SCRAM (ATWS) Mitigation System Actuation Circuitry (AMSAC) system is specifically designed to mitigate the consequences of the (1) accident.

This accident (2) within the design basis as contained in the chapter 15 accident analysis in the V.C. Summer Final Safety Analysis Report (FSAR).

A.

1) Complete Loss of Normal FeedwaterATWS.

2) is not B.

1) Complete Loss of Normal Feedwater ATWS.

2) is C.

1) Complete Loss of External Electrical Load ATWS.

2) is not D.

1) Complete Loss of External Electrical Load ATWS.

2) is Saturday, May 16, 2015 10:53:12AM 77

78. Given the following plant conditions:

All offsite power (115KV and 230KV) was lost.

A and B Emergency Diesel Generators failed to start.

Buses 1 DA and 1 DB read 0 volts.

EOP-6.0, LOSS OF ALL ESF AC POWER is in progress.

The CRS is reading the alternative action for step 29 of EOP-6.0, Continue to control RCS conditions and monitor plant status, Spent Fuel Pool (SFP) level is reported to be 460 ft 6 inches and lowering.

Which ONE of the choices below completes the following statements?

In order to establish makeup to the SFP the first procedure operators are required to use (in parallel with EOP-6.0) is (1)

If makeup to the SFP can not be established using the first procedure, the second procedure operators are required to use (in parallel with EOP-6.0) to establish makeup to the SFP is (2)

A.

1) an Attachment of EOP-6.0

2) a Section of SOP-123, SPENT FUEL COOLING SYSTEM B.

1) anAttachmentofEOP-6.0

2) a Section of BDMG-1.0, SPENT FUEL POOL MAKEUP AND SPRAY STRATEGIES C.

1) a Section of SOP-123, SPENT FUEL COOLING SYSTEM

2) a Section of BDMG-1.0, SPENT FUEL POOL MAKEUP AND SPRAY STRATEGIES D.

1) a Section of SOP-123, SPENT FUEL COOLING SYSTEM

2) an Attachment of EOP-6.0 Saturday, May 16, 2015 10:53:12 AM 78

79. Given the following plant conditions:

Time 1800:

100% power.

Diesel Generator B is tagged out for maintenance.

Battery charger XBC iA-i B is being aligned to battery XBA1A.

Time 2200:

The following alarms come in on XCP-636:

DGALOSSOFDC TRAIN A BATT CHGR TRBL XBC 1AJ1A-1 B DC SYS TRAIN A GND TRBL DC SYS OVRVOLT/UNDRVOLT 7KV ESF CHAN A LOSS OF DC 480V ESF CHAN A LOSS OF DC Based on the conditions at 2200, which ONE of the following Tech Spec conditions is applicable and requires the earliest entry into Cold Shutdown?

REFERENCE PROVIDED A. TS3.0.3 B. TS 3.8.1.1, condition b C. TS 3.8.1.1, condition c D. TS 3.8.1.1, condition e Saturday, May 16, 2015 10:53:12 AM 79

79 314.8 ECWICAL POWER SYSTEMS 3/4.8.1 A.C SOURCES OPERATING LIMfl9NG CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. eleduical power sources shall be OPERA.BLE:

a.

Two physically independent circuits between the offsite transmission network and the onsite Class 1 E distribution system, and b.

Two separate and independent Emergency Diesel Generators (EDG), each with:

I.

A ite day fuel tank onffiining a minimum.ume of 360 gallons of

fuel, 2.

A separate fuel storage system containing a minimum volume of 48,500 gallons of fuel, and 3.

A separate fuel transfer pump.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

a.

With one offsite circuit of 3.8.1.1.a inoperable:

1.

Demonstrate the OPERABILITY of the remaining offsiteA.C. sources by fl performing Surveillance Requirement 4.8.1.1.1 withIn 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter, and 2.

II either EDS has not been successfully tested within the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , demonstrate Its OPERABILITY by performing Surveillance Requirement 4.8.1.1.2.a.3 separately for each such EDS within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless the diesel Is already operating, and 3.

Restore the offsite circuit to OPERABLE status withIn 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With one EDG of 3.8.1.1.b Inoperable:

1.

Demonstrate the OPERABILITY of the A.C. offsite sources by performing Surveillance Requirement 4.8.1.1.1 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter, and 2.

U the EDG became inoperable due to any cause other than prepianned preventive maintenance or testing:

a) determine the OPERABLE EDG is not inoperable due to a common cause failure within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or b) demonstrate the OPERABILITY of the remaining EDG by performing Surveillance Requirement 4.8.1.1.2.a.3 within 24

hours, and Completion of Action b.2 is required regardless of when the inoperable EDG is restoredlo OPERABILITY.

SUMMER-UNIT 1 3/4 8-1 Amendment No. 50 r

77

84. 08. 150. 164

ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION ACTION: (Continued) 3.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , verify that required systems, subsystems, trains, components and devices that depend on the remaining EDG as a source of emergency power are also OPERABLE and in MODE 1, 2, or 3, that the Turbine Driven Emergency Feed Pump is OPERABLE.

If these conditions are not satisfied within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4.

Restore the EDG to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , unless the following condition exists:

a)

The requirement for restoration of the EDG to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months may be extended to 14 days if the Alternate AC (AAC) power source is or will be available within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , as specified in the Bases, and b)

If at any time the AAC availability cannot be met, either restore the AAC to available status within the remainder of the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in 4.a (not to exceed 14 days from the time the EDG originally became inoperable), or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c.

With one offsite circuit and one EDG inoperable:

1.

Demonstrate the OPERABILITY of the remaining offsite A.C. source by performing Surveillance Requirement 4.8.1.1.1 within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter, and 2.

