Text

VC Summer 05000395/2017301 Exam Report Items SRO As-Given Written Exam
	ML17298A572
Person / Time
Site:	Summer
Issue date:	10/25/2017
From:	; NRC/RGN-II
To:	; South Carolina Electric & Gas Co
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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: September 28, 2017 Facility/Unit V.C. Summer Unit 1

Region: I II X III IV Reactor Type: W X CE BW GE

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 percent overall, with 70 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 percent to pass.

You have 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-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-only portion.

Applicant Certification

All work done on this examination is my own. I have neither given nor received aid.

__________________________________

Applicants Signature

Results

RO/SRO-Only/Total Examination Values ______ / ______ / ______ Points

Applicants Score ______ / ______ / ______ Points

Applicants Grade ______ / ______ / ______ Percent

ES-401, Page 50 of 52

Name: ________________________________ 2017 NRC (15-01)

Form: 0

Version: 0

1. Given the following plant conditions:

The reactor is at 100% power.

The reference leg of Pressurizer Level transmitter LT-460 has physically

separated from the transmitter port.

Which ONE of the choices below completes the following statements?

Indication derived from LT-460 will be __(1)__ than actual.

This event __(2)__ cause an actual loss of reactor coolant.

A. 1) higher

2) will not

B. 1) higher

2) will

C. 1) lower

2) will not

D. 1) lower

2) will

Monday, September 25, 2017 8:30:58 AM 1

2017 NRC (15-01)

2. Given the following plant conditions:

A small break loss of coolant accident has occurred.

EOP-2.1, POST-LOCA COOLDOWN AND DEPRESSURIZATION is in

progress.

All Reactor Coolant Pumps have been stopped.

All S/G narrow range levels are approximately 60% and stable.

Steam generator pressures are at 845 psig and decreasing.

RCS pressure is 1600 psig and decreasing.

Narrow Range RVLIS reads 85% and decreasing.

RCS TCOLDs are at 526°F and decreasing.

RCS THOTs are at 550°F and decreasing.

RB pressure is at 3 psig and decreasing.

Which ONE of the choices below completes the following statements?

In order to verify natural circulation, EOP-2.1 requires verification that ___(1)___

temperatures are at the saturation temperature for the associated steam generator

pressure.

In the current condition, the steam generators __(2)__ removing heat from the reactor

coolant system.

A. 1) THOT

2) are

B. 1) TCOLD

2) are

C. 1) THOT

2) are not

D. 1) TCOLD

2) are not

Monday, September 25, 2017 8:30:58 AM 2

2017 NRC (15-01)

3. Given the following plant conditions:

Time 0700:

100% power.

The "A" Emergency Diesel REMOTE/LOCAL/MAINT Switch is taken to MAINT.

1DA and 1DB are energized from their respective NORM FEED breakers.

Time 0800:

XSW1DA 03, EMERG DIESEL GEN A XEG0001A-DG is racked DOWN.

1DA and 1DB remain energized from their respective NORM FEED breakers.

Time 1010:

A spurious lockout occurred on bus 1DX due to a faulty relay actuation.

Time 1015:

A large break LOCA occurred.

Time now 1020.

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

Entry into an action statement in T.S. 3.8.1.1, AC SOURCES was first required at time

__(1)__.

At the current time of 1020, __(2)__ train(s) of ECCS equipment is (are) operating as

required.

ASSUME NO OPERATOR ACTIONS AFTER THE REACTOR TRIP

A. 1) 0700.

2) only one

B. 1) 0800.

2) only one

C. 1) 0700.

2) both

D. 1) 0800.

2) both

Monday, September 25, 2017 8:30:58 AM 3

2017 NRC (15-01)

4. Given the following plant conditions:

Time 0500:

100% power.

"A" CCW train is active.

A cooling coil in the "A" RCP Thermal Barrier Heat Exchanger has completely

ruptured.

Time now 0501:

Which ONE of the following indications will be present now?

A. "A" CCW pump amps increase.

B. CCW Surge Tank Level lowers.

C. MVG-9600, TO THERM BARR ISOL closes.

D. MVT-9593A, FROM RCP A THERM BARR closes.

Monday, September 25, 2017 8:30:58 AM 4

2017 NRC (15-01)

5. Given the following plant conditions:

100% power.

The running Charging pump tripped.

AOP-102.2, LOSS OF CHARGING is in progress.

A Charging pump has been started.

Pressurizer level is 50% and rising.

The NROATC has been directed to restore letdown in accordance with

SOP-102, CHEMICAL AND VOLUME CONTROL SYSTEM.

- LCV-459 and LCV-460, LTDN LINE ISOL are both open.

- FCV-122, CHG FLOW is in MANUAL.

- TI-140, REGEN HX OUT TEMP °F, reads 325°F and lowering.

- PCV-145, LO PRESS LTDN is in AUTO.

PI-145, LO PRESS LTDN PRESS PSIG at 350 psig.

- TCV-144, CC TO LTDN HX is in AUTO

VCT temperature is at the desired value.

Which ONE of the choices below completes the following statement?

In accordance with SOP-102, FCV-122, CHG FLOW will be placed in AUTO _____.

u at the current pressurizer level; Pressurizer level has reached the programmed level

A.

for the current power.

B. at the current pressurizer level; FCV-122 will automatically restore pressurizer level

to program.

C. at a higher pressurizer level; This will allow a transfer of FCV-122 to AUTO with a

minimum amount of control perturbation.

D. at a higher pressurizer level; Flow must be maintained to lower Regenerative Heat

exchanger temperature to a lower value.

Monday, September 25, 2017 8:30:58 AM 5

2017 NRC (15-01)

6. Initial conditions:

RCS TCOLD temperature is 285°F.

"A" RHR loop in cooldown mode.

Pressurizer PORVs PCV-445A, PCV-444B and PCV-445B are in AUTO.

Pressurizer PORV Block Valves MVG-8000A, B and C are open.

A 20 gpm RCS leak to the RB is detected.

Current conditions:

RCS TCOLD temperature is 310°F.

MVG-8701A and MVG-8702A, RCS LP A TO PUMP A are closed for leak

isolation.

MVG-8701B and MVG-8702B, RCS LP C TO PUMP B are open.

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

1) Is the T.S. 3.4.9.3, OVERPRESSURE PROTECTION SYSTEMS LIMITING

CONDITION FOR OPERATION (LCO) applicable for the current RCS

temperature?

2) If it is assumed that T.S. 3.4.9.3 is applicable in the current condition, are there

sufficient pressure relief devices in service to fully meet the T.S. 3.4.9.3, LCO

without reliance on an action statement?

A. 1) Yes.

2) Yes.

B. 1) Yes.

2) No.

C. 1) No.

2) Yes.

D. 1) No.

2) No.

Monday, September 25, 2017 8:30:58 AM 6

2017 NRC (15-01)

7. Initial conditions:

100% power.

RCS pressure is 2235 psig and stable.

All systems are in automatic.

Group 2 backup heater control switch is in AFTER TRIP.

Group 1 backup heater control switch is in AFTER CLOSE.

Current condition:

The pressurizer pressure master controller setpoint potentiometer fails to a

setting of 2275 psig.

Which ONE of the following describes the status of the stated Pressurizer pressure

control system components 5 seconds after the potentiometer failure?

Assume a step change in the controller setpoint.

Group 2 B/U Heaters Spray Valves

A. ON CLOSED

B. OFF CLOSED

C. OFF OPEN

D. ON OPEN

Monday, September 25, 2017 8:30:58 AM 7

2017 NRC (15-01)

8. Given the following plant conditions:

100% power.

Train "B" SSPS testing was in progress in accordance with STP-345.074, SSPS

ACTIVATION LOGIC AND MASTER RELAY TEST FOR TRAIN B.

A feedwater malfunction is occurring.

All Narrow Range Steam Generator levels are at 33% and decreasing.

The following Reactor Protection system breaker position indications are present

on Control Board XCP-6110:

GREEN light RED light

RX TRIP BKR A OFF ON

RX TRIP BKR B ON OFF

BY PASS BKR A OFF OFF

BY PASS BKR B OFF ON

Which ONE of the choices below completes the following statement?

A failure of the automatic reactor trip function __(1)__ occurred.

By plant design, the indicating lights for __(2)__ will change state if switch RX TRIP

CS-CR01 at panel XCP-6110 is taken to the TRIP position.

A. 1) has

2) only RX TRIP BKR A

B. 1) has

2) RX TRIP BKR A and BYPASS BKR B

C. 1) has not

2) only RX TRIP BKR A

D. 1) has not

2) RX TRIP BKR A and BYPASS BKR B

Monday, September 25, 2017 8:30:58 AM 8

2017 NRC (15-01)

9. Given the following plant conditions:

Tube ruptures have occurred on "B" and "C" Steam Generators.

A reactor trip and safety injection occurred.

RCS pressure is 1400 psig.

"B" Steam Generator pressure is 1100 psig.

"C" Steam Generator pressure is 1025 psig.

RCS temperature is 542°F.

Which ONE of the following is closest to the expected condition of the RCS if it is

depressurized to the exact pressure at which all primary to secondary leakage stops?

Assume that RCS temperature and steam generator pressures remain constant

during the RCS depressurization.

A. 4°F subcooled.

B. 7°F subcooled.

C. 14°F subcooled.

D. 16°F subcooled.

Monday, September 25, 2017 8:30:58 AM 9

2017 NRC (15-01)

10. Given the following plant conditions:

Time 10:00

8% power.

"A" Main Feedwater pump is running.

"B" and "C" Main Feedwater pumps are not running.

- Their associated TRIP/RESET switches indicate RESET.

Turbine-driven EFW pump is OFF.

"A" and "B" MD EFW Pumps are in NORMAL AFTER STOP.

Hand Controllers IFV-3531(3541)(3551), MD EFP TO SG A(B)(C) are at 0% and

indicate full closed.

Flow Control Valve Switches FCV-3531(3541)(3551), MD EFP TO SG A(B)(C)

are in MANUAL.

Time 10:02

"A" Main Feedwater pump has tripped.

Steam Generator (S/G) narrow range levels have decreased steadily to the

following values:

A S/G is 33%. B S/G is 45%. C S/G is 48%.

Which ONE of the choices below completes the following statements?

__(1)__ Emergency Feedwater pumps are running.

IFV-3531(3541)(3551), MD EFP TO SG A(B)(C) are __(2)__.

Assume no operator actions.

A. 1) No

2) closed.

B. 1) The "A" and "B" motor-driven and the turbine-driven

2) 100% open.

C. 1) Only the "A" and "B" motor-driven

2) 100% open.

D. 1) Only the "A" and "B" motor-driven

2) closed.

Monday, September 25, 2017 8:30:58 AM 10

2017 NRC (15-01)

11. Given the following plant conditions:

Initial conditions:

100% power.

Turbine-driven EFW Pump is inoperable.

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

Current conditions:

Operators are in EOP-1.1, REACTOR TRIP RESPONSE.

Both EDGS are tripped and will not start from the control room.

SG narrow range levels are 20%, decreasing slowly.

Which ONE of the following describes the next procedure transition from EOP-1.1 and

the first high level step that is performed in that procedure?

A. EOP-15.0, FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK;

Check if secondary heat sink is required.

B. EOP-15.0, FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK;

Try to establish EFW flow to at least one SG.

C. EOP-6.0, ECA-0.0 LOSS OF ALL ESF AC POWER;

Verify the Reactor is tripped.

D. EOP-6.0, ECA-0.0 LOSS OF ALL ESF AC POWER;

Try to restore power to any ESF bus.

Monday, September 25, 2017 8:30:58 AM 11

2017 NRC (15-01)

12. Given the following plant conditions:

Time 0700:

75% power.

"A" CCW train is active.

"B" CCW pump is inoperable.

There are no Technical Specification Action Statements in effect.

Time 0710:

APN-5903 is deenergized due to a malfunction.

Time 0715:

A large break LOCA occurred.

A loss of all offsite power (115 KV and 230 KV) occurred after the reactor trip.

EOP-1.0, E-0 REACTOR TRIP OR SAFETY INJECTION is in progress.

Which ONE of the choices below completes the following statement?

While performing EOP-1.0, ATTACHMENT 3, SI EQUIPMENT VERIFICATION, the

BOP will find "C" CCW pump_______.

A. off and a manual start will be required because an automatic start is prevented

by the ESFLS AUTO START BLOCK function.

B. off and a manual start will be required because the "B" Train ESFLS is

deenergized.

C. running because a "A" CCW header pressure decreased below the autostart

setpoint.

D. running because it was aligned to operate as the "B" train CCW pump.

Monday, September 25, 2017 8:30:58 AM 12

2017 NRC (15-01)

13. Given the following plant conditions:

A sustained loss of offsite and onsite power has occurred.

An ELAP has been declared.

EOP-6.0, ECA-0.0 LOSS OF ALL ESF AC POWER is in progress.

The following annunciators are noted to be in alarm:

- XCP-636, 4-4, TRAIN A BATT CHGR TRBL XBC1A/1A-1B.

- XCP-637, 4-4, TRAIN B BATT CHGR TRBL XBC1B/1A-1B.

Meters on the Main Control Board read as follows:

- 1A DC VOLTS 104 VDC and decreasing.

