ML15278A228

2015-09 Final Written Examination

ML15278A228
Person / Time
Site:	Waterford
Issue date:	09/14/2015
From:	Gaddy A Operations Branch IV
To:
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Download: ML15278A228 (109)

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2015 NRC Exam RO Written Exam RO 1 Given:

Plant is at 100% power SG ILR 1111, Steam Generator 1 Downcomer Level, fails high Crew has entered OP-901-201, Steam Generator Level Control Malfunction Upon a reactor trip, Main Feed Pump A speed will reduce automatically. This design feature was added to reduce the differential pressure across the ____(1)____ valves.

Upon subsequent entry into OP-902-001, Reactor Trip Recovery procedure, the Main Feed Pump A speed controller (FW IHIC1107) will be controlled in the _____(2)_____

mode.

(1) (2)

A. Main Feed Regulating automatic B. Main Feed Isolation automatic C. Main Feed Regulating manual D. Main Feed Isolation manual Facility: Waterford 3 Page 1 of 75

2015 NRC Exam RO Written Exam RO 2 The plant was at 100% power when Pressurizer Safety Valve, RC-317A, failed open.

The crew tripped the reactor and initiated SIAS and CIAS.

The following conditions exist:

RCS pressure is 1340 psia and stable Reactor Coolant Pumps have been secured CET is 556°F, Thot is 550°F, Tcold is 543°F (all stable)

Pressurizer level is 70% and rising Quench Tank pressure is 20 psig with the Quench Tank rupture disc intact.

QSPDS indicates reactor head level 1 voided Steam Generator (SG) 1 and 2 pressures are 980 psia and stable SG 1 and 2 levels are 60% WR and slowly lowering The expected temperature indication of the Pressurizer Relief Line is ____(1)____ °F.

The crew ______(2)______ throttle close Train B High Pressure Safety Injection flow control valves.

(1) (2)

A. 258 will not B. 228 will not C. 258 will D. 228 will Facility: Waterford 3 Page 2 of 75

2015 NRC Exam RO Written Exam RO 3 Given:

Small Break LOCA has occurred and the crew has diagnosed to OP-902-002, LOCA Recovery Procedure Pressurizer pressure is 1690 PSIA and slowly lowering Containment pressure is 17.4 psia and slowly rising Containment temperature is 210°F Which of the following ESFAS signal(s) will have been generated?

A. MSIS only B. SIAS and CIAS only C. SIAS, CIAS, and MSIS only D. SIAS, CIAS, MSIS, and CSAS Facility: Waterford 3 Page 3 of 75

2015 NRC Exam RO Written Exam RO 4 Given:

A LOCA has occurred RCS pressure is 100 PSIA The crew is performing OP-902-002, Loss of Coolant Accident Recovery The following alarms are received on Control Room Cabinet K:

o K-19, RAS TRAIN A LOGIC INITIATED o K-20, RAS TRAIN B LOGIC INITIATED The crew will verify that Refueling Water Storage Pool level is _____(1)______ percent.

If required, a manual initiation of an RAS can be performed _____(2)______.

(1) (2)

A. 10 from the local ESFAS cabinet only B. 10 from CP-7 or local ESFAS cabinet C. 15 from the local ESFAS cabinet only D. 15 from CP-7 or local ESFAS cabinet Facility: Waterford 3 Page 4 of 75

2015 NRC Exam RO Written Exam RO 5 Given:

The reactor was manually tripped due to 1A RCP ARRD High Temperature 1A RCP has been secured Five minutes later, the ATC reports that the RCP PMC Mimic indicates RCP 1A speed is 600 rpm OP-901-130, Reactor Coolant Pump Malfunction, provides the guidance to trip the reactor if ARRD temperature exceeds ____(1)____ °F. Based on the above conditions, the crew will ______(2)______.

(1) (2)

A. 225 only continue to monitor RCP 1A for reverse rotation B. 210 only continue to monitor RCP 1A for reverse rotation C. 225 remove all reactor coolant pumps from service D. 210 remove all reactor coolant pumps from service Facility: Waterford 3 Page 5 of 75

2015 NRC Exam RO Written Exam RO 6 Given:

Plant is at 50% power A loss of all Charging Pumps has occurred The crew will verify closed ____(1)____ in accordance with ______(2)______.

(1) (2)

A. Letdown Inside Containment OP-901-110, Pressurizer Level Isolation, CVC-103 Control Malfunction B. Letdown Stop Valve, CVC-101 OP-901-110, Pressurizer Level Control Malfunction C. Letdown Stop Valve, CVC-101 OP-901-112, Charging or Letdown Malfunction D. Letdown Inside Containment OP-901-112, Charging or Letdown Isolation, CVC-103 Malfunction Facility: Waterford 3 Page 6 of 75

2015 NRC Exam RO Written Exam RO 7 Given:

The plant is in Mode 5 with Shutdown Cooling Train A in service A loss of Instrument Air has occurred SI-129A, LPSI Pump A Discharge Flow Control, is not accessible due to plant conditions The crew will direct the Operator to force closed SI-129A using a (an) ____(1)____

accumulator. Manipulation of the required 3-way valve will be performed

______(2)______.

(1) (2)

A. nitrogen gas from the -35 hallway outside of Safeguards Room A B. instrument air from the RAB -15 Valve Gallery C. instrument air from the -35 hallway outside of Safeguards Room A D. nitrogen gas from the RAB -15 Valve Gallery Facility: Waterford 3 Page 7 of 75

2015 NRC Exam RO Written Exam RO 8 Given:

CCW Surge Tank Level Switch CC-ILS-7013A failed low CC-200A/727, CCW Hdr A TO AB Supply and Return Isolations, failed closed CC-134 A, CCW A Dry Cooling Tower Bypass failed open CC-135 A, CCW A Dry Cooling Tower Isolation, failed closed Both Train A and Train B CC-620, Fuel Pool Heat Exchanger Temperature Control Valve, control switches are in the CONTROL position at CP-8 Based on this level switch failure, A. Spent Fuel Pool temperature will rise since CC-620 failed closed.

B. Spent Fuel Pool temperature will lower since CC-134 A, CCW A Dry Cooling Tower Bypass failed open.

C. Spent Fuel Pool temperature will rise since CC-135 A, CCW A Dry Cooling Tower Isolation, failed closed.

D. Spent Fuel Pool temperature is controlled in automatic since the Train B CC-620 control switch is in CONTROL.

Facility: Waterford 3 Page 8 of 75

2015 NRC Exam RO Written Exam RO 9 Given:

The plant is at 100% power Control Systems are in normal 100% power alignments The Pressurizer Pressure Controller, RC-IPIC-0100, output fails HIGH Assuming no action by the crew, a reactor trip will occur first due to ____(1)____

Pressurizer Pressure generated by ______(2)______.

(1) (2)

A. high PPS B. high CPCs C. low PPS D. low CPCs Facility: Waterford 3 Page 9 of 75

2015 NRC Exam RO Written Exam RO 10 Given:

Reactor power is 1%

A large steam leak upstream of MSIV B prompts the crew to trip the reactor A manual reactor trip using CP-2 pushbuttons was unsuccessful The crew tripped the reactor using the Diverse Reactor Trip System (DRTS)

All CEAs have inserted into the core The DRTS de-energized CEDM cabinets by opening the MG set ____(1)____. Boron injection ______(2)______.

(1) (2)

A. supply breakers IS required to maintain shutdown margin B. supply breakers IS NOT required because all CEAs have inserted C. load contactors IS required to maintain shutdown margin D. load contactors IS NOT required because all CEAs have inserted Facility: Waterford 3 Page 10 of 75

2015 NRC Exam RO Written Exam RO 11 Given:

A Steam Generator Tube Rupture (SGTR) has occurred in Steam Generator (SG) #2 The crew has entered OP-902-007, Steam Generator Tube Rupture Recovery Procedure, and has isolated SG #2 Steam Generator #2 level is 80% NR and is limiting the RCS cooldown The CRS directs lowering SG #2 level to 65% NR using back flow to the RCS.

RCS boron concentration is presently 1210 ppm The CRS directs the ATC to calculate final RCS boron concentration for the SG

1. 2 level reduction Prior to lowering SG#2 level using backflow, the ATC will verify ____(1)____. Final RCS boron concentration will be approximately ______(2)______ ppm.

(1) (2)

A. natural circulation conditions are 1101 being met B. at least one RCP is running 907 C. at least one RCP is running 1101 D. natural circulation conditions are 907 being met Facility: Waterford 3 Page 11 of 75

2015 NRC Exam RO Written Exam RO 12 An Excess Steam Demand event is in progress and OP-902-004, Excess Steam Demand Recovery is being implemented.

RCS Subcool Margin 80ºF and stable SG 1 pressure is 540 psia and lowering SG 2 pressure is 670 psia and stable SG 1 level 45% WR and lowering SG 2 level 60% WR and lowering slowly Containment Pressure 25 psia and rising Containment Spray Pump A is tagged out with CS-125A gagged shut Containment Spray Header B flow is 1000 gpm CVC-101, Letdown Stop Valve, is stuck open EFW-228A, Emergency Feedwater Isolation SG 1 Primary is tagged closed All other systems and components are operating as designed Based on this, which Safety Function is NOT being met?

A. RCS Pressure Control B. RCS Heat Removal C. Containment Isolation D. Containment Temperature and Pressure Control Facility: Waterford 3 Page 12 of 75

2015 NRC Exam RO Written Exam RO 13 Given:

A Loss of all Main Feedwater has occurred The crew has entered OP-902-006, Loss of Main Feedwater Recovery Procedure EFW Pump AB is the only EFW pump available The crew will secure ____(1)____. The reason for this response is to ______(2)______.