If the EDG became inoperable due to any cause other than preplan ned preventative maintenance or testing:

a) determine the OPERABLE EDG is not inoperable due to a common cause failure within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or b) demonstrate the OPERABILITY of the remaining EDG by performing Surveillance Requirement 4.8.1.1.2.a.3 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , and 3.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , verify that required systems, subsystems, trains, components and devices that depend on the remaining EDG as a source of emergency power are also OPERABLE and in MODE 1, 2, or 3, that the Turbine Driven Emergency Feed Pump is OPERABLE.

If these conditions are not satisfied within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4.

Restore one of the inoperable sources to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , and 5.

Restore the other A.C. power source (offsite circuit or diesel generator) to OPERABLE status in accordance with the provisions of Section 3.8.1.1 Action Statement a. or b.,

as appropriate, with the time requirement of that Action Statement based on the time of initial loss of the remaining inoperable A.C. power source.

Completion of Action c.2 is required regardless of when the inoperable EDG is restored to OPERABILITY.

SUMMER

- UNIT 1 3/4 8-2 Amendment No. 77, 98, 16l, 178

ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION (Coriti nued)

ACTION: (Continued) ci.

With two of the required offsite A.

C. circuits inoperable:

1.

Demonstrate the OPERABILITY of the two LOGs by sequentially performing Surveiflance Requirement 4.8.LL2.a.3 on both

.wjthin8hours,unless the EDGs are alrea operating, and 2.

Restore one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

3.

Following restoration of one offsite source, follow Action Statement a. with the time requirement of that Action Statement based on the time of initial loss of the remaining inoperable offsite A.C. circuit.

a.

With two of the above required EDGs inoperable:

1.

Demonstrate the OPERABILITY of two offsite 1 tC. circuits by performing Surveillance Requirement 4.B.1.1.1 within one bour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter, and 2.

Restore one of the inoperable LOGs to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

3.

Following restoration of one LOG, follow Action Statement b.

with the time requirement of that Action Statement based on the time of initial loss of the remaining inoperable diesel generator.

SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system shall be determined OPERABLE at least once per 7 days by verifying correct breaker alignment and indication of power availability for each Class 1E bus and its preferred offsite power source.

0 SUWIER

- UNIT 1 3/4 8-2a ANENDMENT NO.

77 98 4

80. Given the following plant conditions:

Time 0100 100% power initially.

An automatic Safety Injection (SI) occurred.

A 51 BX Lockout occurs on bus 1 DA.

Time 0115:

The crew transitioned from EOP-2.0 to EOP-2.5, LOCA OUTSIDE CONTAINMENT.

RCS wide range pressure is 900 psig, lowering.

Time 0120:

The crew closed valve MVG-8888B, RHR LP B TO COLD LEG, as directed by EOP-2.5.

RCS wide range pressure is 1000 psig, rising.

Which one of the choices below completes the following statements?

In accordance with the EOP-2.5 background document, a break in the (1) piping is an event with high Probabilistic Risk Assessment (PRA) significance and is analyzed as a basis for that procedure.

For the conditions at time 0120, operators will transition to (2)

A.

1) RHR Pump suction

2) EOP-2.0, LOSS OF PRIMARY OR SECONDARY COOLANT B.

1) RHR Pump suction

2) EOP-2.4, LOSS OF EMERGENCY COOLANT RECIRCULATION C.

1) CVCS Normal Letdown

2) EOP-2.0, LOSS OF PRIMARY OR SECONDARY COOLANT D.

1) CVCS Normal Letdown

2) EOP-2.4, LOSS OF EMERGENCY COOLANT RECIRCULATION Saturday, May 16, 2015 10:53:12AM 80

81. Given the following plant conditions:

100% power initially.

A total loss of Main Feedwater occurred.

All EFW pumps failed to start.

EOP-15.0, RESPONSE TO LOSS OF SECONDARY HEAT SINK is in progress.

Bleed and Feed cooling is in progress.

EFW flow using the Turbine Driven EFW Pump has been established.

Core exit TC temperatures and RCS THOT temperatures are both decreasing.

Which ONE of the choices below answers both of the following questions?

1) In accordance with EOP-15.0, what is a parameter that must be met to allow operators to secure from Bleed and Feed?

2) Based on the given conditions, in what procedure will operators close Pressurizer PORVs and check SI Termination Criteria?

NOTE: EOP-2.0 is LOSS OF REACTOR OR SECONDARY COOLANT A.

1) 26% Narrow Range Level in one Steam Generator.

2) EOP-2.0.

B.

1) 26% Narrow Range Level in one Steam Generator.

2) EOP-15.0.

C.

1) At least 450 gpm of EFW flow.

2) EOP-2.0.

D.

1) At least 450 gpm of EFW flow.

2) EOP-15.0.

Saturday, May 16, 2015 10:53:12 AM 81

82. Given the following plant conditions:

Time 1200:

Plant startup in progress in Mode 2.

Reactor power was stable at 4.0%.

Operators noted the following Control Bank D DRPI indications.

H02 E08 H14 P08 F06 FlO K10 K06 96 84 96 102 84 96 96 102 Control Bank D GROUP DEMAND COUNTERs indicate 100 steps.

Rod Control Urgent Failure alarm is !1.Q lit.

Time 1230:

Rod Control electrical troubleshooting is complete with no problems reported.

Operators attempted to move Control Bank D rods.

Rod E08 did not move.

All other Control Bank D Rods moved.

Operators realigned Control Bank D rods to the following positions:

H02 E08 H14 P08 F06 FlO K10 K06 90 84 90 96 96 90 90 96 Control Bank D GROUP DEMAND COUNTERs now indicates 94 steps.

Which ONE of the choices below completes the following statements in accordance with TS LCO 3.1.3.1, MOVABLE CONTROL ASSEMBLIES

- GROUP HEIGHT?