- 1A DC AMPS 0 amps and stable.

- 1A-1B DC AMPS 0 amps and stable.

- 1B DC AMPS 0 amps and stable.

- 1B DC VOLTS 104 VDC and decreasing.

Which ONE of the choices completes the following statements?

Entry into FSP-7.0, LOSS OF VITAL INSTRUMENTATION OR CONTROL POWER

__(1)__ required in accordance with EOP-6.0.

Restoration of power to __(2)__ will allow the TRAIN A BATT CHGR TRBL

XBC1A/1A-1B alarm to clear.

A. 1) is

2) XMC1DA2Z

B. 1) is

2) XMC1DA2X

C. 1) is not

2) XMC1DA2Z

D. 1) is not

2) XMC1DA2X

Monday, September 25, 2017 8:30:58 AM 13

2017 NRC (15-01)

14. Given the following plant conditions:

100% power initially.

Both Emergency Diesels are inoperable and out of service due to a common

mode failure.

The following occur simultaneously:

- Large break LOCA.

- Overcurrent lockout of XTF0031, EMERGENCY AUXILIARY

TRANSFORMER.

Which ONE of the following identifies a valid alarm that would be present for the given

conditions?

A. XCP-601, 1-3, CCP A/C TRIP FAIL.

B. XCP-605, 2-4, SWBP B SUCT/DISCH PRESS LO.

C. XCP-619, 1-1, RCP C TRIP.

D. XCP-634, 1-5, BUS 1A3/1C3 AUTO XFER.

Monday, September 25, 2017 8:30:58 AM 14

2017 NRC (15-01)

15. Given the following plant conditions:

50% power and stable.

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

The System Controller suspended administrative limits for MVAR loading and

requested that VC Summer establish the maximum LAG MVARs.

The BOP is adjusting Main Generator Voltage.

The AC MEGAVARS meter is at 90 MVARs and increasing in the positive

direction.

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

accordance with AOP-301.1:

1) What is the VC Summer maximum limit for LAG MVAR load when the

administrative limits of AOP-301 do not apply?

2) If administrative limits will be exceeded, what condition does the reference page of

AOP-301.1 identify as a potential adverse effect if the maximum limit for LAG

MVARs is violated?

A. 1) 325 MVARs.

2) Main generator overheating.

B. 1) 325 MVARs.

2) Excessive load currents.

C. 1) 484 MVARs.

2) Main Generator overheating.

D. 1) 484 MVARs.

2) Excessive load currents.

Monday, September 25, 2017 8:30:58 AM 15

2017 NRC (15-01)

16. Initial conditions:

100% power initially.

"A" EDG is inoperable and out of service.

A break has occurred one (1) foot downstream of MVG-8888B, RHR LP B TO

COLD LEGS.

- A reactor trip and safety injection automatically actuated as a result of the

break.

Current conditions:

RWST level is 17% and decreasing.

A loss of 230 KV power has occurred.

Which ONE of the following identifies why cold leg recirculation cannot be satisfactorily

implemented for this event?

A. "A" RHR pump is deenergized and "B" RHR train cannot discharge to the RCS.

B. Emergency Operating procedures will require closing RHR pump discharge valves.

C. RCS pressure will remain above the discharge pressure of the RHR pumps.

D. RHR pumps will not have a suction source for cold leg recirculation.

Monday, September 25, 2017 8:30:58 AM 16

2017 NRC (15-01)

17. Given the following plant conditions:

A LOCA has occurred.

Both RHR pumps are inoperable.

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

RWST level is 30% and decreasing.

Operators have just stopped "B" Charging pump.

"A" Charging pump is running in injection mode.

RCS subcooling is 5°F.

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

reason for stopping the "B" Charging pump?

Operators stopped the "B" charging pump _________.

A. to conserve the available RWST inventory.

B. to reduce RCS pressure and the RCS leakrate.

C. to protect the pump from a loss of Net Positive Suction head.

D. in preparation for aligning "A" Charging pump for normal charging.

Monday, September 25, 2017 8:30:58 AM 17

2017 NRC (15-01)

18. Given the following plant conditions:

A large steam break occurred downstream of the Main Steam Isolation Valves

(MSIVs).

An automatic reactor trip and safety injection occurred.

All MSIVs failed OPEN and could not 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 establishing minimum EFW flow

to each SG that has a Narrow Range level LESS THAN 26% is to _______.

A. minimize thermal shock to SG components.

B. maintain the ability to diagnose a subsequent SG tube rupture.

C. maintain a cooldown rate in the RCS Cold Legs LESS THAN 100°F/hr.

D. prevent damage to EFW pumps due to operating for long periods of time at low flow

conditions.

Monday, September 25, 2017 8:30:58 AM 18

2017 NRC (15-01)

19. Given the following plant conditions:

50% power.

TREF 1ST STG PRESS switch is selected to PT446, CH III

Rods are in AUTO.

The NROATC notes a prompt change to a First Stage Pressure Transmitter

indication.

First Stage Pressure Transmitter indications read as follows:

- PT-446 indicates 750 psig and stable.

- PT-447 indicates 360 psig and stable.

Which ONE of the choices below completes the following statement?

For the given conditions, Control Rods should be automatically __(1)__ at __(2)__

steps per minute.

A. 1) withdrawing

2) 48

B. 1) withdrawing

2) 72

C. 1) inserting

2) 48

D. 1) inserting

2) 72

Monday, September 25, 2017 8:30:59 AM 19

2017 NRC (15-01)

20. Initial conditions:

A small break LOCA has occurred.

EOP-2.1, ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION is in

progress.

All RCPs are OFF.

"A" and "B" Charging pumps are running in injection mode.

The RO is depressurizing the RCS using a Pressurizer PORV.

Core Exit TCs are 557°F and stable.

Pressurizer Level is 0%.

NR RVLIS is 75% and stable.

Current conditions:

The RO reports that the open Pressurizer PORV cannot be closed.

Core Exit TCs are 590°F and increasing.

RCS pressure is 1365 psig and decreasing.

Pressurizer Level is 23% and increasing at 1% per second.

NR RVLIS is 50% and decreasing.

Which ONE of the following describes the reason for the change in Pressurizer level in

the current conditions above?

A. Charging pump flowrates are not increasing but approximately half of the reactor

vessel head is voided with an expanding steam volume.

B. Charging pump flowrates are not increasing but the reactor vessel head is

completely voided with core voiding now occurring.

C. Charging pump flowrates are increasing and the reactor vessel head is completely

voided with core voiding now occurring.

D. Charging pump flowrates are increasing and approximately half of the reactor

vessel head is voided with an expanding steam volume.

Monday, September 25, 2017 8:30:59 AM 20

2017 NRC (15-01)

21. Given the following plant conditions:

"A" Waste Gas Decay Tank is in service.

Which one of the choices below complete the following statements in accordance with

T.S. 3.11.2.6, RADIOACTIVE EFFLUENTS - GAS STORAGE TANKS?

If the noble gas activity in "A" Waste Gas Decay Tank reaches __(1)__ curies, then

additions to the tank must be immediately stopped.

There __(2)__ a requirement in the action statement(s) to reduce the curie content of

the tank less than this limit within one hour.

A. 1) 10

2) is

B. 1) 10

2) is not

C. 1) 131,000

2) is

D. 1) 131,000

2) is not

Monday, September 25, 2017 8:30:59 AM 21

2017 NRC (15-01)

22. Given the following plant conditions:

A plant fire occurred.

EPP-013, FIRE EMERGENCY was used to respond.

The fire has been extinguished.

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

guidance in EPP-013:

Fire Brigade members are expected to apply an extinguishing agent on the fire within

__(1)__ minutes of the station fire alarm.

After the fire is extinguished, a reflash watch will be posted for __(2)__ minutes.

A. 1) 20

2) 20

B. 1) 20

2) 30

C. 1) 30

2) 20

D. 1) 30

2) 30

Monday, September 25, 2017 8:30:59 AM 22

2017 NRC (15-01)

23. Which ONE of the following identifies an instrument function on the Control Room

Evacuation Panel (CREP) that is required to be OPERABLE in accordance with T.S.

3.3.3.5, REMOTE SHUTDOWN INSTRUMENTATION?

A. Reactor Vessel level.

B. Steam Generator level.

C. Reactor Building pressure.

D. Core Exit Thermocouple temperatures.

Monday, September 25, 2017 8:30:59 AM 23

2017 NRC (15-01)

24. Given the following plant conditions:

The NROATC has noticed that the RM-L1, CVCS LETDOWN HIGH & LOW

LIQUID RADIATION MONITOR meter indication has increased.

Chemistry is contacted to sample for RCS activity.

The CRS directs the NROATC to perform an operational check of RM-L1 in

accordance with SOP-124, PROCESS AND AREA RADIATION MONITORING

SYSTEM.

Which ONE of the choices below completes the following statements?

RM-L1 __(1)__ have an associated INTERLOCK switch that must be turned while

performing SOP-124, Section 3. E. LIQUID MONITOR OPERATIONAL CHECK.

To check for the proper RM-L1 detector response, the operator will depress the

__(2)__ pushbutton.

A. 1) does

2) HI-RAD

B. 1) does

2) NOR-CS

C. 1) does not

2) HI-RAD

D. 1) does not

2) NOR-CS

Monday, September 25, 2017 8:30:59 AM 24

2017 NRC (15-01)

25. Initial conditions:

100% power initially.

A LOCA occurred.

The reactor tripped and safety injection actuated.

RCPs are off.

RCS pressure is 1100 psig and decreasing.

EOP-16.0, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK is in

progress.

Safety Injection has been terminated.

- Operators are reading step 14, "Isolate all SI accumulators".

Which ONE of the choices below completes the following statements?

Prior to the Safety Injection, MVG-8808A, B and C, Accumulator Discharge Isolation

Valves were __(1)__.

If any Accumulators were to remain unisolated and unvented, a decrease of RCS

pressure to 575 psig would result in injection of __(2)__ into the RCS

A. 1) open.

2) only additional cooling water

B. 1) open.

2) additional cooling water and nitrogen

C. 1) closed and opened automatically when SI occurred.

2) only additional cooling water

D. 1) closed and opened automatically when SI occurred.

2) additional cooling water and nitrogen

Monday, September 25, 2017 8:30:59 AM 25

2017 NRC (15-01)

26. Given the following plant conditions:

A loss of 230 KV power occurred.

The reactor is tripped.

A Technical Specification action statement requires taking the plant to COLD

SHUTDOWN expeditiously.

EOP-1.4 NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN

VESSEL is in progress.

Operators are performing an RCS cooldown.

Narrow Range RVLIS is 72% and decreasing.

Which ONE of the choices below completes the following statements?

In the current condition, steam voiding in the reactor vessel is more likely to occur

because __(1)__ are not available.

In accordance with a note in EOP-1.4, maintaining Narrow Range RVLIS close to

__(2)__ will allow subcooled RCS liquid to condense steam from the reactor vessel

head.

A. 1) CRDM cooling fans

2) 70%

B. 1) CRDM cooling fans

2) 93%

C. 1) pressurizer backup heaters

2) 70%

D. 1) pressurizer backup heaters

2) 93%

Monday, September 25, 2017 8:30:59 AM 26

2017 NRC (15-01)

27. Given the following plant conditions:

A large break LOCA occurred.

The actions of EOP-2.2, ES-1.3 TRANSFER TO COLD LEG RECIRCULATION

are complete.

The NROATC reports that RB sump levels are continuing to increase.

Which ONE of the choices below completes the following statements?

The minimum RHR Sump level which is the entry condition for EOP-17.1, REACTOR

BUILDING FLOODING is __(1)__ feet.

The RB sump will be sampled by chemistry in EOP-17.1 to assist in determining the

__(2)__.

A. 1) 414

2) source of the unexpected water in the sump.

B. 1) 414

2) effect of the unanticipated water volume on sump pH.

C. 1) 419.5

2) source of the unexpected water in the sump.

D. 1) 419.5

2) effect of the unanticipated water volume on sump pH.

Monday, September 25, 2017 8:30:59 AM 27

2017 NRC (15-01)

28. Given the following plant conditions:

Mode 4.

Reactor Coolant Pump 'A' is to be started.

The operator notes the following:

(1) NR PRESS PSIG PI-402A is 250 psig.

(2) VCT pressure is 40 psig.

(3) "A" RCP Seal Injection flow is 5.0 GPM.

(4) "A" RCP CBO flow is 1.0 gpm.

Which ONE of the following contains all the parameters, as numbered above, that

individually would prevent the operator from starting "A" RCP in accordance SOP-101,

REACTOR COOLANT SYSTEM?

A. (1) and (3)

B. (1) and (4)

C. (2) and (3).

D. (2) and (4).

Monday, September 25, 2017 8:30:59 AM 28

2017 NRC (15-01)

29. Given the following plant conditions:

The plant is in Mode 5.

The pressurizer is solid.

RCS temperature is 150°F.

RCS pressure is 350 psig.

"A" RHR Train is aligned for shutdown cooling.

Low pressure letdown is in service.

PCV-145, LO PRESS LTDN is in AUTO, set at 350 psig.

Which ONE of the following describes an event that will cause both PCV-145 to

initially throttle closed and RCS pressure to initially increase upon initiation of the

event?