(1) (2)

A. one Reactor Coolant Pump in reduce heat input into the RCS each loop B. one Reactor Coolant Pump in prevent operating RCPs without each loop adequate NPSH C. all Reactor Coolant Pumps reduce heat input into the RCS D. all Reactor Coolant Pumps prevent operating RCPs without adequate NPSH Facility: Waterford 3 Page 13 of 75

2015 NRC Exam RO Written Exam RO 14 Given:

A Station Blackout has occurred.

The CRS has directed the BOP to restore EDG A to service in accordance with Attachment 23-A, EDG A restoration during SBO.

The minimum requirement for a single start attempt of Emergency Diesel Generator (EDG) A is _____(1)_____ psig in ______(2)_____ EDG A Air receiver(s).

(1) (2)

A. 125 both B. 125 one C. 250 both D. 250 one Facility: Waterford 3 Page 14 of 75

2015 NRC Exam RO Written Exam RO 15 Given:

A Loss of Offsite Power has occurred 30 minutes ago The crew has entered OP-902-003, Loss of Offsite Power Recovery Procedure RCS pressure is 1725 psia and slowly rising Thot is 595°F and constant CET temperature is 600°F and constant Tcold is 590°F and constant The present subcooling margin is ____(1)____ °F. The crew will verify the operating loop steam generator pressure is approximately equal to saturation pressure for the existing

______(2)______.

(1) (2)

A. 15 Thot B. 15 Tcold C. 20 Tcold D. 20 Thot Facility: Waterford 3 Page 15 of 75

2015 NRC Exam RO Written Exam RO 16 Given:

A Loss of all Offsite Power has occurred The crew has entered OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery Procedure The CRS has directed the auxiliary operator to secure TGB loads in accordance with 3 of OP-902-009, Standard Appendices.

With no turbine building battery chargers energized and no operator action, the maximum discharge time for the turbine building battery is ____(1)____ minutes.

Securing TGB loads will preserve the remote operation of the ____(2)____ bus feeder breakers.

(1) (2)

A. 30 2 B. 30 1 C. 90 1 D. 90 2 Facility: Waterford 3 Page 16 of 75

2015 NRC Exam RO Written Exam RO 17 Given:

Power is 100%

A level switch malfunction has caused the B Dry Cooling Tower to isolate and bypass.

The Control Room has entered OP-901-510, Component Cooling Water (CCW) System Malfunction A Loss of Coolant Accident occurs. Plant conditions are:

Pressurizer pressure is 1600 psia and slowly lowering Containment pressure is 17.3 psia and stable CCW heat exchanger B outlet temperature is 105 ºF If ACCW basin temperature is 80 ºF, ACC-126B, ACC Hdr B CCW HX Outlet Temp Control valve, will be ____(1)____ . This occurs to ______(2)______.

(1) (2)

A. open conserve ultimate heat sink water supply B. closed conserve ultimate heat sink water supply C. open ensure proper component cooling in the Wet mode D. closed ensure proper component cooling in the Wet mode Facility: Waterford 3 Page 17 of 75

2015 NRC Exam RO Written Exam RO 18 Given:

Power is 100%

Main Generator load is 1200 MW; 200 MVAR out Pine Bluff System Operations Center informed the control room that grid parameters are outside of the prescribed operating range The crew has entered OP-901-314, Degraded Grid Conditions and TRM 3.8.1.1 due to predicted post-trip offsite AC circuit voltage < 223KV The concern with a degraded grid (low voltage) is ______(1)______.

To help stabilize the grid, the CRS orders raising main generator voltage. The BOP will

____(2)____ reactive load (MVARs).

(1) (2)

A. degraded voltage relay raise reliability on the safety bus B. degraded voltage relay lower reliability on the safety bus C. emergency core cooling raise system motor overheating D. emergency core cooling lower system motor overheating Facility: Waterford 3 Page 18 of 75

2015 NRC Exam RO Written Exam RO 19 Given:

Reactor Power is 10% with power ascension in progress Reg Group 6 is being withdrawn manually in Manual Group mode to raise power to 15%

The ATC releases the IN-HOLD-OUT switch at 135 and Reg Group 6 CEA#

20 continues outward movement. The remaining Reg Group 6 CEAs indicate 135 The operator will FIRST ____(1)____ . If CEA 20 has stopped outward motion at 143 the crew will be required to ______(2)______ in accordance with the guidance in OP-901-102, CEA or CEDMCS Malfunction.

(1) (2)

A. place CEDMCS mode select go to section E1, CEA switch to OFF misalignment greater than 7 inches B. remove the Group Select switch go to section E1, CEA from the Reg Group 6 position misalignment greater than 7 inches C. remove the Group Select switch align CEAs to comply with TS from the Reg Group 6 position 3.1.3.6, Regulating and Group P CEA Insertion limits D. place CEDMCS mode select align CEAs to comply with TS switch to OFF 3.1.3.6, Regulating and Group P CEA Insertion limits Facility: Waterford 3 Page 19 of 75

2015 NRC Exam RO Written Exam RO 20 Given:

The plant is at 55% power performing a power ascension Group P is at 140 INCHES for ASI control At 0335 Group P Control Element Assembly (CEA) 35 slips to 125 Power is stabilized at 55%

The crew implements OP-901-102, CEA or CEDMCS Malfunction Attempts to move the CEA are unsuccessful, CEA 35 is declared INOPERABLE At 0420 o Malfunctioning Automatic Control Timing Module (ACTM) card is replaced and o CEA 35 was realigned to 140 and CEA 35 is declared OPERABLE The earliest that the crew can re-commence the power ascension is _____(1)_____ to

_______(2)______.

(1) (2)

A. 0535 minimize the effects of Xenon redistribution B. 0535 allow for clad relaxation C. 0620 minimize the effects of Xenon redistribution D. 0620 allow for clad relaxation Facility: Waterford 3 Page 20 of 75

2015 NRC Exam RO Written Exam RO 21 Given:

Reactor Power is 5.5 X 10-8 ENI Log Channel C has failed hi Startup Channel high voltage is automatically removed when power exceeds approximately _____(1)_____%. To restore High Voltage power to Startup Channel

_____(2)_____, the HV Control Switch in the Startup Channel drawer will be selected to Alternate.

(1) (2)

-4 A. 1.0 X 10 2 B. 1.0 X 10-4 1 C. 5.3 X 10-6 1 D. 5.3 X 10-6 2 Facility: Waterford 3 Page 21 of 75

2015 NRC Exam RO Written Exam RO 22 Given:

The plant is in MODE 6 with fuel shuffle in progress in both the Fuel Handling Building and Containment Containment Purge is in the Refueling Mode Containment equipment hatch and airlock doors are closed and no containment penetrations are impaired A fuel bundle is dropped from the Refueling Machine Fuel Hoist The crew has entered OP-901-405, Fuel Handling Incident Which of the following radiation monitors will automatically terminate the radioactive gas release to the environment?

A. Containment Atmosphere Hi Range Area Radiation Monitor, ARM-IRE-5400AS B. Containment Purge Area Radiation Monitor, ARM-IRE-5024 C. Refueling Machine Area Radiation Monitor, ARM-IRE-5013 D. Containment PIG Process Radiation Monitor, PRM-IRE-0100S Facility: Waterford 3 Page 22 of 75

2015 NRC Exam RO Written Exam RO 23 Given:

A cooldown is being performed to MODE 5 per OP-901-202, Steam Generator Tube Leakage or High Activity due to a leak on SG 2 All RCPs are secured CET Temp is 382 ºF THOT Loop1 is 375 ºF THOT Loop2 is 378 ºF TCOLD Loop 1 is 350 ºF TCOLD Loop 2 is 382 ºF The CRS has placed a lower limit of 30ºF on Subcool Margin Determine the minimum value of RCS pressure that supports the requested RCS Subcool Margin.

A. 196 psia B. 262 psia C. 270 psia D. 283 psia Facility: Waterford 3 Page 23 of 75

2015 NRC Exam RO Written Exam RO 24 During a LOCA or Steam Line Break in Containment, the _____(1)______ Radiation Monitor(s) will read erroneously _____(2)______ while Containment temperature is rising.

(1) (2)

A. Containment PIG low B. Containment PIG high C. Containment High Range low D. Containment High Range high Facility: Waterford 3 Page 24 of 75

2015 NRC Exam RO Written Exam RO 25 Given:

Power is 100%

A special test of the Control Room Envelope has inadvertently rendered continued operation from the Control Room impossible The CRS enters OP-901-502, Evacuation of Control Room & Subsequent Plant Shutdown Plant cooldown will be controlled using the ____(1)____. Per OP-901-502 Attachment 14, Reliable Instrumentation, reliable indication of Steam Generator pressure can be read on ____(2)____.

(1) (2)

A. atmospheric dump valves both trains B. steam bypass control system both trains C. atmospheric dump valves train B only D. steam bypass control system train B only Facility: Waterford 3 Page 25 of 75

2015 NRC Exam RO Written Exam RO 26 Which ONE of the following conditions will result in a Loss of Containment Integrity per Technical Specification while operating in MODE 1?

A. One of two normally open redundant containment isolation valves has failed in the CLOSE position with power removed.

B. A mechanic props OPEN the Personnel Airlock outer door to perform corrective maintenance on an inoperable inner door.

C. A blank flange was installed in place of a containment isolation valve which had failed its surveillance test.

D. A manual isolation valve is CLOSED to isolate a penetration where an electrician had disconnected the auto-close feature for a containment isolation valve.