At Time 1200, TS LCO 3.1.3.1 jJ require a plant shutdown to HOT STANDBY.

At Time 1230, TS LCO 3.1.3.1 f2) require a plant shutdown to HOT STANDBY.

REFERENCE PROVIDED A.

1) did

2) does B.

1) did

2) does not C.

1) did fl2

2) does D.

1) did not

2) does not Saturday, May 16, 2015 10:53:12AM 82

82 REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMiTING CONDITION FOR OPERTION 3.1.3.1 Afl full length (shutdown and control) rods which are inserted in the core shall be OPERABLE and positioned within

+/- 12 steps (indicated position) of their group stpcounter demand position.

APPLICABILITY:

MODES 1* and 2*

ACTION:

a.

With one or more full length rods inoperable due to t:qg immovable as a result of excessive friction or mechanical or known to be untrippable, determine that the SHUTDOWN MARGiN require ment of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With more than one full length rod misaligned from the group step counter demand position by more than z 12 steps (indicated position),

be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With more than one full length rod inoperable due to a rod control urgent failure alarm or obvious electrical problem in the rod control system for greater than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , be in HOT STANDBY within the fol lowing 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months sb d.

With one full length rod inoperable due to causes other than addressed by ACTION a., above, or misaligned from its group step counter demand height by more than

+/- 12 steps (indicated position),

POWER OPERATION may continue provided that within one hour either:

1.

The rod is restored to OPERABLE status within the above alignment requirements, or 2.

The remainder of the rods in the group with the inoperable rod are aligned to within

+/- 12 steps of the inoperable rod within one hour while maintaining the rod sequence and insertion limits specified in the CORE OPERATING LIMITS REPORT (COLR); the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, or 3.

The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that;

See Special Test Exceptions 3.10.2 and 3.10.3.

SUMMER

- UNIT 1

3/4 114 Amendment No. fl, gg

REAC11VITY CONTROL SYSTEMS LIMmNG CONDfl1ON FOR OPERAI1ON (Continued) a)

A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previotsly analyzed results of these accidents remain valid for the duration of operation under these conditions; b)

The SHUTDOWN MARGIN requirement of SpecifIcation 3.1.1.1 s

determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c)

A core power distribution measurement is obtained and F<

2 (z) and p are verified to be within their limils within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and d)

The ThERMAL POWER level is reduced to less than or equal to 75% of RATED ThERMAL POWER within the next hour and within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the high neutron flux trip setpoint is reduced to less than or equal to 85% of RATED ThERMAL POWER.

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each full length rod shall be determined to be within the group demand hmit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time inteiva when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each full length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 31 days.

SUMMER - UNIT 1 3/41-15 Amendment No.

142

83. Given the following plant conditions:

A LOCA is in progress.

The crew is initiating RCS cooldown in accordance with EOP-2. 1, POST-LOCA COOLDOWN AND DEPRESSURIZATION.

The Shift Supervisor has completed all required local, state, and NRC notifications jy for the initial Emergency Classification.

The Shift Supervisor is now referencing NL-122 Enclosure A, MASTER LIST OF REPORTING REQUIREMENTS.

A FOUR (4) hour reporting requirement to the Nuclear Regulatory Commission (NRC) has been identified.

Which ONE of the choices below identifies the additional requirement(s), if any, for ONE(1) hour and EIGHT (8) hour reports to the Nuclear Regulatory Commission?

NOTE:

Do not consider any required updates for the Emergency Classification in effect.

REFERENCE PROVIDED ONE hour report EIGHT hour report A.

not required required B.

not required

.required C.

required required D.

required

!2.Q required Saturday, May 16, 2015 10:53:12 AM 83

NL-122 ENCLOSURE A

83 PAGE3OF39 REVISION 5 MASTER LIST OF REPORTING REQUIREMENTS ID # I REFERENCE REPORT! SUBJECT CONTENT REPORT TIME I METHOD RECIPIENT 4

Exceeding any Technical Specification Critical operation of the plant shall not be Telephone notification within NRC

- ENS or Safety Limit, resumed until authorized by the NRC.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Operations Ctr.

(301) 816-5100 Tech. Spec. 6.7.1

Written report to be reviewed byVPNPO, PSRC, and NSRC.

Notify within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months VPNO and NSRC Safety Limit Violation Report to NRC

- DCD be submitted within 14 days.

1-5 Any event where the following exposures Telephone notification within NRC

- ENS or occurred:

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of event.

Operations Ctr.

(301) 816-5100 1 OCFR2O.2202(a)

1. Exposure of the whole body of 25 10CFR2O.2203(a)(1) rems of radiation, eye equivalent dose LER within 30 days.

NRC

- DCD of 75 rems, shallow dose to skin or (A copy of the LER submitted to extremities of an individual of 250 the NRC reporting personal rads; or, exposure shall be provided to each individual involved per the

2. Release of radioactive material, inside requirements of 10CFR2O.2205) or outside of a restricted area, so that, had an individual been present for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the individual could have received an intake 5 times the annual limit on intake.

1-6 Theft or Unlawful diversion of special Reportable Safeguard Event.

Telephone notification within NRC

- ENS or nuclear material.

Security Team Leader to substantiate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Operations Ctr.

IOCFR73 71b1 event, initiate response and address (301) 816-5100 R

reportability with Operations Shift App. G I(a)(1)

Supervisor in accordance with LER within 60 days NRC

- DCD SPP-118, Section 5.3.3 A.

Any event in which there is reason to believe that a person has committed or caused, or attempted to commit or cause, or has made a credible threat to commit or cause.

MASTER LIST OF REPORTING REQUIREMENTS NL-122 ENCLOSURE A PAGE 4 OF 39 REVISION 5 ID#/REFERENCE REPORT/SUBJECT CONTENT REPORTTIMEIMETHOD RECIPIENT 1-7 Radioactive material package received Reference 10CFR71.87(i).