A. Tripping the in-service RHR Pump

B. Throttling FCV-122, CHG FLOW from 100% open to 50% open.

C. Increasing CCW flow through an in-service RHR heat exchanger.

D. Throttling HCV-142, LTDN FROM RHR from 50% open to 100% open.

Monday, September 25, 2017 8:30:59 AM 29

2017 NRC (15-01)

30. Given the following plant conditions:

Mode 4.

Operators are performing a cooldown using the "B" RHR train.

FCV-603B, B RHR HX DISCH VLV is throttled 75% open.

FCV-605B, RHR HX BYP is in manual and 75% open.

The CRS has directed the NROATC to increase the cooldown rate using

FCV-605B, RHR HX BYP.

Which ONE of the choices below completes the following statement?

The NROATC will adjust FCV-605B further __(1)__ to increase the cooldown rate.

The indication as read on FI-605B, PUMP B FLOW GPM will __(2)__ as a result of the

adjustment.

A. 1) open

2) not change

B. 1) open

2) increase

C. 1) closed

2) decrease

D. 1) closed

2) not change

Monday, September 25, 2017 8:30:59 AM 30

2017 NRC (15-01)

31. Given the following plant conditions:

The plant was operating at 100% power.

A large break loss of coolant accident occurred.

Operators are in the process of establishing Cold Leg Recirculation in

accordance with EOP-2.2, TRANSFER TO COLD LEG RECIRCULATION.

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

1) Which ESF system suction(s) must be manually transferred from the RWST in

accordance with EOP-2.2?

2) Which signal(s) must be reset in order to satisfy the circuit logic that will allow the

transfer(s)?

A. 1) Charging system only.

2) Safety Injection and Phase A signals.

B. 1) Charging system only.

2) Safety Injection signal only.

C. 1) Charging and RB Spray systems.

2) Safety Injection and Phase A signals.

D. 1) Charging and RB Spray systems.

2) Safety Injection signal only.

Monday, September 25, 2017 8:30:59 AM 31

2017 NRC (15-01)

32. Initial conditions:

Small break LOCA was in progress.

MVG-8808A, B and C, Accumulator Discharge Isolation Valves are energized.

Current conditions:

XCP-641, 1-1, BUS IDB O/C 51BX-1DB is in alarm.

Operators have determined that the alarm is valid.

Which ONE of the choices below identifies the Accumulator Discharge Isolation valves

that are still energized?

A. Only MVG-8808A.

B. Only MVG-8808C.

C. Only MVG-8808A and MVG-8808B.

D. Only MVG-8808A and MVG-8808C.

Monday, September 25, 2017 8:30:59 AM 32

2017 NRC (15-01)

33. Given the following plant condition:

100% power initially.

A LOCA occurred.

Operators entered EOP-16.0, RESPONSE TO IMMINENT PRESSURIZED

THERMAL SHOCK, due to a RED status on Critical Safety Function Status

Trees.

Safety injection has been terminated.

Operators have determined that a soak is required.

Which ONE of the choices below completes the following statements?

A cooldown greater than 100°F in one hour __(1)__ required to cause a pressurized

thermal shock concern with a RED status on the INTEGRITY Critical Safety Function

Status Tree.

The conditions for the soak will be maintained for a minimum period of __(2)__

hour(s) to relieve thermal stresses.

A. 1) is

2) one

B. 1) is

2) four

C. 1) is not

2) one

D. 1) is not

2) four

Monday, September 25, 2017 8:30:59 AM 33

2017 NRC (15-01)

34. Given the following plant conditions:

100% power.

XCP-616, 4-4, PRT LVL LO/TEMP/LVL/PRESS HI.

PRT conditions are as follows:

Temperature 115°F.

Level 66%.

Pressure 7 psig.

Which ONE of the following describes the parameter causing the alarm and the

method that can be used to clear the alarm?

A. Pressure is high;

Drain the PRT to the Recycle Holdup tank.

B. Pressure is high;

Vent the PRT to the Waste Gas System.

C. Temperature is high;

Cool the PRT with the RCDT heat exchanger using Service Water to cool the heat

exchanger.

D. Temperature is high;

Cool the PRT with the RCDT heat exchanger using Component Cooling Water to

cool the heat exchanger.

Monday, September 25, 2017 8:30:59 AM 34

2017 NRC (15-01)

35. Given the following plant conditions:

Reactor power is 100%.

The crew is in AOP-118.1, LOSS OF COMPONENT COOLING WATER.

Which ONE of the choices below completes the following statement?

In accordance with AOP-118.1, operators will trip RCPs if component cooling water is

not restored to the RCP motor bearing coolers within a maximum allowed time of

__(1)__ minutes or if motor bearing temperatures increase to a minimum value of

__(2)__.

A. 1) 10

2) 195°F

B. 1) 10

2) 250°F

C. 1) 20

2) 195°F

D. 1) 20

2) 250°F

Monday, September 25, 2017 8:30:59 AM 35

2017 NRC (15-01)

36. Time 1000:

The plant was operating at 80% power.

Pressurizer pressure was at 2235 psig and stable.

Pressurizer heater control switches were as pictured below.

Time 1001:

The NROATC took the PZR PRESS MASTER CONTROL to MANUAL and

pressed the down arrow pushbutton until the output % meter deflection was 0%

(Bottom of the scale).

Which ONE of the choices below completes the following statement?

As a result of taking the output meter to 0%, the BU GRP 1 AMPS indication __(1)__.

At time 1001 the BU GRP 2 breaker RED light is __(2)__.

A. 1) increased

2) LIT (on).

B. 1) increased.

2) DARK (off).

C. 1) remain the same

2) LIT (on).

D. 1) remain the same

2) DARK (off).

Monday, September 25, 2017 8:30:59 AM 36

2017 NRC (15-01)

37. Given the following plant conditions:

Time 0700:

100% power.

Plant personnel have begun performing STP-345.037, SOLID STATE

PROTECTION SYSTEM ACTUATION LOGIC AND MASTER RELAY TRAIN A.

Reactor Protection system breaker positions are as follows:

Trip Breaker Position

Bypass breaker "A" (BYA) Racked in and CLOSED

Reactor Trip breaker "A" (RTA) Racked in and CLOSED

Bypass breaker "B" (BYB) Racked out and OPEN

Reactor Trip breaker "B" (RTB) Racked in and CLOSED

Time 0701:

All Train "A" Logic Cabinet switches are in NORMAL.

The Train "B" MULTIPLEXER TEST switch is taken out of the NORMAL

position.

Which ONE of the choices below completes the following statements?

__(1)__ will be in alarm and operators will next __(2)__.

A. 1) Only XCP-605, 2-6, SSPS B TRAIN TRBL

2) perform immediate actions of EOP-1.0, E-0 REACTOR TRIP OR SAFETY

INJECTION.

B. 1) Only XCP-605, 2-6, SSPS B TRAIN TRBL

2) record entry into a one hour Technical Specification action statement.

C. 1) Both XCP-604, 2-6, SSPS A TRAIN TRBL and XCP-605, 2-6, SSPS B TRAIN

TRBL

2) perform immediate actions of EOP-1.0, E-0 REACTOR TRIP OR SAFETY

INJECTION.

D. 1) Both XCP-604, 2-6, SSPS A TRAIN TRBL and XCP-605, 2-6, SSPS B TRAIN

TRBL

2) record entry into a one hour Technical Specification action statement.

Monday, September 25, 2017 8:30:59 AM 37

2017 NRC (15-01)

38. Given the following plant conditions:

Time 0400.

100% power.

Reactor Building Pressure transmitter IPT-953 was inoperable.

All actions associated with HI-1, HI-2 and HI-3 bistables actuated by PT-953 are

complete in accordance with SOP-401, REACTOR PROTECTION AND

CONTROL SYSTEM.

Time 0500:

APN-5902 deenergized due to equipment malfunctions.

Which ONE of the choices below completes the following statements?

Power for IPT-953 is supplied from __(1)__.

At time 0500, a Reactor Building Spray actuation __(2)__ occur.

Assume no operator actions.

A. 1) APN-5903

2) did

B. 1) APN-5903

2) did not

C. 1) APN-5904

2) did

D. 1) APN-5904

2) did not

Monday, September 25, 2017 8:30:59 AM 38

2017 NRC (15-01)

39. Given the following plant conditions:

100% power.

RBCU TRAIN A EMERG switch is selected to XFN-64A.

A Safety Injection occurs.

The BOP is performing Attachment 3 of EOP-1.0, SI EQUIPMENT

VERIFICATION.

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

The minimum flow that the BOP is required to verify in each train of RBCUs, in

accordance with EOP-1.0, Attachment 3, is greater than a minimum value of __(1)__.

XFN0065A-AH (RBCU-65A) __(2)__ have service water flow through its cooling coils.

A. 1) 2000 gpm.

2) will

B. 1) 2000 gpm.

2) will not

C. 1) 4000 gpm.

2) will

D. 1) 4000 gpm.

2) will not

Monday, September 25, 2017 8:30:59 AM 39

2017 NRC (15-01)

40. Initial conditions:

100% power.

Operators are preparing to start XFN0065B 2B to reduce RB temperature.

Current conditions:

The average RB temperature as noted on station logs is 110°F.

XFN-64B/XFN 65B - RBCU TRAIN B EMERG is selected to XFN 64B.

The NROATC took the XFN0065B 2B NORM (fast speed) control switch to

START for 1 second and released the switch.

The NROATC noted the following indications:

- The red running light remained dim.

- Fan amps remained at 0 amps.

Which ONE of the choices below answers both of the following:

1) Is L.C.O. T.S. 3.6.1.5 CONTAINMENT SYSTEMS - AIR TEMPERATURE currently

met?

2) What action will allow the operator to start Fan XFN-65B in accordance with

SOP-114, REACTOR BUILDING VENTILATION SYSTEM?

A. 1) T.S. 3.6.1.5 L.C.O. is met;

2) The XFN-64B/XFN 65B - RBCU TRAIN B EMERG must be selected to XFN 65B

prior to taking the control switch to START.

B. 1) T.S. 3.6.1.5 L.C.O. is met;

2) The XFN0065B 2B NORM switch must be held to START until the red running

light is lit and fan amps are indicated.

C. 1) T.S. 3.6.1.5 L.C.O. is not met;

2) The XFN-64B/XFN 65B - RBCU TRAIN B EMERG must be selected to XFN 65B

prior to taking the control switch to START.

D. 1) T.S. 3.6.1.5 L.C.O. is not met;

2) The XFN0065B 2B NORM switch must be held to START until the red running

light is lit and fan amps are indicated.

Monday, September 25, 2017 8:30:59 AM 40

2017 NRC (15-01)

41. Given the following plant condition:

The plant is in Mode 3 with a cooldown in progress.

The NaOH tank in the Reactor Building Spray system contains a volume of 3175

gallons.

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

accordance with T.S. 3.6.2.2, SPRAY ADDITIVE SYSTEM:

1) Will T.S. 3.6.2.2 be applicable when the plant transits to Mode 4?

2) Does the volume of NaOH meet the requirements of the T.S. 3.6.2.2 LCO without

reliance on an action statement?

A. 1) No.

2) Yes.

B. 1) No.

2) No.

C. 1) Yes.

2) Yes.

D. 1) Yes.

2) No.

Monday, September 25, 2017 8:30:59 AM 41

2017 NRC (15-01)

42. Initial conditions:

The plant is shutdown.

A plant cooldown is in progress.

Steam Dump Bank 1 and Bank 2 are open.

Current conditions:

RCS TAVG has decreased to the Low-Low TAVG setpoint.

The "A" Train P-12 permissive signal actuates.

"B" Train P-12 does not actuate due to a circuit malfunction.

Which ONE of the following describes how the Steam Dumps will automatically

respond?

A. Only Bank 1 steam dumps will close.

B. Only Bank 2 steam dumps will close.

C. Both Bank 1 and Bank 2 steam dumps will close.

D. Neither Bank 1 nor Bank 2 steam dumps will close.

Monday, September 25, 2017 8:30:59 AM 42

2017 NRC (15-01)

43. Initial conditions:

A plant startup is in progress in accordance with GOP-4A, POWER

OPERATION (MODE 1 - ASCENDING).

Operators are preparing to transfer steam generator feed to the Main Feed Reg

valves.

The Main Feedwater Pump MASTER SPEED CNTRL is in MANUAL.

Reactor power is 5% and stable.

Current conditions:

Reactor power is 9% and stable.

Transfer to the Main Feed Reg Valves is complete.

Which ONE of the following describes how Feedwater Pump discharge pressure was

controlled during transfer of steam generator feed to the Main Feed Reg valves in

accordance with GOP-4A?

A. MASTER SPEED CNTRL output demand is maintained between 35% and 40%.

B. MASTER SPEED CNTRL output demand is maintained between 50% and 60%.

C. MASTER SPEED CNTRL output is adjusted to maintain Feedwater pump

discharge pressure 50 psig to 150 psig above steam header pressure.

D. MASTER SPEED CNTRL output is adjusted to maintain Feedwater pump

discharge pressure 150 psig to 300 psig above steam header pressure.

Monday, September 25, 2017 8:30:59 AM 43

2017 NRC (15-01)

44. Given the following plant conditions:

The plant is operating at 100% power.

