ML17122A048

2017-03 Final Written Examination

ML17122A048
Person / Time
Site:	Waterford
Issue date:	04/05/2017
From:	Vincent Gaddy Operations Branch IV
To:	Entergy Operations
References
Download: ML17122A048 (313)

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ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date: April 5, 2017 Facility/Unit: Waterford 3 Region: IV Reactor Type: CE Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.

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

Applicants Signature Results Examination Value 75 Points Applicants Score Points Applicants Grade Percent

2017 NRC Written Examination Waterford 3 Reactor Operator

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2017 NRC Exam RO Written Exam RO 1 Given:

Circulating Water Pump (CWP) A is unavailable and danger tagged Circulating Water Pumps B, C and D are running Plant tripped due to feedwater heater perturbations Upon the trip, the auto transfer to the Startup Transformers was not successful for the 1B and 2B electrical busses Following the plant trip, the plant is left with ____(1)____ Circulating Water Pump(s) running. The diagnostic flowchart will direct the crew to _____(2)_____ Recovery Procedure.

(1) (2)

A. one OP-902-006, Loss of Feedwater B. one OP-902-001, Reactor Trip C. zero OP-902-001, Reactor Trip D. zero OP-902-006, Loss of Feedwater Facility: Waterford 3 Page 1 of 75

2017 NRC Exam RO Written Exam RO 2 Given:

A Reactor trip occurred to due to a Pressurizer Relief Valve spuriously opening QSPDS indicates saturation conditions in the reactor vessel head Currently, Reactor Coolant System pressure is 1500 PSIA and steady Quench Tank temperature rose to 165°F and stabilized During the event, Pressurizer Level will ____(1)____.

The Pressurizer Relief Valve is currently ____(2)____.

(1) (2)

A. rise closed B. lower closed C. lower open D. rise open Facility: Waterford 3 Page 2 of 75

2017 NRC Exam RO Written Exam RO 3 Given:

A SBLOCA has occurred RCS pressure is 1600 psia and lowering Pressurizer level is 15% and lowering Charging Pump AB Assignment switch is in the NORM position Two CEAs failed to insert into the core on the reactor trip The ATC informs the CRS that only Charging Pump A is running.

To meet the minimum required number of Charging Pumps running, the crew will start Charging Pump(s) ____(1)____ .

The crew started the additional charging pump(s) to ensure ______(2)_____.

(1) (2)

A. B only adequate RCS makeup is available B. B only shutdown margin requirements met C. B and AB shutdown margin requirements met D. B and AB adequate RCS makeup is available Facility: Waterford 3 Page 3 of 75

2017 NRC Exam RO Written Exam RO 4 Given:

A large break LOCA occurred A SIAS, CIAS, MSIS and CSAS has occurred The crew has split CCW headers due to only one CCW pump available The crew has ___(1)___ train(s) of Essential Chillers available to manage the event.

The crew has ___(2)___ train(s) of Low Pressure Safety Injection available to manage the event.

(1) (2)

A. two two B. two one C. one one D. one two Facility: Waterford 3 Page 4 of 75

2017 NRC Exam RO Written Exam RO 5 The ATC notes the following indications on RCP 1A:

• Vapor Seal is 45 PSIG

• Upper Seal is 1180 PSIG

• Middle Seal is 1250 PSI

• RCS pressure is 2250 PSIA Which ONE of the following RCP 1A seals has failed or is degraded?

A. Vapor B. Upper C. Middle D. Lower Facility: Waterford 3 Page 5 of 75

2017 NRC Exam RO Written Exam RO 6 Given:

Plant operating at 100% power Charging Pump B is running with Charging Pumps A and AB in standby Upon a trip of Charging Pump B, the first backup charging pump is designed to start at a pressurizer level of __(1)__ %. If uncorrected, letdown will isolate on __(2)__ heat exchanger outlet temperature.

(1) (2)

A. 51.7 Regenerative B. 51.7 Letdown C. 53.1 Letdown D. 53.1 Regenerative Facility: Waterford 3 Page 6 of 75

2017 NRC Exam RO Written Exam RO 7 Given:

• The crew has entered OP-901-131, Shutdown Cooling Malfunction, due to System Leakage

• The crew has aligned LPSI Pumps for injection mode to maintain RCS level To prevent vortexing in the Safety Injection Sump following an RAS, OP-901-131, Shutdown Cooling Malfunction, directs the crew to ____(1)____.

The minimum injection flow to prevent a LPSI pump from overheating is _____(2)_____

gpm.