Immediately notify:

with removable beta-gamma emitting

1. Final delivery carrier, and Reference receipt radionuclide contamination on external paperwork.

10CFR2O.1906(d)(1) 2 surfaces in excess of 0.01 iCi/cm (2200 DPM/100cm 2

). 220 DPM/100cm 2 for all

2. NRC Region II by telephone NRC

- Region II other alpha emitters.

and telegram, mailgram, or facsimile.

-8 Radioactive material package received Reference 10CFR71.47.

Immediately notify:

with radiation at the external surface in

1. Final delivery carrier, and

1. Reference receipt 10CFR2O 1906d2 excess of 200 mRem/hr, orat2 meters paperwork

from external surface in excess of 10

2. NRC Region II by telephone

2. NRC

- Region II mRem/hr.

and telegram, mailgram, or facsimile.

1-9 Significant physical damage to a power Security Team Leader to substantiate Telephone notification within NRC - ENS or reactor or any facility possessing Special event, initiate response and address 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of discovery.

Operations Ctr.

10CFR73 71 Nuclear Material (SNM) or its equipment reportability with Operations Shift (301) 816-5100 or carrier equipment transporting nuclear Supervisor in accordance with Appendix G l(a)(2) fuel or spent nuclear fuel, or to the SPP-1 18, Section 5.3.3 A.

LER within 60 days.

NRC

- DCD nuclear fuel or spent nuclear fuel a facility or carrier possesses.

These incidents shall also be reported if an attempt or credible threat to commit or cause these events has been made.

Fitness for Duty events shall be reported under 10CFR26.73 (Sec. P-8).

i-io Interruption of normal operation of a Security Team Leader to substantiate Telephone notification within NRC

- ENS or licensed nuclear power reactor through event, initiate response and address 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of discovery.

Operations Ctr.

10CFR73 71 the unauthorized use of or tampering reportability with Operations Shift (301) 816-5100 with its machinery, components, or Supervisor in accordance with Appendix G I(a)(3) controls including the security system.

SPP-118, Section 5.3.3 A.

LER within 60 days.

NRC

- DCD These incidents shall also be reported if an attempt or credible threat to commit or cause these events has been made.

MASTER LIST OF REPORTING REQUIREMENTS NL-122 ENCLOSURE A PAGE 11 0F39 REVISION 5 ID#/REFERENCE REPORT/SUBJECT CONTENT REPORTTIME/METHOD RECIPIENT E-1 1 OCFR50.72 (b)(3)(ii)(A) & (B)

Any event or condition that results in:

(A) The condition of the nuclear power plant, including its principal safety barriers being seriously degraded; or (A) This criterion applies to material (e.g., metallurgical or chemical) problems that cause abnormal degradation of or stress upon the principal safety barriers (i.e., the fuel cladding, RCS pressure boundary, or the containment).

(1)

Fuel cladding failures in the reactor, or in the storage pool, that exceed expected values, or that are unique or widespread, or that are caused by unexpected factors.

(2)

Welding or material defects in the primary coolant system, which cannot be found acceptable under ASME Section Xl, IWB-3600 orlWB-3410-1.

(3)

Serious steam generator tube degradation. Tube degradation is considered serious only if either the steam generator structural integrity or accident-induced leakage performance criteria are not met.

(Reference NUREG 1022 page 25)

(4)

Low temperature over pressure transients in which the pressure-temperature relationship violates pressure-temperature limits derived from 10 CFR 50, Appendix G (e.g., TS pressure-temperature curves).

(5)

Loss of containment function or integrity, including containment leak rate tests in which the total containment as-found, minimum-pathway leak rate exceeds limits in TS.

Telephone notification within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

NRC

- ENS or Operations Ctr.

(301) 816-5100

MASTER LIST OF REPORTING REQUIREMENTS NL-122 ENCLOSURE A PAGE 12 OF 39 REVISION 5 ID#/REFERENCE REPORT/SUBJECT CONTENT REPORTTIMEIMETHOD RECIPIENT E-1 Continued (B) The nuclear power plant being in an (B)

Engineering judgment and LER within 60 days.

NRC

- DCD unanalyzed condition that experience can be used to determine 10CFR5O 73 significantly degrades plant whether an unanalyzed condition

\\

1 2f 1

A fB safety.

existed.

It is not intended that this

)\\R paragraph apply to minor variations in individual parameters, or to problems concerning single pieces of equipment. Reference Page 26 to NUREG 1022 for additional guidance. The level of significance of the discussed cases generally corresponds to the inability to perform a required safety function.

MASTER LIST OF REPORTING REQUIREMENTS NL-122 ENCLOSURE A PAGE 13 OF 39 REVISION 5 E-2 1 0CFR50.72(b)(3)(iv)(A) 1 OCFR50.73(a)(2)(iv)

Note: Reference MLRR F-2 for possible 4-hour telephone notifications on ECCS and RPS actuations.

Any event or condition that results in valid actuation of any of the following systems:

(1)

Reactor protection system (RPS) including: Reactor scram and reactor trip.

(2)

General containment isolation signals affecting containment isolation valves in more than one system or multiple MSIVs.

(3)

Emergency core cooling systems (ECCS) including: High-head injection systems and the low pressure injection function of residual (decay) heat removal systems.

(4)

Emergency or auxiliary feedwater system (EFW).

(5)

Containment heat removal and depressurization systems, including containment spray and fan cooler systems.

(6)

Emergency diesel Generators (EDG).

(7)

Emergency service water systems that do not normally run and that serve as ultimate heat sinks.

System actuations under this part are not reportable when:

(1)

The actuation resulted from and was a part of a pre-planned sequence during testing or reactor operation; or (2)

The actuation was invalid and; (i)

Occurred while the system was properly removed from service; or (ii)

Occurred after the safety function had been already completed.