All Main Feed Reg valves are in AUTO.

XCP-624, 1-5, SG A LVL DEV is in alarm.

STEAM CONTROL CHANNEL SEL FOR SG A is selected to FY474A.

The RO determines that SG "A" Narrow Range level is decreasing slowly.

SG "B" and "C" Narrow Range levels are stable.

Which ONE of the choices below completes the following statements?

The minimum deviation of "A" Steam Generator level from program that will cause

XCP-624, 1-5 is __(1)__.

A malfunction that could have caused the indications above is a __(2)__.

A. 1) 10%.

2) HIGH failure of Steam Generator pressure channel PT-475.

B. 1) 10%.

2) a leak on the line for operating air to FCV-478, A FCV.

C. 1) 5%.

2) HIGH failure of Steam Generator pressure channel PT-475.

D. 1) 5%.

2) a leak on the line for operating air to FCV-478, A FCV.

Monday, September 25, 2017 8:30:59 AM 44

2017 NRC (15-01)

45. Given the following plant conditions:

100% power initially.

The reactor is tripped.

EOP-1.1, ES-0.1 REACTOR TRIP RESPONSE is in progress.

The PERMISV C-9 status light on XCP-6114, 1-3 is DIM.

Steam generator NR levels are 40% and increasing.

EFW flows are 250 gpm to each steam generator.

RCS cold leg temperatures are 520°F and decreasing.

Pressurizer level is 18% and decreasing.

RB pressure is 0.5 psig and stable.

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

accordance with EOP-1.1:

1) What is the minimum pressurizer level at which operators will be required to

manually actuate Safety Injection?

2) What is an action allowed under the current conditions that will reduce the RCS

cooldown rate?

A. 1) 8%.

2) Reduce EFW flow to 50 gpm to each steam generator.

B. 1) 8%.

2) Close all condenser steam dumps.

C. 1) 10%.

2) Reduce EFW flow to 50 gpm to each steam generator.

D. 1) 10%.

2) Close all condenser steam dumps.

Monday, September 25, 2017 8:30:59 AM 45

2017 NRC (15-01)

46. Initial conditions:

100% power initially.

A steam line break occurred on "A" Steam Generator.

Instrument air has been lost.

The accumulators associated with the valves below are designed to last the

minimum required duration of __(1)__ hours to fulfill their design function:

FCV-3531, MD EFP TO SG A

FCV-3541, MD EFP TO SG B

FCV-3551, MD EFP TO SG C

If all three of the associated accumulators are depleted, this will result in the loss of

the ability to maintain ___(2)___

A. 1) 3

2) EFW to "A" steam generator isolated.

B. 1) 3

2) "B" and "C" steam generator levels for heat sink.

C. 1) 5

2) EFW to "A" steam generator isolated.

D. 1) 5

2) "B" and "C" steam generator levels for heat sink.

Monday, September 25, 2017 8:30:59 AM 46

2017 NRC (15-01)

47. Given the following plant condition:

The Unit is in Hot Standby.

A loss of offsite power (115 KV and 230 KV) has occurred.

Which ONE of the following identifies the 480V power source that can directly supply

bus 1B1 in the current condition?

Assume that any required interlock condition is met.

QI 1A1

A.

B. 1DA1

C. 1C1

D. 1DB1

Monday, September 25, 2017 8:30:59 AM 47

2017 NRC (15-01)

48. Given the following plant conditions:

Time 0100:

100% power initially.

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

Both "A" and "B" EDGs failed to start.

Time 0300:

Operators opened supply breaker 5 on DPN-2X for the Main Turbine Emergency

Bearing Oil Pump. The pump was running when the breaker was opened.

Time 0400:

Operators opened supply breaker 6 on DPN-1HB1 for the "B" EDG Oil Pump.

The pump was running when the breaker was opened.

Which ONE of the following identifies whether the available capacity for batteries that

are required under T.S. 3.8.2, DC SOURCES was extended and, if so, when?

A. Not extended for the breaker operations described above.

B. Extended at time 0300 only.

C. Extended at time 0400 only.

D. Extended at time 0300 and then extended again at 0400.

Monday, September 25, 2017 8:30:59 AM 48

2017 NRC (15-01)

49. Given the following plant conditions:

Work was in progress on Diesel Generator Building ventilation dampers.

Tags have been cleared on DIESEL RM A CLG FAN A and DIESEL RM A CLG

FAN B.

- The associated control switches have been taken to AUTO.

Which ONE of the choices below completes the following statement?

DIESEL RM A CLG FAN A and DIESEL RM A CLG FAN B will automatically start

_____.

A. by output from the "A" ESFLS sequencer or at a high room temperature setpoint.

B. upon any diesel start or at a high room temperature setpoint.

C. at a high room temperature setpoint only.

D. upon any diesel start only.

Monday, September 25, 2017 8:30:59 AM 49

2017 NRC (15-01)

50. Given the following plant conditions:

"A" EDG is operating in parallel with bus 1DA.

Due to an error in the operation of controls, the following Main Control Board

indications are present:

- DG A KILOVARS 4100 KVAR

- DG A KILOWATTS 4275 KW

Which ONE of the choices below completes the following statement in accordance with

SOP-306 EMERGENCY DIESEL GENERATOR?

The operator can use one switch to establish an operating condition in which all

operating limits for continuous operation are met by taking the _____.

REFERENCE PROVIDED

A. VOLT REG RAISE-LOWER to RAISE.

B. VOLT REG RAISE-LOWER to LOWER.

C. SPEED switch to RAISE.

D. SPEED switch to LOWER.

Monday, September 25, 2017 8:30:59 AM 50

SOP-306

ENCLOSURE B

Q 50 PAGE 1 OF 2

REVISION 19

DIESEL GENERATOR POWER FACTOR

NOTE 1: This is the preferred graph for Power Factor determination

since the values are independent of voltage. Do not operate in this

zone

NOTE 2: The machine should normally be operated with a Lagging Emergency operation or

Power Factor (KVAR OUT). as directed by procedure

0.70 0.75

5000

4500 0.80

4000

REACTIVE LOAD (KVAR OUT)

0.85

3500

3000 0.90

2500

2000 0.95

1500

1000

500

0

0 500 1000 1500 2000 2500 3000 3500 4000 4500 5000 5500 6000

4250

REAL POWER (KW)

164

2017 NRC (15-01)

51. Initial conditions:

100% power.

A waste gas release is in progress in accordance with SOP-119, WASTE GAS

PROCESSING.

RM-A10, WASTE GAS DISCHARGE MONITOR is inoperable and out of

service.

Current conditions:

The RM-A13, MAIN PLANT EXHAUST HIGH RANGE ATMOSPHERIC

MONITOR is in service.

The RM-A3, MAIN PLANT VENT EXHAUST MONITOR detector failed high.

Which ONE of the choices below completes the following statements?

RM-A13 __(1)__ a monitor that is verified OPERABLE on SOP-119, Attachment VA,

GASEOUS WASTE RELEASE WORKSHEET-CONTROL ROOM,

The failure of RM-A3 requires operators to use __(2)__ to determine the required

action(s).

A. 1) is

2) ODCM, Section 1.2.1, Radioactive Gaseous Effluent Monitoring Instrumentation.

B. 1) is

2) T.S. 3.3.3 Radiation Monitoring Instrumentation.

C. 1) is not

2) ODCM, Section 1.2.1, Radioactive Gaseous Effluent Monitoring Instrumentation.

D. 1) is not

2) T.S. 3.3.3 Radiation Monitoring Instrumentation.

Monday, September 25, 2017 8:30:59 AM 51

2017 NRC (15-01)

52. Given the following plant conditions:

100% power.

Offsite power to bus 1DA was lost.

The A Emergency Diesel Generator (EDG) automatically started and restored

power to bus 1DA.

There is no Service Water pump running on "A" train.

The following annunciators are in alarm in the Control Room:

- 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 OIL TEMPERATURE is in alarm.

- Lube Oil Temperature is reading 180 °F and rising.

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 ___(2)___ have automatically aligned to the DG "A" lube oil cooler.

A. 1) should

2) should not

B. 1) should not

2) should not

C. 1) should

2) should

D. 1) should not

2) should

Monday, September 25, 2017 8:30:59 AM 52

2017 NRC (15-01)

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

(XPP-0039C) when aligned to Service Water Loop "A" per SOP-117, SERVICE

WATER SYSTEM?

A. 1EA

B. 1EB

C. 1DA

D. 1C

Monday, September 25, 2017 8:30:59 AM 53

2017 NRC (15-01)

54. Which ONE of the choices below completes the following statements in accordance

with T.S. 3.6.4, CONTAINMENT ISOLATION VALVES ?

___(1)___ is a containment isolation valve that is required to be OPERABLE in

accordance with T.S. 3.6.4; This valve is automatically and directly closed by a

___(2)___ signal.

A. 1) MVG-9605, FROM RB LOAD ISOL

2) Phase "A"

B. 1) MVG-9605, FROM RB LOAD ISOL

2) Safety Injection

C. 1) PVT-2660, AIR SPLY TO RB

2) Safety Injection

D. 1) PVT-2660, AIR SPLY TO RB

2) Phase A

Monday, September 25, 2017 8:30:59 AM 54

2017 NRC (15-01)

55. Given the following plant condition:

RM-A2, REACTOR BUILDING SAMPLE LINE MONITOR is in alarm due to a

high radiation reading.

Which ONE of the following identifies a valve that receives a signal to automatically

close because of the RM-A2 alarm?

A. XVB00001A, REACTOR BUILDING PURGE SUPPLY ISOLATION VALVE.

B. XVB00002A, REACTOR BUILDING PURGE EXHAUST ISOLATION VALVE.

C. XVB06067, CNTMT PUR EXH ISOL VLV.

D. XVB06056, ALT PUR SPLY ISOL VLV.

Monday, September 25, 2017 8:30:59 AM 55

2017 NRC (15-01)

56. Given the following plant conditions:

Operators are preparing to begin withdrawing Control Banks in accordance with

GOP-3 REACTOR STARTUP FROM HOT STANDBY TO STARTUP (MODE 3

TO MODE 2).

Source Range N-31 and N-32 HIGH FLUX AT SHUTDOWN switches are in

NORMAL.

Considering the following items:

(1) Control Board alarms.

(2) RB Evacuation Alarm.

(3) Reactor trip.

Which ONE of the following contains all the items from the list above that would occur

if Source Range N-31 and N-32 HIGH FLUX AT SHUTDOWN switches are not taken

to BLOCK as required by GOP-3?

A. Item (1) only.

B. Items (1) and (2) only.

C. Items (1) and (3) only.

D. Items (1), (2) and (3).

Monday, September 25, 2017 8:30:59 AM 56

2017 NRC (15-01)

57. Given the following plant conditions:

A small break LOCA occurred.

All EFW pumps failed to start.

EOP-15.0, FR-H.1 RESPONSE TO A LOSS OF SECONDARY HEAT SINK is in

progress.

RB pressure is 0.5 psig and stable.

RCS pressure is 1300 psig and stable.

Steam Generator Wide range levels are as follows:

"A" 11%

"B" 10%

"C" 27%

Which ONE of the choices below completes the following statements?

Bleed and feed cooling __(1)__ required for the current conditions in accordance with

EOP-15.0.

The steps in EOP-15.0 for establishing bleed and feed direct operators to open

__(2)__ Pressurizer PORV(s).

A. 1) Is not

2) 1.

B. 1) Is not

2) 3.

C. 1) is

2) 1.

D. 1) is

2) 3.

Monday, September 25, 2017 8:30:59 AM 57

2017 NRC (15-01)

58. Given the following plant conditions:

100% power.

1B EDG is inoperable and out of service for emergent repairs.

A spurious lockout has occurred on XTF0032, EMERG AUX XFMR.

Which ONE of the following identifies the Pressurizer heaters that still have an

electrical power source available?

ASSUME NO OPERATOR ACTIONS

A. Backup group 1 only.

B. Backup group 1 and Backup group 2 only.

C. Backup group 1 and the Control group only.

D. Backup group 1, Backup group 2 and the Control group.

Monday, September 25, 2017 8:30:59 AM 58

2017 NRC (15-01)

59. Initial conditions:

100% power.

I&C reported that DRPI Data train "A" was suspect and recommended removing

the train from service for troubleshooting.

Data train "A" has been removed from service in accordance with SOP-403,

ROD CONTROL AND POSITION INDICATING SYSTEM.

Indications associated with Control Bank "D" rods are as follows:

174 steps on DRPI

172 steps on the "D" Bank Demand Step Counter.

Which ONE of the following states the possible range of actual rod positions for

Control Bank "D" rods?

A. 170 - 184 steps

B. 168 - 182 steps

C. 164 - 178 steps

D. 162 - 176 steps

Monday, September 25, 2017 8:30:59 AM 59

2017 NRC (15-01)

60. Given the following plant conditions:

The Reactor has tripped and is stabilizing in HOT STANDBY.

Train 'A' of the Core Cooling Monitor is selected to "DEG F MAR".

The following Train 'A' temperature indications exist:

- Hottest Wide-Range RTD = 557°F.

- Hottest core exit T/C = 567°F

The following pressure indications exist:

- PT-403, RC WIDE RNG PRESS TRANSMITTER = 2285 psig.