Facility: Waterford 3 Page 26 of 75

2015 NRC Exam RO Written Exam RO 27 Given:

Plant is at 100% power The crew has entered OP-901-111, Reactor Coolant System Leak RCS Tavg is 575 degrees and steady Charging Pump A is running Pressurizer level is 55% and slowly lowering The Standby Charging Pumps selector switch is selected to the B-AB position To allow for a more accurate leak rate determination, the CRS will direct the ATC to

____(1)____.

The ATC will determine an RCS leak rate by subtracting the total of ____(2)____.

(1) (2)

A. place Charging Pump B control Charging flow and RCP CBO flow switch to the ON position from Letdown flow B. place the Letdown Flow controller Charging flow and RCP CBO flow to manual from Letdown flow C. place the Letdown Flow controller Letdown flow and RCP CBO flow to manual from Charging flow D. place Charging Pump B control Letdown flow and RCP CBO flow switch to the ON position from Charging flow Facility: Waterford 3 Page 27 of 75

2015 NRC Exam RO Written Exam RO 28 Given:

The reactor is operating at 100% power At 0100 RCP 1A Lower Seal fails and Controlled Bleedoff flow rises to 2.5 GPM OP-901-130, Reactor Coolant Pump Malfunction is implemented and the plant remains at 100% power At 0530 RCP 1A Middle Seal fails RCP 1A Controlled Bleedoff flow went out of range high and then went to 0 GPM RCP 1A Controlled Bleedoff flow went low due to closure of ________(1)_________.

The crew should ________(2)_________ and secure RCP 1A.

(1) (2)

A. a RCP Controlled Bleedoff perform a shutdown to MODE 3 per Containment Isolation Valve OP-010-005, Plant Shutdown B. a RCP Controlled Bleedoff manually trip the reactor and Containment Isolation Valve perform Standard Post Trip Actions C. the check valve on RCP 1A perform a shutdown to MODE 3 per Controlled Bleedoff line OP-010-005, Plant Shutdown D. the check valve on RCP 1A manually trip the reactor and Controlled Bleedoff line perform Standard Post Trip Actions Facility: Waterford 3 Page 28 of 75

2015 NRC Exam RO Written Exam RO 29 Given:

The reactor was at 100% power RCP 1A trips on overcurrent

__(1)__ RCP 1A Lift Oil Pump(s) started when RCP 1A __(2)__.

(1) (2)

A. One load breaker opened B. Both load breaker opened C. One speed lowered to 600 RPM D. Both speed lowered to 600 RPM Facility: Waterford 3 Page 29 of 75

2015 NRC Exam RO Written Exam RO 30 Given:

Power is 100%

A grid transient causes turbine load to lower by 10%

As a result of this transient, RCS temperature will ____(1)____ and the Letdown Backpressure control valve will ______(2)______.

(1) (2)

A. lower open B. lower close C. rise open D. rise close Facility: Waterford 3 Page 30 of 75

2015 NRC Exam RO Written Exam RO 31 Given:

The plant is in Mode 4 Shutdown Cooling Train A is in service RCS temperature is 204°F and steady Component Cooling Water temperature is dropping through the night as ambient temperature drops To prevent entry into Mode 5, the SDC Train A Temperature Control Valve (SI-415A) must be throttled ____(1)____. This will result in the SDC Train A Flow Control Valve (SI-129A) automatically throttling ______(2)______.

(1) (2)

A. open open B. open closed C. closed closed D. closed open Facility: Waterford 3 Page 31 of 75

2015 NRC Exam RO Written Exam RO 32 What is the power supply to SI-138 A, LPSI Header to RC Loop 2B Control Isolation?

A. Bus 213 A B. Bus 311 A C. Bus 314 A D. Bus 315 A Facility: Waterford 3 Page 32 of 75

2015 NRC Exam RO Written Exam RO 33 Given:

A Loss Of Cooling Accident is in progress Reactor Coolant System (RCS) pressure is 200 PSIA High Pressure Safety Injection Pump B trips shortly after starting All other equipment functions as designed The minimum required Safety Injection flow for High Pressure Safety Injection is

___(1)____ and ___(2)____ is required for Low Pressure Safety Injection.

(1) (2)

A. >185 GPM total flow to no flow the cold legs B. >185 GPM total flow to >185 GPM flow to the cold legs loop 2 cold legs C. >185 GPM to each cold no flow leg D. >185 GPM to each cold >185 GPM flow to leg loop 2 cold legs Facility: Waterford 3 Page 33 of 75

2015 NRC Exam RO Written Exam RO 34 A Steam Generator Tube Rupture has occurred that resulted in an automatic SIAS/CIAS.

Realignment of ___(1)____ could result in a Quench Tank Rupture Disc failure. Upon the rupture disc failure, the ATC will expect containment pressure to ___(1)____.

(1) (2)

A. RCP Control Bleedoff rise B. RCP Vapor Seal Leak Off be unaffected C. RCP Control Bleedoff be unaffected D. RCP Vapor Seal Leak Off rise Facility: Waterford 3 Page 34 of 75

2015 NRC Exam RO Written Exam RO 35 Given:

Power is 100%

CCW Pump A has tripped with CCW Pump AB OOS Which of the following actions is performed to protect CCW Pump B from runout conditions?

A. Split out the A and B CCW headers B. Close the NNS loop isolations C. Secure Train B Containment Fan Coolers D. Align Chiller B Cooling to the Wet Tower Facility: Waterford 3 Page 35 of 75

2015 NRC Exam RO Written Exam RO 36 Given:

Plant is at 100% power The ATC reports that the Pressurizer Spray Valve, RC-301A, has failed open The output of the Pressurizer Pressure controller (RC-IPIC-0100) will ___(1)____ and the Pressurizer back-up heaters are designed to automatically energize at an RCS pressure of ___(2)____ psia.

(1) (2)

A. lower 2225 B. lower 2200 C. rise 2200 D. rise 2225 Facility: Waterford 3 Page 36 of 75

2015 NRC Exam RO Written Exam RO 37 Given:

The plant is at 100% power A loss of SUPS MD occurs Reactor Trip Switchgear breakers _____(1)_____ open and a reactor trip

_______(2)______.

(1) (2)

A. 3, 4, 7, and 8 occurs B. 3, 4, 7, and 8 does not occur C. 1, 2, 5, and 6 occurs D. 1, 2, 5, and 6 does not occur Facility: Waterford 3 Page 37 of 75

2015 NRC Exam RO Written Exam RO 38 Given:

Plant is at 90% power Reactor Cutback is in service CRS entered OP-901-201, Steam Generator (SG) level control malfunction due to a problem with SG level control. The following alarms are present in the Control Room:

SG1 STEAM/FW FLOW SIGNAL DEV SG2 STEAM/FW FLOW SIGNAL DEV SG1 LEVEL HI/LO SG2 LEVEL HI/LO FWPT A FLOW LO SG1 LEVEL LO PRETRIP A/C SG1 LEVEL LO PRETRIP B/D SG1 level is 26% NR on all indications and stable. SG2 level is 30% NR on all indications and stable. The operator reports FWPT A speed is 3900 rpm and FWPT B speed is 5200 rpm.

The crew will prioritize the ____(1)____ alarm(s) and take action to _____(2)_____.

(1) (2)

A. SG1 LEVEL LO PRETRIP manually trip FWPT A B. FWPT A FLOW LO manually trip FWPT A C. SG1 LEVEL LO PRETRIP manually trip the reactor D. FWPT A FLOW LO manually trip the reactor Facility: Waterford 3 Page 38 of 75

2015 NRC Exam RO Written Exam RO 39 Manual actuation of a Containment Spray Actuation Signal (CSAS) from the Control Room requires _____(1)_____ two of the four ESFAS channels and will start

_____(2)_____ train(s) of Containment Spray.

(1) (2)

A. a specific one B. a specific both C. any one D. any both Facility: Waterford 3 Page 39 of 75

2015 NRC Exam RO Written Exam RO 40 Given:

Plant has experienced an Excess Steam Demand event RCS Pressure is 1750 PSIA Containment Pressure is 16.9 PSIA Steam Generator 1 pressure is 650 PSIA Steam Generator 2 pressure is 600 PSIA Steam Generator #1 level is 5% NR and dropping Steam Generator #2 level is 4% NR and dropping What is the current status of EFAS 1 and EFAS 2?

A. Only EFAS 1 is initiated B. Only EFAS 2 is initiated C. Both EFAS 1 and EFAS 2 are initiated D. Neither EFAS 1 nor EFAS 2 are initiated Facility: Waterford 3 Page 40 of 75

2015 NRC Exam RO Written Exam RO 41 Given:

The plant is operating at 100% power A LOCA occurs Containment pressure is 17.3 PSIA and rising Pressurizer pressure is 1700 PSIA and lowering The containment fan coolers will be operating in _____(1)_____ speed. Containment Fan Cooler discharge will be to the containment cooling ______(2)_____.

(1) (2)

A. slow system ring header B. slow safety discharge dampers C. fast safety discharge dampers D. fast system ring header Facility: Waterford 3 Page 41 of 75

2015 NRC Exam RO Written Exam RO 42 Following a valid CSAS signal, the minimum operator actions required to close CS-125A, Containment Spray Header A Isolation valve, is to take the _________ to CLOSED.