Note:

In the case of an invalid actuation, other than actuation of the RPS when the reactor is critical, the NRC allows a telephone notification within 60 days in lieu of an LER.

Reference 10CFR50.73(a)(1).

Telephone notification within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . (Note: Telephone notification for Report/Subject item (7) is not required under 10CFR5O.72. The actuation would still require a written report within 60 days.)

Note: Refer to MLRR T-1 7 or T-1 8 for possible 90-day Special Report.

ID#IREFERENCE REPORT/SUBJECT CONTENT REPORTTIMEIMETHOD RECIPIENT NRC

- ENS or Operations Ctr.

(301) 816-5100 NRC

- DCD LER within 60 days.

84. Given the following plant conditions:

Reactor trip occurred.

FOP-i.3, NATURAL CIRCULATION COOLDOWN in progress.

The crew is performing the actions of step 4 of EOP-1.3: Ensure two CRDM Cooling Fans are running.

Only ONE (1) CRDM Cooling Fan is available and running Which ONE of the choices below completes the following statements?

In accordance with the NOTE for step 5, the limits of (1)

(see titles below) should be maintained.

-, RCS PIT LIMITS DURING NATURAL CIRCULATION COOLDOWN WITH CRDM FANS

-, RCS PIT LIMITS DURING NATURAL CIRCULATION COOLDOWN WITHOUT CRDM FANS The basis of maintaining the cooldown within the limits of the attachment is to prevent (2)

A.

1) Attachment 2

2) voids from forming in the upper head B.

1) Attachment 2

2) a loss of required subcooling margin C.

1) Attachment 3

2) voids from forming in the upper head D.

1) Attachment 3

2) a loss of required subcooling margin Saturday, May 16, 2015 10:53:12 AM 84

85. Initial Conditions:

A large-break LOCA occurred.

RBCUs lA, 1 B and 2B failed to start automatically or manually.

B RB Spray failed to start automatically or manually.

Both RHR pump and RB Spray pump suctions failed to align to the RB Sump automatically or manually.

EOP-2.4, LOSS OF EMERGENCY COOLANT RECIRCULATION was in progress.

RB Pressure was 27 psig and rising slowly.

Operators stopped the A RB Spray Pump in accordance with EOP-2.4.

Current Conditions:

Operators entered EOP-17.0, RESPONSE TO HIGH REACTOR BUILDING PRESSURE due to Critical Safety Function status.

RB Pressure is 30 psig, rising slowly.

RWST Level is 8%, stable.

Which ONE of the choices below completes the following statements?

Based on the current conditions, operators (1) required to restart the A RB Spray pump in accordance with EOP-17.0.

In accordance with the background document for EOP-17.0, if an additional RBCU becomes available, it will be started in slow speed instead of fast speed (2) under higher density accident atmospheric conditions.

A.

1) are

2) to prevent damage to HEPA filters due to excess differential pressure B.

1) are not

2) to prevent damage to HEPA filters due to excess differential pressure C.

1) are

2) to prevent a motor overload due to stalling of the fan D.

1) are not

2) to prevent a motor overload due to stalling of the fan Saturday, May 16, 2015 10:53:12 AM 85

86. Given the following plant conditions:

The plant is shutdown with the RCS Temperature at 190°F.

RCP A is in service.

RCPs B and C are unavailable and tagged out.

RHR Loop A is OPERABLE and in service.

Steam Generator (S/G) Wide Rancie Levels are:

S/GA: 12%

S/G B: 8%

S/GC:6%

Which ONE of the choices below completes the following statements in accordance with T.S. 3.4.1.4.1, COLD SHUTDOWN

- LOOPS FILLED.?

Based on the given conditions, JL RHR loop(s) is(are) required to be OPERABLE to comply with T.S. 3.4.1.4.1.

Based on the given conditions, and in accordance with the bases for T.S. 3.4.1.4.1, one (1) RHR loop provide sufficient heat removal capability for removing decay heat.

A. 1)1

2) does B.

1) 1

2) does not C.

1) 2

2) does D.

1) 2

2) does not Saturday, May 16, 2015 10:53:12 AM 86

87. Given the following plant conditions:

Time 1200:

100% power.

COW is in the following system alignment:

COW Pump A in standby.

COW Pump C in service and aligned to the A COW Header Time 1205:

The Reactor Operator reports the following control board indications:

CCW Pump A red light is illuminated COW Pump C red light is illuminated XCP-601, 2-5, COW LOOP A ESSEN LOAD FLO LO is in alarm CC PUMP C DISCHARGE PRESSURE INDICATOR reads 40 psig Which ONE of the choices below completes the following statements?

A CCW pump (1) have started automatically at time 1205.

The auto-start feature based on low pressure _(2)_ required for COW train OPERABILITY in accordance with Technical Specification 3.7.3, COMPONENT COOLING WATER SYSTEM?

A.

1) should

2) is B.

1) should

2) is not C.

1) should not

2) is D.

1) should not

2) is not Saturday, May 16, 2015 10:53:12 AM 87

88. Initial conditions:

100% power initially.

A large-break LOCA occurred.

Train A SSPS failed to actuate automatically.

RB Pressure peaked at 16 psig and is lowering.

Actions of EOP-1.0, REACTOR TRIP/SAFETY INJECTION ACTUATION are complete.

Current conditions:

The crew is performing step 11 of EOP-2.0, LOSS OF REACTOR OR SECONDARY COOLANT to check if RB Spray should be stopped.

RB Pressure is currently 4 psig.

Train B of RB Spray fails to reset.

Which ONE of the choices below completes the following statements?