- PT-444, PZR PRESS CONTROL PRESS XMTR = 2185 psig.

Which ONE of the following values will be the largest value that will be displayed when

the "DEG F MAR" pushbutton is depressed on the Train A Core Cooling Monitor?

A. 82

B. 89

C. 92

D. 99

Monday, September 25, 2017 8:30:59 AM 60

2017 NRC (15-01)

61. Given the following plant conditions:

Mode 4.

A Release Permit for a Reactor Building Purge is approved.

Maintenance work is in progress on the personnel hatch door that must be

completed to continue a plant startup.

Reactor Building Alternate Purge is in service in accordance with SOP-114,

REACTOR BUILDING VENTILATION SYSTEM, Section 3.Q. STARTUP

REACTOR BUILDING ALTERNATE PURGE SUPPLY AND EXHAUST.

MVB-6063, H2 REMOVAL ALT PUR THROT is partially open.

PI-8254, RB NR PRESS PSI currently reads 0.9 psi and increasing.

- An operator wishes to reduce RB pressure.

Which ONE of the choices below completes the following statements in accordance

with SOP-114, REACTOR BUILDING VENTILATION SYSTEM?

To reduce RB pressure, the operator will throttle MVB-6063, H2 REMOVAL ALT PUR

THROT in the __(1)__ direction.

While using SOP-114, Section Q, the operator must ensure that flow, as read on

FI-8251, H2 PURGE FLOW CFM is maintained less than __(2)__ cfm.

A. 1) open

2) 100

B. 1) open

2) 5

C. 1) closed

2) 100

D. 1) closed

2) 5

Monday, September 25, 2017 8:30:59 AM 61

2017 NRC (15-01)

62. Given the following plant conditions:

Mode 6.

A leak has begun on the suction of the in-service Spent Fuel Cooling Pump.

Readings on LI-7431, POOL LEVEL, and LI-7433, POOL LEVEL, are both

currently slowly decreasing.

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

Which of the elevations below is closest to the expected level at which the Spent Fuel

Pool will stabilize due to the leak?

ASSUME NO OPERATOR ACTIONS

A. 455'

B. 458'

C. 460'

D. 462'

Monday, September 25, 2017 8:30:59 AM 62

2017 NRC (15-01)

63. Given the following plant conditions:

Time 1400

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

Both EDGs failed to start

Operators are taking actions in accordance with EOP-6.0, ECA-0.0 LOSS OF

ALL ESF AC POWER.

Time 1500

SG depressurization is in progress.

SG Pressures are 500 psig and decreasing.

RCS TAVG is 450°F and decreasing.

RCP CBO flows are 4 gpm and increasing on each RCP.

The Turbine Driven EFW pump is running.

SG NR Levels are as follows:

"A" 16%, decreasing.

"B" 39%, decreasing.

"C" 17%, increasing.

Source Range channels N31 and N32 are 350 cpm and increasing.

Which ONE of the following describes the appropriate action(s) regarding the steam

generator depressurization in accordance with EOP-6.0?

A. Stop the SG depressurization to allow SG levels to recover to maintain secondary

heat sink.

B. Stop the SG depressurization and allow the RCS to heat up to add negative

reactivity.

C. Continue the depressurization to allow accumulators to inject boron and add

negative reactivity.

D. Continue the depressurization to reduce differential pressure across the RCP seals.

Monday, September 25, 2017 8:30:59 AM 63

2017 NRC (15-01)

64. Given the following plant conditions:

100% power.

Condenser Vacuum Pumps "A" and "C" are in service.

Which ONE of the following will cause a Main Turbine trip due to a loss of Main

Condenser vacuum?

A. Loss of output from XTF0032, EMERG AUX XFMR.

B. Trip of XPP-0042A, CO PUMP A.

C. Closure of MVB-102B, VAC PP C TO CNDSR B.

D. Opening of MOV-1-5A TURB DRN VLV.

Monday, September 25, 2017 8:30:59 AM 64

2017 NRC (15-01)

65. Which ONE of the following sources of water flows directly into the Reactor Coolant

Drain Tank?

A. Leakage from RCP #3 seals while at 100% power with normal conditions.

B. Flow through "A" RHR suction relief valve with the "A" RHR loop in service.

C. Flow though LCV-115A, LTDN DIVERT with VCT level at 95%.

D. RCP Seal Controlled Bleed Off with the abeyance seals activated.

Monday, September 25, 2017 8:30:59 AM 65

2017 NRC (15-01)

66. Given the following plant conditions:

A RO-licensed operator is to provide a temporary relief to the on-shift BOP.

The on-shift BOP will not leave the Protected Area during the relief.

The two operators are reviewing SAP-200, CONDUCT OF OPERATIONS,

section 6.2.8, "Temporary or unexpected relief during shift only".

Consider the following turnover activities:

1 - Discussion of plant conditions and anticipated evolutions during the relief period.

2 - Review of the MCB controls, instrumentation and annunciators.

3 - Independent walkdown of the MCB.

4 - Completion of OAP-100.6 Attachment IX, RO RELIEF CHECKLIST.

5 - Station Log Book entry.

Which ONE of the following contains the minimum set of activities for temporary relief

during shift duty, in accordance with SAP-200, section 6.2.8?

A. 1 and 2.

B. 1, 2, and 5.

C. 1, 3, and 5.

D. 1, 2, 3, 4 and 5.

Monday, September 25, 2017 8:30:59 AM 66

2017 NRC (15-01)

67. Given the following plant conditions:

A reactor startup is in progress in accordance with GOP-3 REACTOR STARTUP

FROM HOT STANDBY TO STARTUP (MODE 3 TO MODE 2).

The Estimated Critical Condition is 130 steps on Control Bank D.

Operators are preparing to withdraw Control Bank rods.

Which ONE of the choices below completes the following statement?

In the conditions above, GOP APPENDIX A, GENERIC OPERATING PRECAUTIONS

requires ____.

A. shutdown by manual rod insertion if it appears that the reactor will be subcritical

with Control Bank D above 130 steps.

B. tripping the reactor if criticality occurs with Control Bank positions below the low-low

rod insertion limit.

C. emergency boration and shutdown by manual rod insertion if criticality occurs with

Control Bank positions below the low-low rod insertion limit.

D. shutdown by manual rod insertion if overlapped withdrawal of Control Bank C

begins with Control Bank B at 128 steps.

Monday, September 25, 2017 8:30:59 AM 67

2017 NRC (15-01)

68. 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-100.5, 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.

Monday, September 25, 2017 8:30:59 AM 68

2017 NRC (15-01)

69. Given the following plant conditions:

The plant is in Mode 5.

Emergent maintenance is required on XBC1B, DC DISTRI BUS 1B

BATTERY CHARGER, that will require declaring it inoperable for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

XBC1A-1B, BACKUP BATTERY CHRG, is not available.

XBA1B, DC DISTRIBUTION BUS 1B BATTERY, is in service.

Which ONE of the following choices below answers the following:

In the current MODE, a minimum of __(1)__ OPERABLE combination(s) of Battery

and associated Battery Charger are required to meet the LCO of T.S. 3.8.2.2, DC

SOURCES - SHUTDOWN without entry into an ACTION statement.

If Charger XBC1B is declared inoperable in Mode 5, then operators will be required to

__(2)__ .

A. 1) two (2)

2) immediately declare Battery XBA1B inoperable.

B. 1) two (2)

2) demonstrate operability of Battery XBA1B within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

C. 1) one (1)

2) immediately declare Battery XBA1B inoperable.

D. 1) one (1)

2) demonstrate operability of Battery XBA1B within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

Monday, September 25, 2017 8:30:59 AM 69

2017 NRC (15-01)

70. Given the following plant conditions:

100% power.

A Reactor Building entry by Operations is required.

HP has sampled the Reactor Building atmosphere and reports that Particulate,

Gas and Iodine are at 0.1 DAC.

The crew is utilizing OAP-108.1, CONTROL OF REACTOR BUILDING ENTRY.

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

1) What is the preferred point of entry?

2) What is a condition that is required to be satisfied before this RB entry in

accordance with OAP-108.1?

A. 1) Escape Airlock.

2) Incore detectors must be tagged out.

B. 1) Escape Airlock.

2) RB Charcoal Cleanup Units must be in service.

C. 1) Personnel Airlock.

2) Incore detectors must be tagged out.

D. 1) Personnel Airlock.

2) RB Charcoal Cleanup Units must be in service.

Monday, September 25, 2017 8:30:59 AM 70

2017 NRC (15-01)

71. Given the following plant conditions:

100% power initially.

"A" steam generator (SG) is ruptured.

EOP-4.0, E-3 STEAM GENERATOR TUBE RUPTURE is in progress.

Chemistry reports that "A" SG activity is highly elevated and that "B" and "C"

activities are elevated above normal.

Operators are preparing to begin an RCS cooldown.

The wind direction is from the East.

Which ONE of the following identifies an event that would increase the radiation hazard

to someone standing on the bridge between the Auxilary Building and Control Building

roofs as EOP-4.0 progresses?

Assume no other additional malfunctions occur.

A. "A" Motor-driven EFW pump trips.

B. All Circulating Water pumps trip.

C. Ruptured steam generator level reaches 85% Narrow Range level.

D. Ruptured steam generator pressure reaches 1092 psig.

Monday, September 25, 2017 8:30:59 AM 71

2017 NRC (15-01)

72. Given the following plant conditions:

A LOCA inside the RB has occurred.

The use of planned dose limits in accordance with VCS-EPP-020,

EMERGENCY PERSONNEL EXPOSURE CONTROL has been authorized by

the Emergency Director.

A task must be performed in a penetration room in the Auxiliary Building in an

area that has elevated radiation levels.

The task is not required to save valuable equipment, for lifesaving, or to protect

large populations.

Which ONE of the following is the maximum emergency dose a V.C. Summer

employee may receive to perform the task described above in accordance with

EPP-020?

A. 4 rem.

B. 5 rem.

C. 10 rem.

D. 25 rem.

Monday, September 25, 2017 8:30:59 AM 72

2017 NRC (15-01)

73. Given the following plant conditions:

100% power initially.

A LOCA occurred.

RCS pressure is 780 psig and stable.

RWST level is 30% and decreasing.

RB pressure is 8 psig and increasing.

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

1) What is the setpoint for the first alarm that will alert operators that transfer to

EOP-2.2, ES-1.3 TRANSFER TO COLD LEG RECIRCULATION is immediately

required based on RWST level?

2) What is an action that occurs automatically at this RWST level?

A. 1) 6%.

2) MVG-3004A and MVG-3005A, SUMP ISOL LOOP A, will both open.

B. 1) 6%.

2) MVG-8706A(B), RHR LP A(B) TO CHG PP will both open.

C. 1) 18%.

2) MVG-3004A and MVG-3005A, SUMP ISOL LOOP A, will both open.

D. 1) 18%.

2) MVG-8706A(B), RHR LP A(B) TO CHG PP will both open.

Monday, September 25, 2017 8:30:59 AM 73

2017 NRC (15-01)

74. Given the following plant conditions:

100% power initially.

A large break LOCA occurred.

The STA is now monitoring Critical Safety Function Status Trees.

Total EFW flow is 350 gpm.

All Narrow Range Steam Generator levels are 42% and increasing.

RB pressure is 56 psig.

Core Exit Thermocouples are 700°F and increasing.

Source Range Startup rate is positive.

Which ONE of the following identifies a Critical Safety Function with a RED status in

the current condition?

A. Subcriticality.

B. Core Cooling.

C. Heat Sink.

D. Containment.

Monday, September 25, 2017 8:30:59 AM 74

2017 NRC (15-01)

75. Which ONE of the choices answers both of the following questions in accordance with

VCS-EPP-002, COMMUNICATION AND NOTIFICATION?

1) What is the lowest Emergency Action Level at which ERO responders are required

to report to their duty stations?

2) What is the preferred method that the assigned communicator will use to notify

ERO responders that they must report?

A. 1) Alert.

2) Activation of an automated messaging system.

B. 1) Alert

2) Verbal phone notification using a Call Tree.

C. 1) Site Area Emergency.

2) Activation of an automated messaging system.

D. 1) Site Area Emergency.

2) Verbal phone notification using a Call Tree.

Monday, September 25, 2017 8:30:59 AM 75

2017 NRC (15-01)

76. Initial conditions:

100% power initially.

A loss of all Feedwater pumps occurred.

The reactor failed to trip.

All EFW pumps failed to start.

Current conditions:

EOP-13.0, RESPONSE TO ABNORMAL NUCLEAR POWER GENERATION, is

in progress.

Emergency boration has been started.

Operators have just verified all dilution flowpaths are isolated.

Core Exit TCs are 1300°F and increasing.

Narrow range RVLIS is 37% and decreasing.

Reactor Power is 4% and decreasing.

Intermediate Range Startup range is negative.

EFW is 0 gpm.

Steam Generator Narrow Range levels are 0%.

Which ONE of the choices below completes the following statement in accordance with

EOP-13.0?

Operators will next transition directly to _____.

A. SACRG-1,SEVERE ACCIDENT CONTROL ROOM GUIDELINE INITIAL

RESPONSE.