A. CP-8 control switch for CS 125A B. CP-8 control switch for CS 125A to OPEN, then back C. Keyswitch, CS-125A Override, to OVERRIDE, then take the CP-8 control switch for CS 125A D. Keyswitch, CS-125A Override, to OVERRIDE, then take the CP-8 control switch for CS 125A to OPEN, then back Facility: Waterford 3 Page 42 of 75

2015 NRC Exam RO Written Exam RO 43 Given:

Reactor Coolant System Tcold is 500 F and lowering Reactor Coolant Pumps 1B and 2B are running 15 minutes ago the Reactor Coolant System Tc was 515 F when a controlled cool down was established The cool down is being controlled using MS-319A, Main Steam Bypass 1A, at 15% open IF MS-319A failed open, the maximum allowed cool down rate of ___(1)____ which protects the ___(2)__________ under all conditions, would be exceeded.

(1) (2)

A. 100 F/Hr most limiting component in Reactor Coolant System B. 60 F/Hr SG tube sheet from cyclic stress, which is the most limiting component C. 100 F/Hr SG tube sheet from cyclic stress, which is the most limiting component D. 60 F/Hr most limiting component in Reactor Coolant System Facility: Waterford 3 Page 43 of 75

2015 NRC Exam RO Written Exam RO 44 Given:

The plant is at 42% power Condensate Pumps A, B and C are in operation Both Main Feedwater Pumps are operating Condensate Pumps A and B trip.

The Main Feedwater Pump Turbine Condensate Pump Interlock will trip Main Feedwater Pump _____(1)_____. This trip is active if the Main Feedwater Pump Turbine High Pressure (HP) governor valves are ______(2)_____.

(1) (2)

A. A not fully closed B. A fully closed C. B fully closed D. B not fully closed Facility: Waterford 3 Page 44 of 75

2015 NRC Exam RO Written Exam RO 45 Given:

The plant has a experienced a Loss of Main Feedwater Event An EFAS-1 has occurred Steam Generator #1 level is 40% WR and dropping Steam Generator #1 EFW flow transmitter has failed high The Steam Generator #1 Primary Flow Control Valve is ______(1)______. The Steam Generator #1 Backup Flow Control Valve is _______(2)______.

(1) (2)

A. closed open to 400 gpm flow value B. closed closed C. open to a preset valve position closed D. open to a preset valve position open to 400 gpm flow value Facility: Waterford 3 Page 45 of 75

2015 NRC Exam RO Written Exam RO 46 Given:

Power is 100%

CEDMCS Motor Generator Tie Breaker (TCB 9) is removed for maintenance An equipment problem caused an overcurrent condition on the 3A-to-2A bus tie (BT).

Overcurrent on the bus tie will trip the ____(1)____ . The crew will enter

______(2)______ to mitigate the event.

(1) (2)

A. 3A-to-2A BT breaker only OP-901-310, Loss of Train A Safety Bus and OP-902-000, Standard Post Trip Actions concurrently B. 3A-to-2A BT breaker only OP-901-310, Loss of Train A Safety Bus only C. 3A-to-2A and the 2A-to-3A BT OP-901-310, Loss of Train A breakers Safety Bus and OP-902-000, Standard Post Trip Actions concurrently D. 3A-to-2A and the 2A-to-3A BT OP-901-310, Loss of Train A breakers Safety Bus only Facility: Waterford 3 Page 46 of 75

2015 NRC Exam RO Written Exam RO 47 Given:

Power is 100%

W3 System Engineer and Transmission & Distribution workers are investigating an alarm in the 230KV yard The Control receives annunciator EDG B FUEL OIL XFER PUMP POWER LOST due to Emergency Diesel Generator B fuel oil transfer pump breaker tripping on overcurrent.

Both 230KV West Bus Feeder breakers trip. Both 230KV East Bus Feeder breakers remain closed.

Select the correct statement:

A. Emergency Diesel Generator B is inoperable and both Offsite Trains remain operable.

B. Emergency Diesel Generator B is inoperable and both Offsite Trains are inoperable.

C. Emergency Diesel Generator B remains operable and both Offsite Trains are inoperable.

D. Emergency Diesel Generator B remains operable and both Offsite Trains remain operable.

Facility: Waterford 3 Page 47 of 75

2015 NRC Exam RO Written Exam RO 48 Given:

Emergency Diesel Generator 'A' is running loaded A loss of the 125VDC A Bus occurs Which of the following describes the effect of the loss of DC control power on the EDG and its auxiliaries?

A. The EDG must be secured locally by pulling the overspeed trip.

B. The EDG CCW flow control valve, CC-413A, will fail full open.

C. Fuel oil transfer pump starts and must be secured to prevent overfilling the feed tank.

D. Jacket cooling water valves fail open and the jacket water heater loses power.

Facility: Waterford 3 Page 48 of 75

2015 NRC Exam RO Written Exam RO 49 Given:

EDG B is being synchronized to the grid in accordance with OP-009-002, Emergency Diesel Generator, for a retest following maintenance The synchroscope is slowly rotating in the counter-clockwise (Slow) direction.

EDG voltage is approximately 10 volts lower than Bus voltage IF the EDG output breaker is closed under these conditions, the potential effect of an (a)

____(1)____ trip exists.

Taking action to raise EDG ______(2)______ PRIOR to closing the EDG output breaker will prevent the effect.

(1) (2)

A. overcurrent frequency B. overcurrent voltage C. reverse power frequency D. reverse power voltage Facility: Waterford 3 Page 49 of 75

2015 NRC Exam RO Written Exam RO 50 Given:

The crew is performing OP-903-068, Emergency Diesel Generator Operability and Subgroup Relay Operability Verification, for Emergency Diesel Generator B The crew has started Emergency Diesel Generator B in accordance with OP-009-002, Emergency Diesel Generator OP-009-002 Attachment 11.8, Emergency Diesel Generator Start Evaluation, states that a successful start of Emergency Diesel Generator is defined as required voltage and frequency is ____(1)____ within ______(2)______ of taking the EDG B control switch to start.

(1) (2)

A. attained 5 seconds B. stabilized 5 seconds C. stabilized 10 seconds D. attained 10 seconds Facility: Waterford 3 Page 50 of 75

2015 NRC Exam RO Written Exam RO 51 Given:

The plant is at 40% power Blowdown discharge to Circ Water is in progress BD-303, Blowdown to Circ Water and Metal Waste Pond Isolation Valve, closes Which ONE of the following can cause the valve to close?

A. High radiation on the Blowdown Radiation Monitor B. High Radiation on the Circ Water Radiation Monitor C. Trip of the running Blowdown Pump D. Hi pH alarm on Blowdown Proportional Sampler Facility: Waterford 3 Page 51 of 75

2015 NRC Exam RO Written Exam RO 52 Given:

The crew is preparing to discharge Waste Condensate Tank A to Circ Water per OP-007-004, Liquid Waste Management System The crew can perform a source check for LWM Radiation Monitor, PRM-IRE-0647 from

____(1)____. A successful source check will result in a _____(2)_____ for the channel under test.

(1) (2)

A. RM-11 at CP-6 only green light B. RM-11 at CP-6 or locally at the green light RM-80 C. RM-11 at CP-6 or locally at the medium blue light RM-80 D. RM-11 at CP-6 only medium blue light Facility: Waterford 3 Page 52 of 75

2015 NRC Exam RO Written Exam RO 53 Which of the following conditions on the associated loop will send an automatic start signal to ACCW Pump A?

A. Low ACCW system pressure B. High ACCW system temperature C. Dry Cooling Tower A bypass opens D. Low Component Cooling Water flow Facility: Waterford 3 Page 53 of 75

2015 NRC Exam RO Written Exam RO 54 Given:

Instrument Air Header pressure has lowered to 100 psig due to a leak SA-125, Station Air Backup Supply for IA Press Cntl valve, is at its normal setpoint SA-125 is _____(1)_____ . The remote instrument air pressure gauge (IA-IPI-9700) is located on ______(2)_____.

(1) (2)

A. open CP-18 B. closed CP-1 C. open CP-1 D. closed CP-18 Facility: Waterford 3 Page 54 of 75

2015 NRC Exam RO Written Exam RO 55 A plant trip and SIAS have occurred due to low Pressurizer pressure.

What is the designed range of Containment Annulus to ambient differential pressure in inches of water?

A. -3.0 to -8.0 B. +2.0 to -8.0 C. -3.0 to -10.0 D. +2.0 to -10.0 Facility: Waterford 3 Page 55 of 75

2015 NRC Exam RO Written Exam RO 56 Which ONE of the following alarms would be the FIRST indication of a leaking Pressurizer Safety Valve?

A. Pressurizer Level High/Low B. Containment Water Leakage High C. Quench Tank Temperature High D. Reactor Drain Tank Level High/Low Facility: Waterford 3 Page 56 of 75

2015 NRC Exam RO Written Exam RO 57 Given:

Plant is operating at 100% power TAVG LOOP SELECTOR switches in RRS Cabinets 1 and 2 are in the BOTH position RCS temperature Loop 1 Hot Leg (RC-ITI-0111-X) indicates failed low Letdown flow will initially ____(1)____. Pressurizer heaters will ______(2)_____ .

(1) (2)

A. lower de-energize B. lower energize C. rise energize D. rise de-energize Facility: Waterford 3 Page 57 of 75

2015 NRC Exam RO Written Exam RO 58 Given:

A plant Startup to Mode 1 is in progress in accordance with OP-010-003, Plant Startup Reactor power is 10-4 % power and rising The LOGARITHMIC PWR HI BY-PASS annunciator is received The crew will _____(1)_____ on all four PPS Channels prior to exceeding ____(2)___ %

power or a reactor trip will occur.