During performance of EOP-1.0, the crew (1) directed to refer to SOP-116, REACTOR BUILDING SPRAY SYSTEM, to ensure proper alignment of the RB Spray system.

Based on the current conditions, the crew will be directed by EOP-2.0 to refer to (2) to manually reset relays.

A.

1) was

2) SOP-112, SAFETY INJECTION SYSTEM B.

1) was NOT

2) SOP-112, SAFETY INJECTION SYSTEM C.

1) was

2) SOP-116 D.

1) was NOT

2) SOP-116 Saturday, May 16, 2015 10:53:12 AM 88

89. Given the following sequence of events:

A refueling outage was in progress in Mode 5.

All offsite power (115KV and 230K\\J) was lost.

A and B Emergency Diesel Generators failed to start.

Operators entered AOP-304.4, LOSS OF ALL ESF AC POWER WHILE SHUTDOWN (MODES 5 AND 6 AND DEFUELED).

Two actively licensed Reactor Operators (ROs) were dispatched to locally start the A Diesel Generator in accordance with Attachment 1, LOCAL STARTING AND LOADING DIESEL GENERATOR A(B), of AOP-304.4.

Which ONE of the choices below completes the following statements in accordance with Attachment I of AOP-304.4?

Operators (1) use Main Air Start Valves as the fkt method to locally start the A Diesel Generator.

AOP-304.4 specifically states that Shift Supervisors permission must be obtained prior to depressing the (2) pushbutton.

A.

1) will

2) ENGINE SHUTDOWN RESET B.

1) will

2) EMERG START RESET C.

1) will not

2) ENGINE SHUTDOWN RESET D.

1) will not

2) EM ERG START RESET Saturday, May 16, 2015 10:53:12AM 89

90. Initial Conditions:

Mode 5 with preparations being made for entering Mode 6.

Operators and Reactor Engineering are preparing to move fuel assemblies in the Spent Fuel Pool.

Battery XBAIA is inoperable and out of service for cell replacement.

An equalize charge has been in progress on the Battery XBA1 B for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Current Conditions:

XCP-6210, 11-22, VIBR. ALARM, alarms An AO reports that the running Battery Room Exhaust fan, XFN-39A has tripped and that Battery Room Exhaust Fan XFN-39B will start.

Which ONE of the choices below completes the following statements?

A CAUTION statement in SOP-503, INTERMEDIATE BUILDING HVAC, states that the Battery Room Ventilation System must be running continuously, except when swapping ventilation trains, in order to prevent (1)

If Battery XBAIB is declared inoperable, operators (2) be allowed to commence movement of irradiated fuel in the Spent Fuel Pool in accordance with T.S.

3.8.2.2, DC SOURCES

- SHUTDOWN.

A.

1) damage to the battery from high ambient temperatures in excess of the Technical Specification limit

2) will B.

1) damage to the battery from high ambient temperatures in excess of the Technical Specification limit

2) will not C.

1) accumulation of battery gases from reaching a corrosive or explosive concentration

2) will D.

1) accumulation of battery gases from reaching a corrosive or explosive concentration

2) will not Saturday, May 16, 2015 10:53:12AM 90

91. Given the following plant conditions:

Time 1700:

100% power initially.

A leak began from the RCS to the B Steam Generator (SG).

AOP-1 12.2, STEAM GENERATOR TUBE LEAK NOT REQUIRING SI COOLANT, was entered.

Which ONE of the choices below completes the following statements?

Step 1 of AOP-112.2 directs operators to restore pressurizer level using (1) in manual.

The highest offsite dose that is calculated to occur for the leak from the RCS to the B SG, in accordance with the bases for T.S. 3.4.6.2, REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE, would be due to a/an (2)

A.

1) Controller PZR LEVEL MASTER CONTROL

2) unisolable main steam line break on B SG to the atmosphere outside of the RB.

B.

1) FCV-122, CHG FLOW

2) unisolable main steam line break on B SG to the atmosphere outside of the RB.

C.

1) Controller PZR LEVEL MASTER CONTROL

2) cooldown using B SG to the atmosphere when a Steam Generator Tube Rupture occurs on another SG.

D.

1) FCV-122, CHG FLOW

2) cooldown using B SG to the atmosphere when a Steam Generator Tube Rupture occurs on another SG.

Saturday, May 16, 2015 10:53:12AM 91

92. Initial Conditions:

MODE 6.

The refueling team was raising a fuel assembly from the core.

The fuel assembly had not yet cleared the top of the core.

A red OVERLOAD IL-4 light was received.

All activities for fuel movement in the RB were stopped.

The digital Load Readout indicated that the load cell has a failed to a higher output.

Current Conditions:

Technicians have determined that the load cell output did i trip the Master Overload interlock.

The decision has been made to complete the fuel assembly transfer and then maintain the Manipulator Crane at the Transfer Canal to allow repairs The Overload Bypass switch TS-1 was placed in the BYPASS position.

Lifting of the fuel assembly has resumed.

Which ONE of the choices below completes the following statements?

In accordance with FHP-601, REFUELING ORGANIZATION, the use of TS-1 required (1)

While TS-1 is in the BYPASS position, the Master Overload (2)_ provide protection against an overload condition.

A.

1) authorization by the Refueling Operations Coordinator (ROC) concurrence by the Core Loading Supervisor (SRO).

2) does B.

1) authorization by the Refueling Operations Coordinator (ROC) and concurrence by the Core Loading Supervisor (SRO).

2) does not C.

1) authorization by the Refueling Operations Coordinator (ROC); concurrence by the Core Loading Supervisor (SRO) is not required.

2) does D.

1) authorization by the Refueling Operations Coordinator (ROC); concurrence by the Core Loading Supervisor (SRO) is not required.

2) does not Saturday, May 16, 2015 10:53:12AM 92

93. Given the following plant conditions:

Time 1200:

100% power.