B. EOP-14.0, FR-C.1 RESPONSE TO INADEQUATE CORE COOLING.

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

D. EOP-15.0, FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK.

Monday, September 25, 2017 8:30:59 AM 76

2017 NRC (15-01)

77. Initial conditions:

100% power.

Engineering reviewed an x-ray of a piping weld on the 3 inch normal letdown line

directly upstream of LCV-459 and LCV-460, LTDN LINE ISOL(s).

Current conditions:

A steam generator tube rupture occurred.

The reactor tripped and safety injection actuated.

After the trip, the normal letdown line sheared completely at the weld location

described above.

Which ONE of the following identifies the Emergency Operation Procedure that will be

used to achieve COLD SHUTDOWN conditions?

A. EOP-2.1, ES-1.2 POST-LOCA COOLDOWN AND DEPRESSURIZATION.

B. EOP-4.1A, ES-3.1 POST-SGTR COOLDOWN BY BACKFILLING THE REACTOR

COOLANT SYSTEM.

C. EOP-4.2, ECA-3.1 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED

RECOVERY DESIRED.

D. EOP-4.3, ECA-3.2 SGTR WITH LOSS OF REACTOR COOLANT SATURATED

RECOVERY DESIRED.

Monday, September 25, 2017 8:30:59 AM 77

2017 NRC (15-01)

78. Initial conditions:

100% power initially.

A pressurizer spray valve failed open mechanically.

A reactor trip and safety injection occurred.

Reactor Coolant Pump "A" was stopped.

Current conditions

EOP-1.0, E-0 REACTOR TRIP OR SAFETY INJECTION is in progress.

Pressurizer level is 100%.

Pressurizer pressure is cycling between 2250 and 2335 psig.

Pressurizer PORVs are cycling continuously.

PRT pressure is 40 psig and increasing.

RB pressure is 0.5 psig.

The Shift Engineer provides the CRS with a CRITICAL SAFETY FUNCTION

STATUS.

- There are no RED or ORANGE statuses indicated.

- EOP-18.0, FR-I.1 RESPONSE TO HIGH PRESSURIZER LEVEL is circled

for operator discretion.

Which ONE of the choices below completes the following statements?

EOP-1.0 will provide a transition to __(1)__ in the given condition.

MVG-8801A(B), HI HEAD TO COLD LEG INJ __(2)__ required to be closed before

EOP-18.0, RESPONSE TO HIGH PRESSURIZER LEVEL can be used to mitigate the

high pressurizer level.

A. 1) EOP-1.2, ES-1.1 SAFETY INJECTION TERMINATION.

2) are not

B. 1) EOP-1.2, ES-1.1 SAFETY INJECTION TERMINATION.

2) are

C. 1) EOP-2.0, E-1 LOSS OF SECONDARY OR REACTOR COOLANT.

2) are not

D. 1) EOP-2.0, E-1 LOSS OF SECONDARY OR REACTOR COOLANT.

2) are

Monday, September 25, 2017 8:31:00 AM 78

2017 NRC (15-01)

79. Given the following plant condition:

100% power.

Which ONE of the choices below completes the following statements?

The limit on specific activity in the secondary coolant for this mode is ___(1)___

microcurie per gram of DOSE EQUIVALENT I-131 in accordance with T.S. 3.7.1.4,

PLANT SYSTEMS - ACTIVITY.

The basis for this is to limit offsite dose during a ___(2)___.

A. 1) 1.0

2) Steam line break.

B. 1) 1.0

2) Steam Generator tube rupture.

C. 1) 0.10

2) Steam line break.

D. 1) 0.10

2) Steam Generator tube rupture.

Monday, September 25, 2017 8:31:00 AM 79

2017 NRC (15-01)

80. Given the following plant conditions:

Time 0100:

100% power.

Bus APN-5904 is deenergized due to equipment malfunctions.

Operators are evaluating the action statements of T.S.3.8.3, ONSITE POWER

DISTRIBUTION - OPERATING.

Time 0830:

Reactor and plant shutdown in progress.

The insertion of Control Banks to 0 steps has just been completed.

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

1) Have operators completed the minimum insertion of rods at time 0830 that is

required by the action of T.S. 3.8.3?

2) What is the latest time allowed by the action statement of T.S. 3.8.3 to complete

the minimum rod insertion?

Assume no change in the status of APN-5904.

REFERENCE PROVIDED

A. 1) Yes.

2) 0900.

B. 1) Yes.

2) 1500.

C. 1) No.

2) 0900.

D. 1) No.

2) 1500.

Monday, September 25, 2017 8:31:00 AM 80

Q 80

ELECTRICAL POWER SYSTEMS

3/4.8.3 ONSITE POWER DISTRIBUTION

OPERATING

LIMITING CONDITION FOR OPERATION

3.8.3~1 The following electrical busses shall be energized in the specified

manner with tie breakers open between redundant busses:

a. Train A A.C. Emergency Busses consisting of: -.

1. 7200 volt Emergency Busses # iDA and lEA.

2. 480 volt Emergency Busses # 1DA1, lDAVarrd 1EA1.

b. Train B A.C. Emergency Busses consisting of:

1. 7200 volt Emergency Busses # 1DB and 1EB.

2. 480 volt Emergency ~8usses-#.-1DB.1.,-

10B2.1 and XEB1.

-

c. 120 volt A.C. Vital Busses # 5902 and 5901 energized from an

associated inverter connected to D.C. Bus # hIM.

d. 120 volt A.C. Vital Busses # 5904 and 5903 energized from an

associated inverter connected to D.C. Bus # 1HB*.

e. 120 volt A.C. Vital Bus #5907 energized.

f. 120 volt A.C. Vital Bus #5908 energized. -

g. 125 volt D.C. Bus lilA energized from Battery Bank #1A.

h. 125 volt D.C. Bus 1MB energized from Battery Bank #13.

APPLICABILITY: MODES 1, 2, 3, and 4. -

ACTION:

a. With one of the required trains of A.C. Emergency busse~ not fully

energized, re-energize the division within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-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 . . -

b. With one A.C. Vital Bus not energized, reenergize the A.C. Vital Bus

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 .

c. With one of A.C. Vital Busses #5901, 5902, 5903, or 5904 either not

energized from its associated inverter, or with the inverter not

connected to its associated D.C. Bus re-energize the A.C. Vital Bus

from its associated inverter connected to its associated D.C. Bus

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

and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

The i nverters may be disconnected from their 0. C. Bus for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

as necessary for the purpose of performing an equal i zi ng charge on their

associated battery bank provided (1) their vital busses are energized, and

(2) the vital busses associated with the other battery bank are energized

from their associated inverters and connected to their associated D.C. Bus.

SU*IER - UNIT 1 3/4 813

267

2017 NRC (15-01)

81. Given the following plant conditions:

0100 on 10/5:

100% power.

"A" Service Water pump was vibrating abnormally.

The system engineer requested that the "A" Service Water pump be taken out of

service as soon as possible.

0125 on 10/5:

"C" Service Water pump was racked up and started.

"A" Service Water pump was stopped.

0126, on 10/5.

"B" Service Water pump tripped.

Time now 0130, on 10/5.

The AO reports that the "A" Service Water Pump breaker will not rack down.

Based on the equipment status at the current time, which ONE of the following

identifies the earliest time by which the plant is required to be in HOT STANDBY in

accordance with Technical Specifications?

REFERENCE PROVIDED

A. 0726 on 10/5.

B. 0826 on 10/5.

C. 0126 on 10/8.

D. 0726 on 10/8.

Monday, September 25, 2017 8:31:00 AM 81

Q 81

.

PLANT SYSTEMS

3/4.7.4 SERVICE WATER SYSTEM

LIMITING CONDITION FOR OPERATION

3.7.4 At least two independent service water loops shall be OPERABLE.

APPLICABILITY: MODES ~2, 3 and 4. + +

ACTION:

With only one service water loop OPERABLE, restore at least two loops 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 .

SURVEILLANCE REQUIREMENTS +

4.7.4 At least two service water loops shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual,

power operated or automatic) servicing safety related equipment that

is not locked, sealed, or otherwise secured in position, is in its

correct position.

.

SUMMER - UNIT 1 3/4 7-12 Amendment No. 21 271

2017 NRC (15-01)

82. Given the following plant conditions:

Time 1000:

100% power initially.

A large break LOCA occurred.

Several Equipment malfunctions occurred.

RB pressure was 40 psig and increasing.

Time 1018:

RB pressure was 60 psig and increasing.

Core exit TCs were 690°F and increasing.

NR RVLIS was 40% and decreasing.

Time 1025:

Core exit TCs were 750°F and increasing.

NR RVLIS was 39% and decreasing.

Personnel reported the following valves not fully seated and blowing by:

XVB-2A, RB PURGE EXHAUST ISOLATION VALVE

XVB-2B, RB PURGE EXHAUST ISOLATION VALVE

RM-A4, RB PURGE EXHAUST was 3 mR/hr and increasing.

Which ONE of the choices below completes the following statements in accordance

with EPP-001, ACTIVATION AND IMPLEMENTATION OF EMERGENCY PLAN?

The highest EAL declaration for this event was a __(1)__ .

Conditions for the highest EAL declaration were first met at time __(2)__.

Do not consider Emergency Director Judgment as a basis for your emergency

classification.

REFERENCE PROVIDED

A. 1) Site Area Emergency.

2) 1018.

B. 1) Site Area Emergency.

2) 1025.

C. 1) General Emergency.

2) 1018.

D. 1) General Emergency.

2) 1025.

Monday, September 25, 2017 8:31:00 AM 82

EPP-001, Activation and Implementation of Emergency Plan, Attachment I, EAL Classification

Matrix, Revision 31 provided as a reference for Questions 82 and 99.

2017 NRC (15-01)

83. Given the following plant conditions:

Time 0030:

Mode 4.

XTF0005, UNIT 2 ENGINEERED SAFEGUARD TRANSFORMER was

inoperable and tagged out.

XTF0004, UNIT 1 ENGINEERED SAFEGUARD TRANSFORMER was in

service.

A fire occurred due to leaking oil on the exterior of XTF0004 and an actuation of

the associated deluge system occurred.

Upstream power sources to XTF0004 were disconnected to deenergize the

transformer.

Time 0130:

The 230 KV section of STP-125.001, STP-125.001 ELECTRIC POWER

SYSTEMS WEEKLY TEST was completed satisfactorily.

Time now 0200:

Bus 1DA is being powered from XTF5052, ALTERNATE AC SOURCE

TRANSFORMER.

Which ONE of the following identifies the latest time at which the completion of the

230 KV section of STP-125.001 is next required to satisfy an action statement, if at

all?

REFERENCE PROVIDED

A. Further performance is not required.

B. 0830.

C. 0930.

D. 1130.

Monday, September 25, 2017 8:31:00 AM 83

Qs 83 and 90

314.8 ELECTRICAL POWER SYSTEMS

3/4.8.1 A.C. SOURCES

OPERATING

LIMITING CONDITION FOR OPERATION

3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a. ~ Two physically independent circuits between the offsite transmission network and

the onsite Class I E distribution system, and

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

A ~iiate day fuel tank containing a minimum-volume 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 ofisite circuit of 3.8.1.1.a inoperable:

1. Demonstrate the OPERABILITY of the remaining offsiteA.C. 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

S.n~ 2.

once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter, and

If either EDG 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 EDG 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 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s- 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

hours thereafter, and , -

2. If the EDG became inoperable due to any cause other than preplanned

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

(U, * Completion of Action b.2 is required regardless of when the inoperable EDG is restorecilo

OPERABILITY.

SUMMER- UNIT 1 3/4 8-1 Amendment No. 50, 77,

84.03.150. ~54

281

ELECTRICAL POWER SYSTEMS

Qs 83 and 90

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

hours.

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

hours, 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

hours.

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 preplanned 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

hours.

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, 164,

178

282

Qs 83 and 90

ELECTRICAL POWER SYSTEMS

LIMITING CONDITION FOR OPERATION (Continued)

ACTION: (Continued) :

d. :- With two of the required offsite A. C. circuits inoperable:

1. Demonstrate the OPERABILITY of the two LOGs by sequentially

performing Surveillance Requirement 4.8.LL2.a.3 on both

~wjitiin8hours, unless the EDOs are alreaiiy 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.

e. With two of the above required EDGs inoperable:

1. Demonstrate the OPERABILITY of two offsite At. circuits 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. Restore one of the inoperable EDGs 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 COU 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 EDO, 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.

SURVEI LLANCE REQUIREMENTS

4.8.1.1.1 Lath of the above required physically independent circuits between

the offsite traflsmission 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.

S

SU*IER - UNIT 1 3/4 8-2a AJIENDMENT NO. 77, 98

4 283

2017 NRC (15-01)

84. Initial conditions:

A large break LOCA has occurred.

"C" Charging pump is inoperable and out of service for motor replacement.

The actions of EOP-2.2, ES-1.3 TRANSFER TO COLD LEG RECIRCULATION

are complete.

Current conditions:

EOP-2.0, E-1 LOSS OF SECONDARY OR REACTOR COOLANT is in progress.

The 1DA NORM FEED opened and "A" EDG failed to start.

"B" RHR pump tripped and cannot be restarted.