(1) (2)

A. verify the High Log power trip is 1.0 automatically bypassed B. manually bypass the High Log 1.0 power trip C. manually bypass the High Log 0.257 power trip D. verify the High Log power trip is 0.257 automatically bypassed Facility: Waterford 3 Page 58 of 75

2015 NRC Exam RO Written Exam RO 59 Given:

A LOCA has occurred The crew is performing OP-902-002, Loss of Coolant Accident Recovery Which ONE of the following describes the sequence of actions required to place a Hydrogen Analyzer in service, and the hydrogen concentration indicated when the containment atmosphere reaches the minimum flammable limit?

A. Open the H2 Analyzer containment isolation valve, then turn the power switch ON; 4%.

B. Place the power switch ON, then open the H2 Analyzer containment isolation valve; 3%.

C. Open the H2 Analyzer containment isolation valve, then turn the power switch ON; 3%.

D. Place the power switch ON, then open the H2 Analyzer containment isolation valve; 4%.

Facility: Waterford 3 Page 59 of 75

2015 NRC Exam RO Written Exam RO 60 Given:

Plant is at 55% power Steam Generator Feed Pump (SGFP) B has been started in accordance with OP-003-033, Main Feedwater Local speed balance meter is balanced and local controls are in Auto Steam Generator Feed Pump B speed is 3900 rpm and the red light on the Speed Governor Control Switch for Main Feed Pump B is illuminated The CRS has directed the BOP to align SGFP B for automatic operation The BOP will manually adjust SGFP B speed using the ____(1)____ .

Before placing SGFP B speed controller in auto on CP-1, SGFP B speed controller output will be adjusted to match _____(2)_____ to assure minimal feedwater flow perturbation.

(1) (2)

A. speed controller M/A station SGFP A speed controller output B. speed governor control switch SGFP A speed controller output C. speed controller M/A station SGFP B speed controller input D. speed governor control switch SGFP B speed controller input Facility: Waterford 3 Page 60 of 75

2015 NRC Exam RO Written Exam RO 61 RCS Reference Temperature (Tref) signal is generated in the ____(1)____ system as a function of the _____(2)_____ input.

(1) (2)

A. Reactor Regulating Turbine First Stage pressure B. Steam Bypass Control Turbine First Stage pressure C. Reactor Regulating Main Steam Crossover Header pressure D. Steam Bypass Control Main Steam Crossover Header pressure Facility: Waterford 3 Page 61 of 75

2015 NRC Exam RO Written Exam RO 62 OP-003-001, Condenser Air Evacuation System, requires Condenser Vacuum Pumps (1) be operating to provide a suction path for the (2)

(1) (2)

A. A or B Condenser Air Evacuation WRGM (PRM-IRE-0002)

B. A or B Condenser Air Evacuation PIG Rad Monitor (PRM-IRE-0004)

C. B or C Condenser Air Evacuation WRGM (PRM-IRE-0002)

D. B or C Condenser Air Evacuation PIG Rad Monitor (PRM-IRE-0004)

Facility: Waterford 3 Page 62 of 75

2015 NRC Exam RO Written Exam RO 63 In Modes 1 and 2, the Transient Insertion Limits of TS 3.1.3.6 (Regulating and Group P CEA Insertion Limits) ensures that____(1)____. If these limits cannot be maintained, the crew is required to ______(2)_____ .

(1) (2)

A. radial xenon redistribution emergency borate effects are maintained within limits B. radial xenon redistribution restore the CEA to within limits effects are maintained within within two hours limits C. minimum shutdown margin restore the CEA to within limits requirements are maintained within two hours D. minimum shutdown margin emergency borate requirements are maintained Facility: Waterford 3 Page 63 of 75

2015 NRC Exam RO Written Exam RO 64 Which ONE of the following radiation monitors will cause an AUTO closure of Waste Gas Discharge FCV (GWM-309) valve during a Gaseous Waste Discharge evolution?

A. Gaseous Waste Management Radiation Monitor B. Plant Stack PIG Monitor A or B C. Plant Stack WRGM Monitor D. RAB HVAC PIG Monitor B Facility: Waterford 3 Page 64 of 75

2015 NRC Exam RO Written Exam RO 65 Turbine Closed Cooling Water (TCCW) Pump B is powered from which bus?

A. SWGR 21B B. SWGR 3B C. SWGR 1B D. SWGR 2B Facility: Waterford 3 Page 65 of 75

2015 NRC Exam RO Written Exam RO 66 Per EN-OP-115, Conduct of Operations, if an operating parameter exceeds any of the reactor protection set points and an automatic shutdown does not occur, the licensed operator is required to:

A. take action to restore the parameter within limit; if not successful, manually trip the Reactor.

B. get Control Room Supervisor permission and then manually trip the Reactor.

C. report tripping the Reactor while taking action to manually trip the Reactor.

D. get a peer check on the parameter and then manually trip the Reactor.

Facility: Waterford 3 Page 66 of 75

2015 NRC Exam RO Written Exam RO 67 Per TS 3.9.10.1 Water Level-Reactor Vessel and RF-005-001 Fuel Movement, at least 23 feet of water shall be maintained over the top of the ____(1)_____ during movements of fuel within the reactor pressure vessel. This is equivalent to a ____(2)____ foot level in the Refuel Cavity.

(1) (2)

A. reactor vessel flange 32 B. reactor vessel flange 43 C. irradiated fuel assemblies seated in 43 the reactor vessel D. irradiated fuel assemblies seated in 32 the reactor vessel Facility: Waterford 3 Page 67 of 75

2015 NRC Exam RO Written Exam RO 68 Given:

A reactor trip has occurred The crew is performing OP-902-000, Standard Post Trip Actions For the RCS Inventory Control Safety Function, the ATC will verify that RCS subcooling is greater than or equal to ____(1)____ °F. RCS subcooling greater than or equal to the minimum RCS subcooling requirements for RCS inventory control will ______(2)_____ .

(1) (2)

A. 28 validate pressurizer level indication as being representative of total RCS inventory B. 30 validate pressurizer level indication as being representative of total RCS inventory C. 28 ensure that Reactor Coolant Pumps are within the acceptable range of the RCP operating curves D. 30 ensure that Reactor Coolant Pumps are within the acceptable range of the RCP operating curves Facility: Waterford 3 Page 68 of 75

2015 NRC Exam RO Written Exam RO 69 Given:

Plant is at 100% Power At 0100, the BOP operator bypasses the Channel C High LPD and Low DNBR trip bistables for a scheduled two hour I&C surveillance on Channel C Core Protection Calculator The I&C technician informs the CRS that the CPC has failed the surveillance and will require a card replacement Operability will be tracked by ___(1)___ when the work begins. The Shift Manager will declare equipment operable following retest using ___(2)___.

(1) (2)

A. the work package the CR operability tab in PCRS B. OP-100-010, Att. 7.1, OP-100-010, Att. 7.2, EOS TS/TRM Entry Guidelines Checklist C. the work package OP-100-010, Att. 7.2, EOS Checklist D. OP-100-010, Att. 7.1, the CR operability tab in PCRS TS/TRM Entry Guidelines Facility: Waterford 3 Page 69 of 75

2015 NRC Exam RO Written Exam RO 70 Per TS 3.6.3, a locked closed containment isolation valve can be opened on an intermittent basis under administrative controls.

These administrative controls will include assigning an operator in constant communication with the control room ____(1)____. The list of containment isolation valves can be found in _____(2)____ .

(1) (2)

A. to close the valve within four hours TS 3.6.3 of an accident situation B. to be stationed at the valve controls TS 3.6.3 C. to close the valve within four hours TRM 3.6.3 of an accident situation D. to be stationed at the valve controls TRM 3.6.3 Facility: Waterford 3 Page 70 of 75

2015 NRC Exam RO Written Exam RO 71 Given:

A Steam Generator Tube Leak is in progress in both Steam Generators The crew is performing actions in accordance with OP-901-202, Steam Generator Tube Leakage or High Activity The condenser is not available The crew will commence a normal plant cooldown to obtain a Hot leg temperature of less than or equal to 520°F using _____(1)_____. The discharge through the Atmospheric Dump Valve(s) is a(an) ______(2)_____ release.

(1) (2)

A. the atmospheric dump valve on the monitored S/G with the lowest indicated activity B. the atmospheric dump valve on the unmonitored S/G with the lowest indicated activity C. both atmospheric dump valves monitored D. both atmospheric dump valves unmonitored Facility: Waterford 3 Page 71 of 75

2015 NRC Exam RO Written Exam RO 72 As an Emergency Team member following a loss of reactor cavity level that has resulted in uncovering irradiated fuel, you will enter the Containment in order to rescue an injured person.

The maximum exposure limit (TEDE) allowed for these conditions is _____(1)_____.

Authorization ______(2)_____ require that dose rates in the area be known.

(1) (2)

A. 10 rem does B. 10 rem does not C. 25 rem does D. 25 rem does not Facility: Waterford 3 Page 72 of 75

2015 NRC Exam RO Written Exam RO 73 In accordance with OI-038-000, Emergency Operating Procedures Operations Expectations/Guidance, and upon entry to the Emergency Operating Procedures, the operating crew will monitor the safety function status checklist ____(1)____. The STA is required to monitor the safety function status checklist every ______(2)_____ minutes.

(1) (2)

A. continuously 30 B. every 30 minutes 15 C. every 30 minutes 30 D. continuously 15 Facility: Waterford 3 Page 73 of 75

2015 NRC Exam RO Written Exam RO 74 The lowest emergency classification that the Technical Support Center (TSC) and the Emergency Operations Facility (EOF) shall be activated is an ____(1)____. Continuous communications with the NRC will be transferred from the Control Room to the

____(2)_____.

(1) (2)

A. unusual event EOF B. unusual event TSC C. alert TSC D. alert EOF Facility: Waterford 3 Page 74 of 75

2015 NRC Exam RO Written Exam RO 75 Given:

A reactor trip has occurred The crew is performing OP-902-000, Standard Post Trip Actions The minimum requirements to verify the main turbine is tripped is to check ____(1)____

are closed. If the main turbine did not trip automatically, the first contingency action to secure steam admission to the main turbine is to ______(2)_____.