A simplex alarm annunciates for the Relay room.

The Main Generator trips.

The Reactor does not trip automatically.

The NROATC attempts to trip the reactor using the Reactor Trip switch on XCP-61 10 and the reactor does not trip.

The BOP successfully trips the reactor using the Reactor Trip switch on XCP-61 14.

Time 1204:

There is heavy black smoke coming in to the Control Room.

The SS announces that the use of FEP-4.0, CONTROL ROOM EVACUATION DUE TO FIRE is required.

There is not time to perform actions in the Control Room prior to evacuation.

Operators note as they were leaving that PCV-445A, PWR RELIEF was cycling open and closed erratically with Pressurizer pressure oscillating at 1900 psig.

Time 1225:

Operators transfer controls to LOCAL at the CREP in accordance with FEP-4.0, Enclosure A, DUTIES OF THE CONTROL ROOM SUPERVISOR.

An operator notes that RCS Wide Range pressure quickly stabilizes at 1950 psig upon aligning PORV XFER PCV-445A at Auxiliary Panel 7200A.

Which ONE of the following choices identifies when the conditions for an EAL declaration of Site Area Emergency (SAE) were met?

Do not use Emergency Director judgment as a basis for classification.

REFERENCE PROVIDED A.

1200.

B.

1204.

C. 1215.

D. 1219 Saturday, May 16, 2015 10:53:12AM 93

94. Initial Conditions:

100% power initially A loss of all offsite power (115KV and 230KV) has occurred.

A and B Emergency Diesel Generators failed to start.

The TD EFW pump shaft sheared on startup.

Current Conditions:

All emergency buses remain de-energized.

Operators have just completed the step in EOP-6.0, LOSS OF ALL ESF AC POWER, to Verify RB pressure has remained LESS THAN 12 psig.

Core Exit Thermocouples (CET5) are 1202 °F and rising.

STA reports the following Critical Safety Function Status Trees:

- Core Cooling: RED

- Heat Sink:

RED

- Containment: ORANGE

- Inventory:

YELLOW

- Subcriticality:

GREEN

- Integrity:

GREEN What procedure is required to be used next to mitigate the casualty?

A. EOP-6.0, LOSS OF ALL ESF AC POWER B. EOP-14.0, FR-C.1, RESPONSE TO INADEQUATE CORE COOLING C. EOP-15.0, RESPONSE TO LOSS OF SECONDARY HEAT SINK D. SACRG-1, SEVERE ACCIDENT CONTROL ROOM GUIDELINE INITIAL

RESPONSE

Saturday, May 16, 2015 10:53:12AM 94

95. Initial conditions:

Mode 6.

A core off-load is in progress.

Water level in the refueling cavity is at 461.5 ft.

A RHR flowrate is 3100 gpm.

B RHR Loop is tagged out for maintenance.

Current conditions:

A fuel bundle has just been removed from the Reactor Vessel and is approximately half-way between the Reactor Vessel and the Upender.

A RHR flowrate is 2700 gpm.

Given the conditions above, which ONE of the choices below completes the following statements?

T.S. 3.9.7, RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL allows operators to move the suspended fuel assembly to the (1)

The bases of TS 3.9.7 states that sufficient (2)

A.

1) Reactor Vessel

2) circulation must be maintained to prevent boron stratification and minimize the effects of a dilution event.

B.

1) Reactor Vessel

2) cooling must be maintained to keep RCS temperature less than a maximum refueling limit of 170°F.

C.

1) Upender

2) circulation must be maintained to prevent boron stratification and minimize the effects of a dilution event.

D.

1) Upender

2) cooling must be maintained to keep RCS temperature less than a maximum refueling limit of 170°F.

Saturday, May 16, 2015 10:53:12 AM 95

96. Given the following conditions:

A refueling outage is in progress that is scheduled for 52 days.

Currently the plant is in MODE 5 in day two (2) of the outage.

A component required by Technical Specifications (TS) must be removed from service and tagged out for maintenance.

The LCO for this component requires that it be OPERABLE in MODES 1-4.

The CRS just completed Attachment VI, OUTAGE REMOVAL AND RESTORATION CHECKSHEET, of SAP-205, STATUS CONTROL AND REMOVAL AND RESTORATION for this component.

Which ONE of the choices below completes the following statements?

If this component is danger-tagged and out of service for 32 days, its status (1) be required to be evaluated using SAP-205 Attachment IX, EVALUATION OF R&R IN EFFECT FOR GREATER THAN 30 DAYS.

SAP-205 states that the outage R&R logbook will be closed out prior to entry into MODE (2).

A.

1) will

2) 2 B.

1) will not

2) 2 C.

1) will

2) 4 D.

1) will not

2) 4 Saturday, May 16, 2015 10:53:12AM 96

97. Given the following plant conditions:

Time 1000 on May 4

100% power.

A Charging pump is in service.

B Charging pump breaker XPPOO43B is open, and cannot be operated or racked down due to problems with the breaker.

C Charging pump breaker XPP0043C is racked up on the B train.

Time 1200 on May 4

XCP-614 2-6, CCW TO CHG PP A VLV NOT FULL OPEN, is in alarm.

Valve XVG-9684A, CC WTR TO CHG PP A, is shut and mechanically bound.

A Charging pump temperatures are being locally monitored using Attachment 1, Charging Pump Temperature Monitoring, of AOP-118.1, TOTAL LOSS OF COMPONENT COOLING WATER.

A Charging pump temperatures are stable.

Which ONE of the choices below completes the following statement?