"B" Charging pump tripped and cannot be restarted.

Core Exit TCs are 650°F and increasing.

NR RVLIS is 40% and decreasing.

Which ONE of the following describes the procedures that the CRS will implement to

mitigate the given conditions?

A. Go to EOP-14.1, FR-C.2 RESPONSE TO DEGRADED CORE COOLING and

implement actions of AOP-102.2, LOSS OF CHARGING in parallel.

B. Go to EOP-14.1, FR-C.2 RESPONSE TO DEGRADED CORE COOLING and

implement actions of AOP-304.1A, LOSS OF BUS 1DA WITH THE DIESEL NOT

AVAILABLE in parallel.

C. Go to EOP-2.4, ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION.

and implement actions of AOP-102.2, LOSS OF CHARGING in parallel.

D. Go to EOP-2.4, ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION.

and implement actions of AOP-304.1A, LOSS OF BUS 1DA WITH THE DIESEL

NOT AVAILABLE in parallel.

Monday, September 25, 2017 8:31:00 AM 84

2017 NRC (15-01)

85. Initial conditions:

100% initially.

A Large break LOCA occurred in the RB

Operators were taking actions in EOP-2.0, E-1 LOSS OF REACTOR

SECONDARY COOLANT.

Operators then transferred to EOP-17.1 RESPONSE TO REACTOR BUILDING

FLOODING based on an ORANGE status for the CONTAINMENT Critical Safety

Function.

Current conditions:

RB pressure is 15 psig and decreasing.

The CRS has just directed Chemistry to sample the RB sump.

The NROATC reports the following:

- The CONTAINMENT ORANGE Critical Safety Function status is still in effect

due to RB level.

- Both RB Spray pumps have tripped.

Which ONE of the following identifies the action the CRS will direct next?

A. Complete actions in EOP-17.1, then transfer to EOP-17.0, RESPONSE TO HIGH

REACTOR BUILDING PRESSURE.

B. Do not complete actions in EOP-17.1; Transfer to EOP-17.0, RESPONSE TO

HIGH REACTOR BUILDING PRESSURE.

C. Continue to direct actions in EOP-17.1 until the CONTAINMENT ORANGE status is

corrected.

D. Complete actions in EOP-17.1, then return to EOP-2.0.

Monday, September 25, 2017 8:31:00 AM 85

2017 NRC (15-01)

86. Given the following plant conditions:

Time 0700:

A shutdown and cooldown is in progress for a refueling outage in accordance

with GOP-6 PLANT SHUTDOWN FROM HOT STANDBY TO COLD

SHUTDOWN (MODE 3 TO MODE 5).

RCS temperature is 305°F and decreasing.

"A" and "B" Charging Pumps are OPERABLE.

The "C" Charging Pump breaker is in the racked down position.

Time 0800:

RCS temperature is 290°F and decreasing.

Operators are preparing to place "B" RHR loop in service in cooldown mode.

"A" Charging pump is in service for normal charging.

Which ONE of the choices below completes the following statements in accordance

with T.S.3.5.3, ECCS SUBSYTEMS - TAVG <350°F?

Between 0700 and 0800 __(1)__.

The basis for this is that mass addition to the RCS must be restricted to within a

minimum relief capability of __(2)__.

A. 1) the "B" Charging Pump breaker was racked down and the pump was declared

inoperable.

2) one (1) RHR suction relief.

B. 1) the "B" Charging Pump breaker was racked down and the pump was declared

inoperable.

2) two (2) RHR suction reliefs.

C. 1) the "A" RHR pump control switch was placed in PULL-TO-LOCK and the pump

was declared inoperable.

2) one (1) RHR suction relief.

D. 1) the "A" RHR pump control switch was placed in PULL-TO-LOCK and the pump

was declared inoperable.

2) two (2) RHR suction reliefs.

Monday, September 25, 2017 8:31:00 AM 86

2017 NRC (15-01)

87. Given the following plant conditions:

A refueling outage is in progress.

Plant is in MODE 6.

"A" RHR train is in service.

FI-605A, PUMP A FLOW GPM reads 1900 gpm.

Which ONE of the choices below completes the following statements in accordance

with T.S. 3.9.7.1, RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION -

HIGH WATER LEVEL?

In order to meet the requirements of 3.9.7.1, RHR flow, as read on FI-605A, must be

adjusted higher by a minimum of ___(1)___ gpm.

A basis for this requirement is to ___(2)___.

A. 1) 100

2) maintain the RCS bulk fluid temperature less than the upper limit of 170°F during

refueling.

B. 1) 100

2) to minimize the effects of a boron dilution incident and prevent boron

stratification.

C. 1) 900

2) maintain the RCS bulk fluid temperature less than the upper limit of 170°F during

refueling.

D. 1) 900

2) to minimize the effects of a boron dilution incident and prevent boron

stratification.

Monday, September 25, 2017 8:31:00 AM 87

2017 NRC (15-01)

88. Given the following plant conditions:

Time 0500:

Mode 3.

A malfunction of the static transfer switch caused a loss of voltage on bus

APN-5903.

Time 0600:

APN-5903 has been reenergized from the Alternate power source (1FB) at

XIT-5903 in accordance with SOP-310, ENGINEERED SAFETY FEATURES

120 VAC INSTRUMENTATION AND CONTROL POWER SYSTEM.

- Actions of STP-506.013, DE-ENERGIZATION OF THE ESF LOAD

SEQUENCER LOSS OF VOLTAGE RELAYS B TRAIN, XEG0001B were

completed as directed by SOP-310.

Time 1800:

RCS temperature is 240°F.

"A" RHR loop for cooldown mode.

A loss of offsite power (115 KV and 230 KV) occurred.

System Control does not expect offsite power restoration for several hours.

A valid XCP-640, 1-1, BUS 1DA O/C 51BX-1DA annunciator is in alarm.

XTF5052, ALTERNATE AC SOURCE TRANSFORMER is not available.

Which ONE of the following identifies the procedure the CRS will enter next and the

action in that procedure that will be performed first?

A. AOP-304.4, ARG-4, LOSS OF ALL ESF AC POWER WHILE ON RHR COOLING;

Start "B" EDG from the Main Control Boards.

B. AOP-304.4, ARG-4, LOSS OF ALL ESF AC POWER WHILE ON RHR COOLING;

Record as found switch positions and place 1DB loads in PULL TO LK NON-A.

C. AOP-304.1A, LOSS OF BUS 1DA WITH THE DIESEL NOT AVAILABLE;

Record as found switch positions and place 1DA loads in PULL TO LK NON-A.

D. AOP-304.1B, LOSS OF BUS 1DB WITH THE DIESEL NOT AVAILABLE;

Start an "A" Train CCW pump.

Monday, September 25, 2017 8:31:00 AM 88

2017 NRC (15-01)

89. Given the following plant conditions:

A loss of Feedwater pump control caused an increase in feedwater flow.

An automatic reactor trip occurred as a result of a turbine trip.

All MSIVs are closed.

Operators have entered EOP-15.1, STEAM GENERATOR OVERPRESSURE.

Secondary radiation is normal.

Steam Generator (SG) Narrow Range Levels are as follows:

"A"- 95% and increasing.

"B"- 60% and stable.

"C"- 63% and stable.

SG Pressures are as follows:

"A"- 1235 psig and increasing.

"B"- 1130 psig and stable.

"C"- 1130 psig and stable.

Which ONE of the following describes the procedure and the action that the CRS will

use to mitigate the above conditions?

The CRS will:

A. Remain in EOP-15.1, STEAM GENERATOR OVERPRESSURE and use manual

control of the A SG PORV to reduce SG pressure to less than SG Safety

setpoints.

B. Remain in EOP-15.1, STEAM GENERATOR OVERPRESSURE and initiate

blowdown from the A Steam Generator.

C. Transition to EOP-15.2, STEAM GENERATOR HIGH LEVEL and use manual

control of the A SG PORV to reduce SG pressure to less than the SG Safety

setpoints.

D. Transition to EOP-15.2, STEAM GENERATOR HIGH LEVEL and initiate blowdown

from the A Steam Generator.

Monday, September 25, 2017 8:31:00 AM 89

2017 NRC (15-01)

90. Time 0500 on 10/5:

Plant was in Mode 3.

The "A" RHR Pump was tagged out for an inspection.

Due to a malfunction, operators attempted to close the BUS 1DB DG FEED

breaker for a monthly load test 180° out of phase.

Breakers BUS 1DB DG FEED and BUS 1DB NORM FEED immediately opened.

Time 0515 on 10/5:

BUS 1DB DG FEED Breaker and BUS 1DB NORM FEED Breakers were

declared inoperable as of 0500 pending further evaluations.

Time 0530 on 10/5:

Electricians reported no visible damage to bus 1DB switchgear.

1DA is energized via BUS 1DA NORM FEED.

1DB was reenergized via BUS 1DB ALT FEED.

Evaluations of breakers BUS 1DB DG FEED and 1DB NORM FEED remain

pending.

Maintenance reports that "A" RHR pump must remain tagged out based on the

result of the inspection.

Which ONE of the following identifies the earliest time that the plant is required to be

in COLD SHUTDOWN in accordance with T.S. 3.8.1, AC SOURCES - OPERATING?

REFERENCE PROVIDED

A. 1300 on 10/6.

B. 1500 on 10/6.

C. 1900 on 10/6.

D. 2300 on 10/6.

Monday, September 25, 2017 8:31:00 AM 90

See reference provided for

question 83.

2017 NRC (15-01)

91. Initial conditions:

100% power initially.

A trip of all Feedwater pumps occurred.

The reactor tripped.

All EFW pumps failed to start automatically or manually.

Current conditions:

EOP-15.0, FR-H.1 RESPONSE TO A LOSS OF SECONDARY HEAT SINK is in

progress.

Operators are taking action to restore SG feed via condensate.

RB pressure is 0.5 psig.

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

accordance with EOP-15.0 and the associated bases?

In the current condition, operators are required to go to steps to implement bleed and

feed at wide range SG levels of __(1)__ .

In accordance with the bases, the specific steam generator level at which operators

must immediately go to bleed and feed steps __(2)__.

A. 1) 20%.

2) indicates dry out is occurring and a limited time remains to complete these steps

before inadequate core cooling conditions develop.

B. 1) 20%.

2) ensures that the remaining liquid inventory in the steam generators will maintain

secondary heat removal while bleed and feed steps are performed.

C. 1) 12%.

2) indicates dry out is occurring and a limited time remains to complete these steps

before inadequate core cooling conditions develop.

D. 1) 12%.

2) ensures that the remaining liquid inventory in the steam generators will maintain

secondary heat removal while bleed and feed steps are performed.

Monday, September 25, 2017 8:31:00 AM 91

2017 NRC (15-01)

92. Initial conditions:

Mode 3.

TAVG is 557°F, stable.

Pressurizer level indications are as follows:

LI-459A 25%, stable.

LI-460 25%, stable.

LI-461 25%, stable.

FCV-122, CHG FLOW controller is in AUTO, output is 36%, stable.

Current conditions:

TAVG is 557°F, stable and has remained unchanged.

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

Pressurizer level indications are as follows:

LI-459A 25%, stable.

LI-460 20%, stable.

LI-461 20%, stable.

FCV-122, CHG FLOW controller is in AUTO, output is 36%, stable and has

remained unchanged.

Which ONE of the choices below completes the following statements in accordance

with T.S. 3.3.1, REACTOR TRIP INSTRUMENTATION?

The Minimum OPERABLE Channels requirement for the High Pressurizer Level trip

function when the applicable MODE is reached __(1)__ be met.

The highest plant Mode in which the plant is allowed in accordance with Technical

Specifications in the current condition is __(2)__.

Assume any Technical Specification action statement in effect is satisfied.

REFERENCE PROVIDED

A. 1) will

2) Mode 1.

B. 1) will

2) Mode 2.

C. 1) will not

2) Mode 2.

D. 1) will not

2) Mode 3.

Monday, September 25, 2017 8:31:00 AM 92

. . .

Q 92

IABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION

MINIMUM

TOTAL NO. CHANNELS CHANNELS APPLICABLE

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

H. Pressurizer Water Level--High 3 2 2 1 6~

12. A. Loss of Flow - Single Loop 3/loop 2/loop in 2/loop In

(Above P-8) any oper- each oper-

ating loop ating loop

B. Loss of Flow - Two Loops 3/loop 2/loop In 2/loop

(Above P-i and below P-B) two oper- each oper-

ating loops ating loop

13. Steam Generator Water 3/loop 2/loop in 2/loop in 1, 2 6

Level--Low-Low any oper- , each opet-

ating loops ating loop

14. Steam/Feedwater Flow 2/loop-level I/loop-level 1/loop-level 1, 2

Mismatch and Low Steam and coincident and

Generator Water Level 2/loop-flow with 2/loop-flow;

mismatch in 1/loop-flow mismatch In

each loop mismatch in same loop or

same loop 2/loop-level

and

1/loopflow

mismatch in

same loop

S

315

Q 92

TABLE 3.3-1 (Continued)

TABLE NOTATION

With the reactor trip system breakers in the closed position and the control rod drive

system capable of rod withdrawal.

The provisions of Specification 3.0.4 are not applicable.