(1) (2)

A. governor and throttle valves depress the turbine trip and think pushbuttons B. governor valves close both MSIVs C. governor and throttle valves close both MSIVs D. governor valves depress the turbine trip and think pushbuttons Facility: Waterford 3 Page 75 of 75

2015 NRC Exam SRO Written Exam SRO 1 Given:

The plant is at 100 % power Atmospheric Dump Valve #1 (MS-116A) controller has been placed in manual in an attempt to more fully seat the valve The crew is evaluating Tech Spec 3.7.1.7, Atmospheric Dump Valve, requirements The automatic actuation channel for Atmospheric Dump Valve # 1 is ___(1)____

For the given power level, TS 3.7.1.7 basis states that the automatic operation of one Atmospheric Dump Valve along with one train of High Pressure Safety Injection is required for mitigation of the _____(2)_____ event.

(1) (2)

A. inoperable steam generator tube rupture B. operable steam generator tube rupture C. inoperable small Break LOCA D. operable small Break LOCA Facility: Waterford 3 Page 1 of 25

2015 NRC Exam SRO Written Exam SRO 2 Given:

Large Break LOCA has occurred The crew is performing the required actions of OP-902-002, LOCA Recovery Procedure The CRS will determine if simultaneous Hot and Cold Injection is required based on

___(1)____. If conditions are met, hot and cold leg injection must be aligned within the maximum allowable time of ____(2)_____ hours from the start of the event to ensure boric acid precipitation in the core does not occur.

(1) (2)

A. HPSI and LPSI flows within two acceptable region of the SI flow curves B. Pressurizer level, Reactor vessel two level and RCS subcooling C. HPSI and LPSI flows within the three acceptable region of the SI flow curves D. Pressurizer level, Reactor vessel three level and RCS subcooling Facility: Waterford 3 Page 2 of 25

2015 NRC Exam SRO Written Exam SRO 3 Given:

Component Cooling Water (CCW) Pump A has tripped on overcurrent.

The crew will declare CCW Train A inoperable along with the affected systems listed in

___(1)____. The crew is required to demonstrate the operability of the Train B offsite AC circuit by performing surveillance procedure____(2)____ within one hour and at least once per eight hours thereafter.

(1) (2)

A. OP-100-014, Technical OP-903-001, Attachment 11.14, Specification and Technical Electrical Distribution Operability Requirements Compliance Check B. OP-100-010, Equipment Out of OP-903-001, Attachment 11.14, Service Electrical Distribution Operability Check C. OP-100-014, Technical OP-903-066, Electrical Breaker Specification and Technical Alignment Check Requirements Compliance D. OP-100-010, Equipment Out of OP-903-066, Electrical Breaker Service Alignment Check Facility: Waterford 3 Page 3 of 25

2015 NRC Exam SRO Written Exam SRO 4 Given:

A plant shutdown in accordance with OP-010-005, Plant Shutdown, is in progress due to primary to secondary leakage The control room has entered OP-901-202, Steam Generator Tube Leakage (SGTL) or High Activity Charging pump AB is tagged out Primary to secondary leakage increases to 95 gpm.

The crew will ___(1)____. After the initial plant cooldown to 520 °F, the CRS will give the order to de-pressurize the RCS to _____(2)______.

Note: OP-901-212: Rapid Plant Power Reduction (1) (2)

A. transition to OP-901-212, 930 psia to minimize leakage concurrently with OP-901-202, SGTL or High Activity B. trip the reactor and diagnose into 930 psia to minimize leakage OP-902-007, Steam Generator Tube Rupture Recovery C. transition to OP-901-212, 1150 psia to maintain RCP NPSH concurrently with OP-901-202, SGTL or High Activity D. trip the reactor and diagnose into 1150 psia to maintain RCP NPSH OP-902-007, Steam Generator Tube Rupture Recovery Facility: Waterford 3 Page 4 of 25

2015 NRC Exam SRO Written Exam SRO 5 The plant is operating at 100% power when the SUPS power supply to PDP-90A is lost.

The crew will enter section ___(1)____ of OP-901-312, Loss of Vital Instrument Bus. The CRS will direct the crew to ______(2)_____.

(1) (2)

A. E8 Loss of monitor primary plant parameters on Safety Channels B, SUPS A C, and D B. E1 Loss of verify Component Cooling Water supplying the AB loop SUPS MA from the B train of CCW C. E8 Loss of verify Component Cooling Water supplying the AB loop SUPS A from the B train of CCW D. E1 Loss of monitor primary plant parameters on Safety Channels B, SUPS MA C, and D Facility: Waterford 3 Page 5 of 25

2015 NRC Exam SRO Written Exam SRO 6 Given:

The plant experienced an uncomplicated reactor trip. The crew transitioned to OP-010-005, Plant Shutdown, and is holding mode 3 conditions.

An unisolable Instrument Air leak occurred when the plant tripped.

Instrument Air pressure has been lost for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> due to the leak and leak repair should be complete in 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

Reactor Coolant Pumps 1B and 2B are operating.

The following annunciators are illuminated on CP-2 o RCP 1A CCW FLOW LO o RCP 2A CCW FLOW LO o RCP 1B CCW FLOW LO o RCP 2B CCW FLOW LO The following annunciators are illuminated on CP-18:

o RCP 1A CCW FLOW LOST o RCP 2A CCW FLOW LOST The CRS will direct the crew to ___(1)____ in accordance with the guidance in

_________(2)_________.

(1) (2)

A. trip Reactor Coolant Pumps 1B and OP-901-511, Loss of Instrument 2B Air B. gag open CC-200A and CC-727, OP-901-511, Loss of Instrument CCW Suct & Discharge Header Tie Air Valves A to AB C. gag open CC-200A and CC-727, OP-901-510, Component Cooling CCW Suct & Discharge Header Tie Water Malfunction Valves A to AB D. trip Reactor Coolant Pumps 1B and OP-901-510, Component Cooling 2B Water Malfunction Facility: Waterford 3 Page 6 of 25

2015 NRC Exam SRO Written Exam SRO 7 Given:

Power is 100%

All CEAs fully withdrawn Five minutes later, the ATC reports the following:

CEA 38 indicates 135 inches on the CP-2 CEAC CRT CEA 38 indicates 150 inches on the PMC Both the Upper and Lower Electrical Limit lights for CEA 38 are extinguished All Rod Bottom lights are extinguished Tcold is 541 ºF and slowly dropping To verify CEA position, the CRS will request indication on the ____(1)____ . The CRS will enter OP-901-102, CEA or CEDMCS Malfunction, sub-section _____(2)_____.

(1) (2)

A. CPC that CEA 38 is targeted to E1, CEA Misalignment Greater than 7 inches B. CPC that CEA 38 is targeted to E5, CEA Position Indication Malfunction C. CP-2 digital meter for CEA 38 E1, CEA Misalignment Greater than 7 inches D. CP-2 digital meter for CEA 38 E5, CEA Position Indication Malfunction Facility: Waterford 3 Page 7 of 25

2015 NRC Exam SRO Written Exam SRO 8 Given:

Plant is performing a cooldown for a refueling outage RCS temperature is 195 ºF RCS pressure is 350 psia EDG A is tagged out Offsite power train B is declared inoperable because of a voltage problem.

The CRS will verify ________ is aligned as the operable boration flow path per OP-903-002, Boration Flow Path Valve Lineup Verification.

A. the RWSP and HPSI pump A B. the RWSP and HPSI pump B C. BAM pump A and Charging pump A D. BAM pump B and Charging pump B Facility: Waterford 3 Page 8 of 25

2015 NRC Exam SRO Written Exam SRO 9 Given:

The plant is at 90% and performing a power reduction from 100% due to lowering condenser vacuum Per OP-901-220, Loss of Condenser Vacuum, the reactor will be tripped if condenser vacuum is approaching ___(1)____ Inches Hg. The crew will _________(2)_________.

(1) (2)

A. 20 perform OP-902-000, Standard Post Trip Actions, concurrently with OP-901-220 B. 14 perform OP-902-000, Standard Post Trip Actions, concurrently with OP-901-220 C. 14 go to OP-902-000, Standard Post Trip Actions, exit OP-901-220 D. 20 go to OP-902-000, Standard Post Trip Actions, exit OP-901-220 Facility: Waterford 3 Page 9 of 25

2015 NRC Exam SRO Written Exam SRO 10 Given:

Plant was operating at 100% power with EDG A danger tagged An Excess Steam Demand occurred SIAS, CIAS, and MSIS have been initiated Pressurizer level is 0%

After entering OP-902-004, Excess Steam Demand Recovery, the following conditions change:

Representative CET temperature and RCS pressure start to rise.

A Loss of Off Site Power occurs All components respond as designed to the event.

Based on these conditions, the CRS will ____(1)____ and ____(2)____

(1) (2)

A. remain in OP-902-004 direct the ATC to stabilize RCS pressure above HPSI Pump shutoff head.

B. remain in OP-902-004 direct the ATC to stabilize RCS pressure below HPSI Pump shutoff head.

C. exit OP-902-004 and enter direct the ATC to stabilize RCS pressure OP-902-008, Functional above HPSI Pump shutoff head.

Recovery D. exit OP-902-004 and enter direct the ATC to stabilize RCS pressure OP-902-008, Functional below HPSI Pump shutoff head.