If no changes to plant status after 1200 are made, the latest time the plant is required to be in HOT STANDBY, in accordance with Technical Specifications, is REFERENCE PROVIDED A. l7000nMay4 B. l900onMay4 C. 1600 on May7 D. 1800 on May7 Saturday, May 16, 2015 10:53:12AM 97

97 EMERGENCY CORE COOLiNG SYSTEMS 3/4.5.2 ECCS SUBSYSTEMS - Tivg 35O°F LIMITING CONDITION FOR OPERATION 3.52 Two independent Emergency Core Cooling System (BCCS) subsystem_st shall be OPERABLE with each subsystem comprised of a.

One OPERABLE centrifugal charging pump,.

b.

One aPE LEresduai beat removalheatexchanger, c.

One OPERABLE residual heat removalpump, and d.

An OPERABLE flow path capable offnkirg suction from the refueling water storage tank on a safety injection signal and automatically transferring suction to the residual heat removal sump during the recirculation phase of operatiom APPLICABILITY: MODES 1,2 and 3.

ACTION:

a.

With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months t or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall he prepared and submitted to the Conmissionpursuantto Specification 6.9.2 within 90 days describ ing the circumstances ofthe actuation and the total accumulated actuation cycles to date. The current value ofthe usage factor for each affected safety injection nozzle shall be provided in this StecialReportwbenever its value exceeds 0.70.

- The allowable outage time for each RER train may be extended to 7 days for the purpose ofmaintenance and modification. This exception may only be used one time per RIIR train and is not valid after December 32, 1997.

SUMMER - UNIT 1

&4 53 Amendment.

98. Given the following timeline:

Tuesday, 5/25/15 Time 0200: The RB atmosphere was sampled in preparation for lowering pressure using Alternate Purge.

Time 0300: The Shift Supervisor approved the release permit.

Time 0310: Due to a manpower shortage, the SS decided to delay the release.

Wednesday, 5/26/15 Time 0330: The Control Room is ready to initiate the release.

Which ONE of the following describes whether the release can be performed?

A. The release can be started Q!JJY if RM-A2 reads the same or less than the reading recorded on the release permit.

B. The release can be started 2flJY if reactor power has not changed by more than 15% since the release permit was approved.

C. The release can not be started because more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months have passed since the containment air sample.

D. The release can not be started because more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months have passed since approval of the release permit.

Saturday, May 16, 2015 10:53:13AM 98

99.

Given the following plant conditions:

A small break LOCA occurred at time 0130.

Time is now 0330.

RCS temperature is 380° F.

Bus 1 DA is de-energized.

An action to cross-connect 1 DA and 1 DB with temporary electrical cabling is being proposed by engineering support personnel to restore vital equipment to protect the health and safety of the general public.

The Emergency Director has determined that it is necessary to perform this action.

Which ONE of the choices below completes the following statements?

The Shift Supervisor was relieved from initial ERO duties upon activation of the (1).

The Emergency Director _(2) require Shift Supervisors concurrence prior to taking actions to cross-connect 1 DA and 1 DB.

A.

1) TSC.

2) does B.

1) TSC.

2) does not C.

1) EOF.

2) does D.

1) EOF.

2) does not Saturday, May 16, 2015 10:53:13AM 99

100. Given the following plant conditions:

Time 1007:

A full core offload has just been completed.

Anti-nuclear protesters were gathered at the guard post.

One person was seen running past the gate carrying a pistol and backpack and climbing over the rock barrier.

Time 1010:

The Security Team Leader reported that the same person jumped over the fence and ran past Warehouse C.

Time 1021:

The Control Room crew heard a large explosion.

Time 1032:

Spent Fuel Pool level indicators LI-7431 and Ll-7433 both read offscale low.

An AO reports water rushing out of a crack in the wall of the Fuel Handling Building in the loading bay on the 436 level.

Time 1041:

RM-A13, MAIN PLANT VENT EXHAUST reads 15 mrem/hr and rising.

Which ONE of the following contains the times at which conditions were first met for declaration of Site Area Emergency and General Emergency?

Do not consider Emergency Director Judgment as a basis for emergency classification.

REFERENCE PROVIDED SAE GE A.

1007 1032 B.

1007 1041 C.

1010 1032 D.

1010 1041 You have completed the test!

Saturday, May 16, 2015 10:53:13 AM 100

3 4

5 6

7 8

9 10 11 12 13 14 15 16 17 18 19 20 21 79 23 24 25 26 27 28 29 30 31 32 )

34 35 36 37 38 39 40 41 42 43 44 45 46 C

D D

C D

B A

C B

D B

A D

C C

B B

B D

B C

A A

C C

A B

D B

A C

A D

D C

B D

C D

A D

D C

C A

A ANSWER KEY REPORT for 2015 NRC Exam FINAL AS GIVEN Test Form: 0 Answers o___--_-_

Wednesday, May 27, 2015 10:41:52AM 1

ANSWER KEY REPORT for 2015 NRC Exam FINAL AS GIVEN Test Form: 0 Answers 0

47 D

48 C

49 C

50 A

51 D

52 A

53 B

54 D

55 B

56 B

57 C

58 A

59 A

60 C

61 B

62 A

63 B

64 A

65 B

66 C

67 C

68 A

69 D

70 A

71 B

72 A

73 A

74 B

75 B

76 B

77 A

78 C

79 D

80 A

81 B

82 A

83 A

84 C

85 D

86 C

87 B

88 B

89 D

90 D

91 B

92 A

Wednesday, May 27, 2015 10:41:53 AM 2

ANSWER KEY REPORT for 2015 NRC Exam FINAL AS GIVEN Test Form:

0 Answers--

0 93 D

94 D

95 C

96 D

97 B

98 C

99 A

100 C

Wednesday, May 27, 2015 10:41:53AM 3

Question 100:

EAL Chart was also included with this Question as a reference, too large to scan and include here.

Reference:

EPP-001, Attachment 1, Rev. 30A, EAL Classification Matrix.

ML15173A439

Text

RESPONSE

Reference:

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