1. Below the P-6 (Intermediate Range Neutron Flux Interlock) setpoint.

1. 1. Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

- - - Values left blank pending NRC approval of 2 loop operation.

ACTION STATEMENTS

ACTION 1 - With the number of OPERABLE channels one less than the Minimum

Channels OPERABLE requirement, restore the inoperable channel to

OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-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 .

ACTION 2 - With the number of OPERABLE channels one less than the Total Number of

Channels, STARTUP and/or POWER OPERATION may proceed provided the

following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 72

hours.

b. The Minimum Channels OPERABLE requirement is met; however, the

inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for

surveillance testing of other channels per Specification 4.3.1.1.

c. Either, THERMAL POWER is restricted to less than or equal to 75% of

RATED THERMAL POWER and the Power Range Neutron Flux trip

setpoint is reduced to less than or equal to 85% of RATED THERMAL

POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is

monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

SUMMER - UNIT 1 3/4 3-6 Amendment No. 101, 177

316

Q 92

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 3 - With the number of channels OPERABLE one less than the Minimum

Channels OPERABLE requirement and with the THERMAL POWER level:

a. Below the P-6 (Intermediate Range Neutron Flux Interlock) setpoint,

restore the inoperable channel to OPERABLE status prior to

increasing THERMAL POWER above the P-6 Setpoint.

b. Above the P-6 (Intermediate Range Neutron Flux Interlock) setpoint

but below 10 percent of RATED THERMAL POWER, restore the

inoperable channel to OPERABLE status prior to increasing

THERMAL POWER above 10 percent of RATED THERMAL POWER.

ACTION 4 - With the number of OPERABLE channels one less than the Minimum

Channels OPERABLE requirement suspend all operations involving positive

reactivity changes.

ACTION 5 - With the number of OPERABLE channels one less than the Minimum

Channels OPERABLE requirement, verify compliance with the SHUTDOWN

MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6 - With the number of OPERABLE channels one less than the Total Number of

Channels, STARTUP and/or POWER OPERATION may proceed provided the

following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 72

hours; and

b. The Minimum Channels OPERABLE requirement is met; however, the

inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for

surveillance testing of other channels per Specification 4.3.1.1.

ACTION 7 - With less than the Minimum Number of Channels OPERABLE, within one

hour determine by observation of the associated permissive annunciator

window(s) that the interlock is in its required state for the existing plant

condition, or apply Specification 3.0.3.

SUMMER - UNIT 1 3/4 3-7 Amendment No. 101, 177

317

2017 NRC (15-01)

93. Initial conditions:

100% power initially.

IPV02000-MS, MAIN STEAM HEADER A POWER RELIEF VALVE failed

partially open and could not be closed from the Main Control Board.

The crew manually tripped the reactor.

Current conditions:

Operators implemented EOP-3.0, E-2 FAULTED STEAM GENERATOR

ISOLATION.

Operators then transferred from EOP-3.0 to EOP-2.0, E-1 LOSS OF REACTOR

OR SECONDARY COOLANT.

Pressurizer level is 5% and decreasing.

RCS pressure is 1765 psig and decreasing.

RCS Tcold temperatures are 510°F and decreasing at 1°F/ minute.

The CRS has read step 14, "Check if pressure in all SGs is stable OR

increasing" and the BOP reports the following:

"SG "A" pressure is 200 psig and decreasing at 100 psig/minute.

"SG "B" and SG "C" pressures are 730 psig and decreasing at 6 psig/

minute."

Which ONE of the following identifies the procedure use by the CRS for the conditions

given above and the reason?

The CRS will:

A. return to Step 1 of EOP-2.0 to allow a re-checking of SI reduction criteria and to

allow a transfer to EOP-1.2, ES-1.1 when conditions are met.

B. continue on in EOP-2.0 then transition later to EOP-2.1, ES-1.2 POST-LOCA

COOLDOWN AND DEPRESSURIZATION to establish conditions for placing RHR

in service.

C. transition to EOP-3.0, E-2 FAULTED STEAM GENERATOR ISOLATION to perform

isolation of additional faulted steam generators.

D. transition to EOP-3.0, E-2 FAULTED STEAM GENERATOR ISOLATION, then to

EOP-3.1 ECA-2.1 UNCONTROLLED DEPRESSURIZATION OF ALL STEAM

GENERATORS to address a fault of all three steam generators.

Monday, September 25, 2017 8:31:00 AM 93

2017 NRC (15-01)

94. Given the following plant conditions:

Time is now 0100 on 9/1.

Reactor power is 100%.

A surveillance of Primary Chemistry has just been completed in accordance with

T.S. 3.4.7, REACTOR COOLANT SYSTEM - CHEMISTRY.

Results were satisfactory.

Which ONE of the choices below completes the following statements in accordance

with T.S. 3.4.7?

The maximum limit for Chloride in the RCS in the current mode is ___(1)___.

The latest allowed time when the surveillance described above can next be

performed is ___(2)___ in accordance with Technical Specifications.

REFERENCE PROVIDED

A. 1) 0.10 ppm.

2) 0100 on 9/4.

B. 1) 0.10 ppm.

2) 1900 on 9/4.

C. 1) 0.15 ppm.

2) 0100 on 9/4.

D. 1) 0.15 ppm.

2) 1900 on 9/4.

Monday, September 25, 2017 8:31:00 AM 94

Q 94

I

REACTOR COOLANT SYSTEM

TABLE 4.4-3 -

CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS

SAMPLE AND

PARAMETER - - ANALYSIS FREQUENCY

DISSOLVED OXYGENIt - At least oncijâr 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

CHLORIDE At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

FLUORIDE At- least -once- per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

I

~lot t~uindwithT ~ 250F

I

SUPPlER - UNIT 1 3/4 4-24

326

2017 NRC (15-01)

95. Initial conditions:

100% power initially.

A small break LOCA occurred.

Charging pumps did not start automatically or manually.

Current conditions:

Operators are taking action in accordance with EOP-14.0, FR-C.1 RESPONSE

TO INADEQUATE CORE COOLING.

The CRS is reading step 2.a, alternative action, "Start pumps and align valves

as necessary to establish SI flow. REFER TO ATTACHMENT 2,

ESTABLISHING SI FLOW".

Which ONE of the choices below completes the following statements?

In accordance with OAP-103.4, EOP/FSP/AOP USER'S GUIDE, the CRS __(1)__

allowed to assign a board operator to perform Attachment 2 independently.

After this step, the next action that will be performed to increase core cooling will be to

__(2)__.

A. 1) is not

2) start reactor coolant pumps.

B. 1) is not

2) depressurize steam generators.

C. 1) is

2) start reactor coolant pumps.

D. 1) is

2) depressurize steam generators.

Monday, September 25, 2017 8:31:00 AM 95

2017 NRC (15-01)

96. Given the following plant conditions:

An operator was performing preventative maintenance on a newly installed piece

of non-safety related equipment.

The operator determined that the procedure could not be completed as written in

the current plant conditions.

A change to the procedure has been drafted and routed for review as a

TEMPORARY APPROVAL.

- The change does not alter the scope or intent of the original procedure or

alter any P/CAP item.

Which ONE of the following describes the final review and approval before a working

copy is created for the TEMPORARY APPROVAL in accordance with VCS-SAP-0139,

DOCUMENT REVIEW AND APPROVAL PROCESS?

A. The Shift Manager reviews and agrees with the change, then any member of Plant

Management staff, who must be a Qualified Reviewer, reviews and approves the

change.

B. The Shift Manager reviews and agrees with the change, then a Plant Manager who

is listed as the Approval Authority in VCS-SAP-139, reviews and approves the

change.

C. A member of Plant Management staff, who is also qualified Quality Reviewer,

reviews and agrees with the change, then the Shift Manager reviews and approves

the change.

D. A member of Plant Management staff, who is also a qualified Quality Reviewer,

reviews and agrees, then a CRS assigned as Designated Supervisor reviews and

approves the change.

Monday, September 25, 2017 8:31:00 AM 96

2017 NRC (15-01)

97. Given the following plant conditions:

The plant is being cooled down for a refueling outage.

RCS temperature is 195°F and lowering.

RCS pressure is 375 psig and stable.

Which ONE of the choices below completes the following statements in accordance

with T.S. 3.7.6, CONTROL ROOM EMERGENCY FILTRATION SYSTEM (CREFS)?

In the current conditions, the OPERABILITY of CREFS must be maintained to ensure

that control room occupancy does not result in more than a maximum of __(1)__ rem,

after the __(2)__ that is assumed in the bases for T.S. 3.7.6.

A. 1) 5

2) loss of coolant accident

B. 1) 5

2) rupture of an outside Waste Gas Decay tank

C. 1) 25

2) loss of coolant accident

D. 1) 25

2) rupture of an outside Waste Gas Decay tank

Monday, September 25, 2017 8:31:00 AM 97

2017 NRC (15-01)

98. Given the following plant conditions:

Today is September 15th (9/15).

A release of a Waste Monitor Tank is planned.

The Liquid Waste Release Permit (LWRP) has just been brought to you for

approval.

You have informed that it was just discovered that the quarterly STP-360.064,

LIQUID WASTE EFFLUENT LIQUID RADIATION MONITOR (RML0005)

OPERATIONAL TEST was not performed within the last six months.

RM-L9, LIQUID RAD MON, LIQUID WASTE EFFLUENT is OPERABLE.

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

The release permit __(1)__ be approved with only RM-L9 in service.

The latest date by which STP-360.064 for RM-L5 must next be performed in

compliance with the Technical Specification 4.0 requirement for a missed surveillance

is __(2)__ .

Assume that a risk assessment show minimal risk due to continued operation.

A. 1) can

2) 9/16

B. 1) can

2) 12/16

C. 1) cannot

2) 9/16

D. 1) cannot

2) 12/16

Monday, September 25, 2017 8:31:00 AM 98

2017 NRC (15-01)

99. Given the following plant conditions:

Time 1000:

The plant is an outage with a plant status of No Mode.

The RCS is being drained to allow an inspection of the lower Reactor Vessel

internals.

Time 1030:

230 KV power is lost due to a grid disturbance.

An overcurrent lockout occurs on bus 1DX.

Time 1045:

Electricians cannot estimate a time for restoration of 1DX.

"B" EDG stopped due to a governor failure.

Which one of the choices answers both of the following questions?

1) What was the highest EAL classification condition that was met in accordance with

EPP-001 ACTIVATION AND IMPLEMENTATION OF EMERGENCY PLAN.

2) Was the Technical Support center required to be activated for the above

conditions?

Do not consider Emergency Director Judgment as a basis for your emergency

classification.

REFERENCE PROVIDED

A. 1) Alert

2) Yes.

B. 1) Alert.

2) No.

C. 1) Unusual Event

2) Yes.

D. 1) Unusual Event

2) No.

Monday, September 25, 2017 8:31:00 AM 99

EPP-001, Activation and Implementation of Emergency Plan, Attachment I, EAL Classification

Matrix, Revision 31 provided as a reference for Questions 82 and 99.

2017 NRC (15-01)

100. Given the following plant conditions:

A emergency has occurred at V.C. Summer station.

The Shift Manager is acting as the Interim Emergency Director (IED).

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

1) What is the lowest EAL declaration at which Protective Action Recommendations

(PARs) are required to be determined?

2) What is a condition that will require the IED to recommend Impediment PARs?

A. 1) General Emergency

2) A report from Security that a Hostile Action is in progress.

B. 1) General Emergency

2) A report from local Law Enforcement that hazardous road conditions exist.

C. 1) Site Area Emergency.

2) A report from Security that a Hostile Action is in progress.

D. 1) Site Area Emergency.

2) A report from local Law Enforcement that hazardous road conditions exist.

You have completed the test!

Monday, September 25, 2017 8:31:00 AM 100

ANSWER KEY REPORT

for 2017 NRC (15-01) Test Form: 0

Answers

0

1 B

2 B

3 A

4 D

5 C

6 D

7 A

8 B

9 B

10 C

11 C

12 B

13 B

14 B

15 C

16 D

17 A

18 A

19 B

20 C

21 D

22 B

23 B

24 D

25 A

26 A

27 C

28 A

29 A

30 C

31 B

32 D

33 A

34 D

35 A

36 C

37 C

38 D

39 B

40 B

41 C

42 C

43 C

44 D

45 A

46 A

47 B

Thursday, September 28, 2017 1:01:31 PM 1

ANSWER KEY REPORT

for 2017 NRC (15-01) Test Form: 0

Answers

0

48 C

49 B

50 D

51 C

52 D

53 A

54 D

55 C

56 B

57 D

58 C

59 A

60 D

61 A

62 C

63 B

64 C

65 A

66 A

67 C

68 A

69 D

70 A

71 B

72 B

73 C

74 D

75 A

76 A

77 C

78 B

79 C

80 A

81 B

82 D

83 C

84 D

85 B

86 A

87 D

88 B

89 D

90 A

91 C

92 C

93 A

94 D

Thursday, September 28, 2017 1:01:31 PM 2

ANSWER KEY REPORT

for 2017 NRC (15-01) Test Form: 0

Answers

0

95 D

96 C

97 B

98 B

99 D

100 A

Thursday, September 28, 2017 1:01:31 PM 3

ML17298A572

Text

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