Recovery Facility: Waterford 3 Page 10 of 25

2015 NRC Exam SRO Written Exam SRO 11 As stated in TS surveillance requirement 4.1.2.8, each borated water source shall be demonstrated operable by verifying the Boric Acid Makeup Tank solution temperature is greater than or equal to 60°F when reactor auxiliary building air temperature is less than

______(1)_______ °F.

The basis for this minimum temperature is to ensure that ______(2)______.

(1) (2)

A. 60 assumptions used in the MSLB return to power event remain valid B. 60 boron will not precipitate out of solution C. 55 boron will not precipitate out of solution D. 55 assumptions used in the MSLB return to power event remain valid Facility: Waterford 3 Page 11 of 25

2015 NRC Exam SRO Written Exam SRO 12 Given:

RCS temperature is 180°F and steady RCS pressure is 320 PSIA and steady SDC Train B is in service SDC Train A is secured The following annunciators are received:

SIAS Train A Logic Initiated (Cabinet K, G-19)

SIAS Train B Logic Initiated (Cabinet K, G-20)

LOOP 1 SDC RELIEF VLV ACTIVE (Cabinet M, A-7)

The addition of borated water ____(1)____ the capacity of SI-406B, RC Loop 1 SDC Suction LTOP relief to CNTMT Sump. The CRS will secure High Pressure Safety Injection Pumps in accordance with the guidance in ____(2)____.

(1) (2)

A. is within OP-901-131, Shutdown Cooling Malfunction B. exceeds OP-901-131, Shutdown Cooling Malfunction C. exceeds OP-901-504, Inadvertent ESFAS Actuation D. is within OP-901-504, Inadvertent ESFAS Actuation Facility: Waterford 3 Page 12 of 25

2015 NRC Exam SRO Written Exam SRO 13 A turbine control system malfunction has caused the turbine to runback from 100%

power. The following indications are present two minutes after the turbine stops running back:

REACTOR COOLANT Tave-Tref HI alarm in SELECTED COLD LEG 1 TEMPERATURE HI alarm in PRESSURIZER PRESSURE HI/LO alarm in Tcold is 547°F PZR Pressure is 2277 psia All PZR Heaters have de-energized automatically Pressurizer pressure controller output is 0%

Pressurizer spray valve controller output is 0%

The CRS will address pressurizer pressure control by entering OP-901-120, Pressurizer Pressure Control Malfunction, subsection ____(1)____ and enter the Tech Spec action(s) for _____(2)_____.

(1) (2)

A. E2, Pressurizer Pressure pressurizer pressure (TS 3.2.8)

Controller Malfunction only B. E3, Pressurizer Spray pressurizer pressure (TS 3.2.8)

Valve Malfunction only C. E2, Pressurizer Pressure pressurizer pressure (TS 3.2.8)

Controller Malfunction and reactor coolant cold leg temperature (TS 3.2.6)

D. E3, Pressurizer Spray pressurizer pressure (TS 3.2.8)

Valve Malfunction and reactor coolant cold leg temperature (TS 3.2.6)

Facility: Waterford 3 Page 13 of 25

2015 NRC Exam SRO Written Exam SRO 14 Given:

An Excess Steam Demand occurred SIAS, CIAS, MSIS and CSAS have been initiated After entering OP-902-004, Excess Steam Demand Recovery, the BOP reports that CFC A has tripped on overcurrent The CRS will determine that the ____(1)____ safety function is not met. The crew will

_____(2)_____.

(1) (2)

A. containment temperature and go to OP-902-008, Functional Recovery pressure control procedure B. containment isolation go to OP-902-008, Functional Recovery procedure C. containment isolation remain in OP-902-004, Excess Steam Demand Recovery procedure D. containment temperature and remain in OP-902-004, Excess Steam pressure control Demand Recovery procedure Facility: Waterford 3 Page 14 of 25

2015 NRC Exam SRO Written Exam SRO 15 Given:

Plant is at 100% power Turbine Cooling Water (TCW) Pump B is in service Turbine Cooling Water (TCW) Pump A is tagged for repair Turbine Cooling Water Pump B trips and the crew enters OP-901-512, Loss of Turbine Cooling Water Pumps.

The most limiting component for this event is the ____(1)____. The crew will perform OP-902-000, Standard Post Trip Actions, and then diagnose to _____(2)_____

Recovery Procedure.

(1) (2)

A. main turbine bearings OP-902-001, Reactor Trip B. main generator OP-902-006, Loss of Main Feedwater C. main generator OP-902-001, Reactor Trip D. main turbine bearings OP-902-006, Loss of Main Feedwater Facility: Waterford 3 Page 15 of 25

2015 NRC Exam SRO Written Exam SRO 16 Given:

The plant is at 100% power.

Letdown flow is 50 gpm and rising.

PZR level indicator RC-ILI-110X indicates 55% and lowering.

PZR level indicator RC-ILI-110Y indicates 54% and lowering.

The ATC reports that the pressurizer level setpoint on the Pressurizer Level Controller (RC-ILIC-0110) is 55.6%.

The output of the Pressurizer Level Controller (RC-ILIC-0110) is 90%.

The CRS will enter ____(1)____ and direct the ATC to take manual control of the ____(2)____

to restore Pressurizer level.

(1) (2)

A. OP-901-110, Pressurizer Level Pressurizer Level Controller Control Malfunction (RC-ILIC-0110)

B. OP-901-112, Charging and Pressurizer Level Controller Letdown Malfunction (RC-ILIC-0110)

C. OP-901-110, Pressurizer Level Letdown Flow Control Valves Control Malfunction controller (RC-IHIC-0110)

D. OP-901-112, Charging and Letdown Flow Control Valves Letdown Malfunction controller (RC-IHIC-0110)

Facility: Waterford 3 Page 16 of 25

2015 NRC Exam SRO Written Exam SRO 17 Given:

The Turbine Building watch reports that Generator Hydrogen Press. Low annunciator is locked in at the H2 Control Panel Main Generator Hydrogen pressure is 29 psig and the crew has tripped the Main Turbine The crew will enter OP-901-101, Reactor Power Cutback and ____(1)____ concurrently.

To ensure no hot work or open flames are occurring in the Turbine Building due to the possible explosive mixture from Hydrogen Leakage the CRS will first _____(2)_____.

(1) (2)

A. OP-901-210, Turbine Trip contact the Work Management Center B. OP-901-210, Turbine Trip make a plant page C. OP-901-211, Generator make a plant page Malfunction D. OP-901-211, Generator contact the Work Management Center Malfunction Facility: Waterford 3 Page 17 of 25

2015 NRC Exam SRO Written Exam SRO 18 Given:

Spent Fuel Pooling Cooling Pump A is tagged out.

A loss of the 3B safety bus has occurred.

The CRS will direct the crew to enter ___(1)___To restore Spent Fuel Pool Cooling, the crew will start Spent Fuel Pool (SFP) Cooling Pump B after the EDG sequencer has timed out by ___(2)___.

(1) (2)

A. OP-901-311, Loss of Train B Safety manually energizing the SFP Bus only Cooling Pump at the 314B bus then taking the Control Switch to start B. OP-901-311, Loss of Train B Safety taking the Control Switch to start Bus only only C. OP-901-311, Loss of Train B Safety taking the Control Switch to start Bus and OP-901-513, Spent Fuel Pool only Cooling Malfunction concurrently D. OP-901-311, Loss of Train B Safety manually energizing the SFP Bus and OP-901-513, Spent Fuel Pool Cooling Pump at the 314B bus Cooling Malfunction concurrently then taking the Control switch to start Facility: Waterford 3 Page 18 of 25

2015 NRC Exam SRO Written Exam SRO 19 Per EN-OP-115, Conduct of Operations, a minimum of ___(1)___ members of the site fire brigade and a minimum of ___(2)___ emergency communicator(s) is required to fulfill minimum shift staffing requirements.

(1) (2)

A. four one B. four two C. five one D. five two Facility: Waterford 3 Page 19 of 25

2015 NRC Exam SRO Written Exam SRO 20 The surveillance requirements of TS 3.4.7, Specific Activity, states that Chemistry will be notified to perform a sample of the RCS for an isotopic iodine analysis following a reactor power change of greater than ___(1)___ percent within a one hour period.

This surveillance requirement states that the sample will be taken two to ___(2)___

hours following the downpower.

(1) (2)

A. 10 six B. 10 four C. 15 four D. 15 six Facility: Waterford 3 Page 20 of 25

2015 NRC Exam SRO Written Exam SRO 21 For planned outages, a risk assessment of the outage schedule is performed per the requirements located in ___(1)___. Based on the risk assessment process, the responsibility for ensuring the hanging, tracking, and prompt removal of protected equipment postings is the responsibility of the ___(2)___.

(1) (2)

A. PLG-009-014, Conduct of Shift Manager Planned outages B. PLG-009-014, Conduct of Outage Manager Planned outages C. OI-037-000, Operations Risk Shift Manager Assessment Guideline D. OI-037-000, Operations Risk Outage Manager Assessment Guideline Facility: Waterford 3 Page 21 of 25

2015 NRC Exam SRO Written Exam SRO 22 Given:

RAD MONITOR SYS ACTIVITY HI-HI annunciator is in alarm Plant Stack PIG A and B show rising activity HVAC Duct PIG D shows rising activity HVAC Duct PIG A is in alarm The CRS should carry out the actions in:

A. OP-901-401, High Airborne Activity in Control Room B. OP-901-402, High Airborne Activity in Reactor Auxiliary Building C. OP-901-403, High Airborne Activity in Containment D. OP-901-404, High Airborne Activity in Fuel Handling Building Facility: Waterford 3 Page 22 of 25

2015 NRC Exam SRO Written Exam SRO 23 The following plant conditions exist:

A radiological release is in progress following a LOCA outside of Containment The Emergency Director is evaluating E Plan Data is now available for a PARs determination The EC directs you to perform this determination per EP-002-052, Protective Action Guidelines.