(1) (2)

A. verify only one LPSI 100 pump is running B. verify only one LPSI 25 pump is running C. limit SDC flow to 2000 100 gpm per LPSI train D. limit SDC flow to 2000 25 gpm per LPSI train Facility: Waterford 3 Page 7 of 75

2017 NRC Exam RO Written Exam RO 8 Given:

Plant is at 100% power RC-301A, Pressurizer Spray Valve indicates open Pressurizer Pressure is 2230 psia and dropping In accordance with OP-901-120, Pressurizer Pressure Control Malfunction, the CRS will direct the ATC to place the ____(1)____ controller in manual and close the spray valves.

The ATC will then place the spray valve selector switch to the _____(2)_____ position.

(1) (2)

A. Pressurizer Pressure 1A B. Pressurizer Pressure 1B C. Pressurizer Spray 1B D. Pressurizer Spray 1A Facility: Waterford 3 Page 8 of 75

2017 NRC Exam RO Written Exam RO 9 Given:

Plant is at 100% power An event occurs and automatic reactor trips fail Manual Reactor trip at CP-2 fails Manual Diverse Reactor Trip fails The crew will attempt to de-energize the Motor Generator Sets by opening the

___(1)___ feeder breakers. If this method of tripping the reactor is unsuccessful, the ATC will direct an NAO to the ___(1)___ safety switchgear room to locally open all Reactor Trip breakers.

(1) (2)

A. 31A and 31B A B. 31A and 31B B C. 32A and 32B A D. 32A and 32B B Facility: Waterford 3 Page 9 of 75

2017 NRC Exam RO Written Exam RO 10 Given:

A Steam Generator Tube Rupture in Steam Generator #1 and Loss of Offsite Power has occurred The crew has entered OP-902-007, Steam Generator Tube Rupture and has isolated Steam Generator #1 The maximum allowed Narrow Range level for the isolated steam generator is

____(1)____. Atmospheric Dump Valve (ADV) #1 can be used only as a last resort to maintain this level because the discharge flow path for the ADVs are not _____(2)_____.

(1) (2)

A. 70% isolable B. 85% monitored C. 70% monitored D. 85% isolable Facility: Waterford 3 Page 10 of 75

2017 NRC Exam RO Written Exam RO 11 OP-902-004, Excess Steam Demand Recovery Procedure, requires verifying no more than two Reactor Coolant Pumps running if Tcold is less than ___(1)___ °F to

__________(2)___________.

(1) (2)

A. 380 prevent generating excessive core uplift forces B. 380 aid in stabilizing Reactor Coolant System temperature after Steam Generator dryout C. 202 prevent generating excessive core uplift forces D. 202 aid in stabilizing Reactor Coolant System temperature after Steam Generator dryout Facility: Waterford 3 Page 11 of 75

2017 NRC Exam RO Written Exam RO 12 Given:

The reactor is tripped due to an Inadvertent Main Steam Isolation Signal (MSIS)

Emergency Feedwater (EFW) Pump B is danger tagged out Both Steam Generators are 43% NR level and dropping A subsequent loss of ____(1)____ would require that all running Reactor Coolant Pumps be tripped. Per the Tech Guide for OP-902-006, Loss of Feedwater Recovery Procedure, this action is required to ____(2)____.

(1) (2)

A. EFW Pump A prevent lifting Pressurizer safety valves B. EFW Pump AB reduce the heat input into the RCS C. EFW Pump AB prevent lifting Pressurizer safety valves D. EFW Pump A reduce the heat input into the RCS Facility: Waterford 3 Page 12 of 75

2017 NRC Exam RO Written Exam RO 13 Given:

A Station Blackout has occurred Offsite power has been restored to buses 3A and 3B A Probable Maximum Precipitation (PMP) event just commenced To restore a DCT Sump Pump, power must be restored to the non-safety section of Motor Control Center _____(1)_____.

OP-902-009 Appendix 20, Operation of DCT Sump Pumps, directs the crew to align at least one Dry Cooling Tower Motor Driven Sump Pump within ___(2)___ of the PMP event.

(1) (2)

A. 312A or B 30 minutes B. 314A or B 30 minutes C. 312A or B 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> D. 314A or B 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Facility: Waterford 3 Page 13 of 75

2017 NRC Exam RO Written Exam RO 14 Given:

Loss of offsite power has occurred Crew has entered OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery The sequencers for both Emergency Diesel Generators are timed out The CRS has directed the BOP to Verify Containment Cooling The BOP will ____(1)____ . Per the Tech Guide for OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery, this action is required to ____ (2) .