The following data is available:

Duration of release is unknown Wind Directions is from 345 º EAB EAB 2 mile 2 mile 5 mile 5 mile TEDE CDE TEDE CDE TEDE CDE Thyroid Thyroid Thyroid Mr/hr Mr/hr Mr/hr Mr/hr Mr/hr Mr/hr 1250 3200 750 1900 50 730 Which ONE of the following PAR actions meets the required recommendations of EP-002-052, Protective Action Guidelines?

EVACUATE A. A1, B1, C1, D1 B. A1, B1, C1, D1, D2 C. A1, B1, C1, D1, B2, D2 D. A1, B1, C1, D1, D2, D3, D4 Facility: Waterford 3 Page 23 of 25

2015 NRC Exam SRO Written Exam SRO 24 As the Emergency Director, what is the time limit for notification of Operations Hotline Members when plant conditions warrant upgrading from an Unusual Event to an Alert?

A. 10 minutes B. 15 minutes C. 30 minutes D. 60 minutes Facility: Waterford 3 Page 24 of 25

2015 NRC Exam SRO Written Exam SRO 25 Given:

• A reactor trip has occurred

• The crew is performing Standard Post Trip actions per OP-902-000 and power to the Moisture Separator Re-heater (MSR) Control panel is not available.

The BOP will direct the auxiliary operator to isolate the Moisture Separator Re-heaters by ____(1)____ valves. This action is required to _____(2)_____ .

(1) (2)

A. taking to close the manual prevent overcooling the handwheel for the temperature RCS control valve isolation B. taking to close the manual prevent over-handwheel for the temperature pressurization of the control valve isolation MSR C. failing closed air operated prevent over-temperature control pressurization of the MSR D. failing closed air operated prevent overcooling the temperature control RCS Facility: Waterford 3 Page 25 of 25

WATERFORD 3 SES OP-902-009 Revision 310 Page 11 of 177 STANDARD APPENDICES Attachment 2-E Page 1 of 1 Figures Attachment 2-E: HPSI Flow Curve 1600 1400 1200 ACCEPTABLE FLOW 1000 800 600 UNACCEPTABLE 400 FLOW 200 0

0 50 100 150 200 250 Individual Injection Line Flow Rate (GPM)

End of Attachment 2-E

WATERFORD 3 SES OP-902-009 Revision 310 Page 12 of 177 STANDARD APPENDICES Attachment 2-F Page 1 of 1 Figures Attachment 2-F: LPSI Flow Curve RCS Pressure, PSIA 200 150 ACCEPTABLE FLOW 100 UNACCEPTABLE FLOW 50 0

0 500 1000 1500 2000 2500 3000 3500 4000 4500 5000 Train A or B Flow Rate (gpm)

End of Attachment 2-F

WATERFORD 3 SES OP-902-009 Revision 310 Page 7 of 177 STANDARD APPENDICES Attachment 2-A Page 1 of 1 2.0 Figures Attachment 2-A: RCS Pressure and Temperature Limits End of Attachment 2-A

PROTECTIVE ACTION GUIDELINES WORKSHEET, RELEASE OCCURRING USE ATT. 7.1 FOR INITIAL GENERAL EMERGENCY CLASSIFICATION RECOMMENDATIONS EVALUATION PERFORMED BY: _____________________________ DATE: __________________ TIME: _____________

(COMPLETE SECTIONS A, B & C EACH TIME AN EVALUATION IS PERFORMED.)

A. 0-2 MILE RESPONSE AREA B. 2-5 MILE RESPONSE AREA C. 5-10 MILE RESPONSE AREA PROJECTED DOSE AT THE EAB PROJECTED DOSE AT 2 MILES PROJECTED DOSE AT 5 MILES TEDE = _______ mrem TEDE = ________ mrem TEDE = __________ mrem CDE THYROID = _______ mrem CDE THYROID = ________ mrem CDE THYROID = ___________ mrem IS THE PROJECTED DOSE NO IS THE PROJECTED DOSE NO IS THE PROJECTED DOSE NO

> 1000 mrem TEDE? NO IMMEDIATE > 1000 mrem TEDE? NO IMMEDIATE > 1000 mrem TEDE? NO IMMEDIATE OR PROTECTIVE OR PROTECTIVE OR PROTECTIVE

> 5000 mrem CDE THYROID? ACTIONS > 5000 mrem CDE THYROID? ACTIONS > 5000 mrem CDE THYROID? ACTIONS REQUIRED REQUIRED REQUIRED YES YES YES EVACUATE (or Shelter) EVACUATE (or Shelter) EVACUATE (or Shelter) 0-2 MILE RECOMMENDATION: 2-5 MILE RECOMMENDATION: (See NOTE 1) 5-10 MILE RECOMMENDATION: (See NOTE 1)

NO PROTECTIVE ACTIONS REQUIRED NO PROTECTIVE ACTIONS REQUIRED NO PROTECTIVE ACTIONS REQUIRED EVACUATE AREAS A1, B1, C1, D1 EVACUATE AREAS ______________________ EVACUATE AREAS ____________________

SHELTER AREAS ______________________ MONITOR & PREPARE____________________ MONITOR & PREPARE__________________

SHELTER AREAS________________________ SHELTER AREAS______________________

NOTE 1: DETERMINE THE APPROPRIATE PROTECTIVE RESPONSE AREAS BY USING ATTACHMENT 7.3.

EP-002-052 REVISION 024 ATTACHMENT 7.2 (1 OF 1) 13

AFFECTED COMPASS SECTORS/PROTECTIVE RESPONSE AREAS CHART Directions for use:

Locate appropriate wind direction and find plume center line sector and two adjacent sectors in the "Affected Compass Sectors" column. The centerline sector is the middle sector of each set. The corresponding "Protective Response Areas" in which protective actions are to be implemented can then be found for downwind distances of interest by reading across the page.

Note that protective actions for any compass sectors in the two-mile radius (0-2 miles column) should be recommended for all 4 protective response areas in the two-mile radius as shown below.

AFFECTED PROTECTIVE RESPONSE AREAS WIND DIRECTION FROM COMPASS 0-2 MILES 2-5 MILES 5-10 MILES SECTORS (DOWNWIND) (DOWNWIND) 191.3 TO 213.8 (Sector K) A, B, C A1, B1, C1, D1 A2, B2 A3, B4 213.8 TO 236.3 (Sector L) B, C, D A1, B1, C1, D1 A2, B2 A3, B4 236.3 TO 258.8 (Sector M) C, D, E A1, B1, C1, D1 B2, D2 B3, B4 258.8 TO 281.3 (Sector N) D, E, F A1, B1, C1, D1 B2, D2 B3, B4, D3 281.3 TO 303.8 (Sector P) E, F, G A1, B1, C1, D1 B2, D2 B3, B4, D3 303.8 TO 326.3 (Sector Q) F, G, H A1, B1, C1, D1 B2, D2 B3, D3, D4 326.3 TO 348.8 (Sector R) G, H, J A1, B1, C1, D1 D2 D3, D4 348.8 TO 11.3 (Sector A) H, J, K A1, B1, C1, D1 D2 D4 11.3 TO 33.8 (Sector B) J, K, L A1, B1, C1, D1 C2, D2 C4, D4 33.8 TO 56.3 (Sector C) K, L, M A1, B1, C1, D1 C2, D2 C4, D4 56.3 TO 78.8 (Sector D) L, M, N A1, B1, C1, D1 C2 C4 78.8 TO 101.3 (Sector E) M, N, P A1, B1, C1, D1 C2 A4, C3, C4 101.3 TO 123.8 (Sector F) N, P, Q A1, B1, C1, D1 C2 A4, C3, C4 123.8 TO 146.3 (Sector G) P, Q, R A1, B1, C1, D1 A2, C2 A3, A4, C3 146.3 TO 168.8 (Sector H) Q, R, A A1, B1, C1, D1 A2, C2 A3, A4, C3 168.8 TO 191.3 (Sector J) R, A, B A1, B1, C1, D1 A2, C2 A3, A4 EP-002-052 REVISION 024 ATTACHMENT 7.3 (1 OF 1) 14

2015 NRC Written Examination Waterford 3 Reactor Operator and Senior Reactor Operator

1. D 26. B

2. A 27. D

3. C 28. D

4. A 29. B

5. C 30. C

6. C 31. D

7. B 32. B

8. A 33. C

9. D 34. A

10. C 35. A

11. C 36. B

12. D 37. B

13. A 38. C

14. B 39. B

15. B 40. D

16. D 41. B

17. B 42. D

18. C 43. A

19. A 44. D

20. D 45. C

21. C 46. D

22. B 47. A

23. D 48. C

24. D 49. C

25. A 50. D Page 1 of 2

2015 NRC Written Examination Waterford 3 Reactor Operator and Senior Reactor Operator

51. B S1. C

52. B S2. D

53. A S3. C

54. C S4. D

55. A S5. C

56. C S6. B

57. C S7. A

58. C S8. B

59. A S9. A

60. C S10. A

61. A S11. C

62. D S12. D

63. D S13. A

64. A S14. C

65. D S15. B

66. C S16. A

67. B S17. C

68. A S18. D

69. B S19. C

70. D S20. D

71. B S21. A

72. C S22. B

73. D S23. B

74. C S24. B

75. A S25. D Page 2 of 2