(1) (2)

A. secure one Containment Fan ensure emergency diesel Cooler generator fuel oil consumption is minimized B. align the Containment Fan ensure emergency diesel Coolers to slow speed generator fuel oil consumption is minimized C. align the Containment Fan prevent damage to Containment Coolers to slow speed Cooling ductwork D. secure one Containment Fan prevent damage to Containment Cooler Cooling ductwork Facility: Waterford 3 Page 14 of 75

2017 NRC Exam RO Written Exam RO 15 Given:

A loss of the 125 Volt DC bus A-DC has occurred The BOP will direct the NAO to secure the Emergency Diesel Generator (EDG) A Fuel Oil Transfer pump by ____(1)____. This action is required to ____(2)____.

(1) (2)

A. taking the local control prevent overflowing the Fuel Oil switch to off Day Tank B. taking the local control prevent pump overheating switch to off C. opening the pump supply prevent pump overheating breaker D. opening the pump supply prevent overflowing the Fuel Oil breaker Day Tank Facility: Waterford 3 Page 15 of 75

2017 NRC Exam RO Written Exam RO 16 Given:

A leak is occurring in the Component Cooling Water System Initially CCW Surge Tank Level A and B lowered to 0%

CCW Surge Tank level A remains at 0%

CCW Surge Tank level B recovered to ~ 55% and stabilized Which of the following is a potential location of the leak?

A. Supply pipe to Waste Gas Compressor A B. Supply pipe to Shutdown Cooling HX A C. Return pipe from Spent Fuel Pool HX A D. Return pipe from CEDM Fan Cooler A Facility: Waterford 3 Page 16 of 75

2017 NRC Exam RO Written Exam RO 17 Given:

Plant is at 100% power An instrument air leak has occurred Crew has entered OP-901-511, Instrument Air Malfunction The BOP will direct the NAO to ____(1)____ the set point for SA-125, SA Backup Supply for IA Press Cntl Valve, to force it open. When instrument air pressure lowers to 95 psig, _____(2)_____ .

(1) (2)

A. raise IA-123, Instrument Air Dryers Bypass solenoid, opens B. raise a plant shutdown in accordance with OP-010-005, Plant Shutdown, is required C. lower IA-123, Instrument Air Dryers Bypass solenoid, opens D. lower a plant shutdown in accordance with OP-010-005, Plant Shutdown, is required Facility: Waterford 3 Page 17 of 75

2017 NRC Exam RO Written Exam RO 18 Given:

Reactor power is 100%

A large load connected to the grid is lost causing a grid disturbance MVAR load changed from 60 MVAR out to 100 MVAR in The grid disturbance caused grid voltage to __(1)__.

To restore MVAR load to 60 MVAR out, the crew will adjust the Main Generator voltage adjust regulator control switch to ____(2)____.

(1) (2)

A. rise raise B. rise lower C. lower raise D. lower lower Facility: Waterford 3 Page 18 of 75

2017 NRC Exam RO Written Exam RO 19 Given:

Plant is at 100% power AB Charging pump is out of service with Charging Pumps A and B running An RCS leak is in progress and the crew is performing the required actions of OP-901-111, RCS Leak Subsequently, the STA reports that RCS leakage has been verified to be 90 gpm.

Which of the following is the appropriate action(s) to be performed?

A. Remain in OP-901-111, Reactor Coolant System Leak, and attempt to locate the leak.

B. Commence a normal shutdown in accordance with OP-010-005, Plant Shutdown.

C. Commence a rapid plant shutdown in accordance with OP-901-212, Rapid Plant Power Reduction.

D. Initiate a manual reactor trip, SIAS/CIAS, and go to OP-902-000, Standard Post Trip Actions.

Facility: Waterford 3 Page 19 of 75

2017 NRC Exam RO Written Exam RO 20 Given:

Plant is in MODE 3 Emergency Diesel Generator A is Danger Tagged out Plant has experienced a steam line leak resulting in an uncontrolled cooldown Loss of power to the 3A safety bus has occurred The AB safety busses are powered from the A Train CRS directs ATC operator to commence emergency boration Which of the following will be the emergency boration flow path aligned by the ATC?

A. BAM Tanks via BAM-143, Direct Boration Valve B. BAM Tanks via BAM-113 A and B, Boric Acid Gravity Feed Valves C. Boric Acid Makeup (BAM) Tank B via BAM Pump B and BAM-133, Emergency Boration Valve D. Refueling Water Storage Pool (RWSP) via CVC-507, RWSP to Charging Pump Suction Isolation Facility: Waterford 3 Page 20 of 75

2017 NRC Exam RO Written Exam RO 21 Given:

Plant is at 100% power The Pressurizer Level Control Channel Select Switch is in the Channel Y position The ATC reports that the Pressurizer Level Hi/Lo and Pressurizer Level Hi/Hi annunciators are in alarm One Charging Pump is running Pressurizer level is steady This event could be caused by which of the following failing high?

A. Reactor Regulating System RCS temperature Loop 1 hot leg indicator B. Pressurizer Level Control Channel X C. Pressurizer Level Control Channel Y D. Reactor Regulating System RCS temperature Loop 2 hot leg indicator Facility: Waterford 3 Page 21 of 75

2017 NRC Exam RO Written Exam RO 22 Given:

A Loss of offsite power has occurred and the crew is performing actions of OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery Condenser Vacuum has lowered to less than 14 INHG The Steam Bypass Control Valves are designed to close at a Condenser vacuum of

__(1)__ INHG.

The BOP will close the Main Steam Isolation Valves to ______(2)______.

(1) (2)

A. 6.4 prevent excessive cooldown B. 3.4 prevent excessive cooldown C. 3.4 ensure the Main Condenser is protected from over-pressurization D. 6.4 ensure the Main Condenser is protected from over-pressurization Facility: Waterford 3 Page 22 of 75

2017 NRC Exam RO Written Exam RO 23 With a Steam Generator Tube leak in progress it is ultimately desired to depressurize the RCS to within ___(1)___ psid of the ruptured Steam Generator to ___(2)___ and minimize the potential for Steam Generator overfill.

(1) (2) minimize the potential release to the A. 50 environment 50 prevent a loss of subcooled margin B.

minimize the potential release to the C. 100 environment prevent a loss of subcooled margin D. 100 Facility: Waterford 3 Page 23 of 75

2017 NRC Exam RO Written Exam RO 24 Given:

Gas Decay Tank(s) discharge is in progress in accordance with OP-007-003, Gaseous Waste Management The RM-11 alarms and the associated annunciator is received The validity of this annunciator is verified by checking Waste Gas Flow and Rad Recorder (GWMIFRR0648) located on __(1)__ .

High radiation on __(2)__ Radiation Monitor will cause the Gas Decay Tank discharge to automatically isolate.

(1) (2)

A. LCP-42 either Plant Stack Vent B. CP-4 either Plant Stack Vent C. LCP-42 the Gaseous Waste Management D. CP-4 the Gaseous Waste Management Facility: Waterford 3 Page 24 of 75

2017 NRC Exam RO Written Exam RO 25 Given:

A fire developed in the Control Room, requiring the Control Room to be evacuated The crew is performing OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown MS-116A, SG1 Atmospheric Dump, has spuriously opened Prior to leaving the Control Room, the BOP will place ____(1)____ to manual and lower output to 0% and ____(2)____ .

(1) (2)

A. only the MS-116A manually initiate a Main controller Steam Isolation Signal B. only the MS-116A close both Main Steam controller Isolation Valves using its C/S C. both MS-116A and B close both Main Steam controllers Isolation Valves using its C/S D. both MS-116A and B manually initiate a Main controllers Steam Isolation Signal Facility: Waterford 3 Page 25 of 75

2017 NRC Exam RO Written Exam RO 26 Given:

Small Break LOCA occurred one hour ago Pressurizer level is 0%

RCS is saturated The Reactor Vessel Level Monitoring System can be monitored using QSPDS and recorders on ____(1)____.

To meet the requirements to perform Hot and Cold Leg Injection, the CRS will direct the ATC to report when vessel plenum level is less than 80%. The equivalent level will be indicated on the RVLMS QSPDS mimic when level ___(2)___ indicates voided.

(1) (2)

A. CP-8 6 B. CP-7 6 C. CP-7 5 D. CP-8 5 Facility: Waterford 3 Page 26 of 75

2017 NRC Exam RO Written Exam RO 27 Given:

A steam line rupture has occurred on Steam Generator #1 and the crew is performing the actions of OP-902-004, Excess Steam Demand Recovery Procedure RCS pressure is 1600 PSIA Containment pressure is 18 PSIA Steam Generator #1 has been isolated in accordance with OP-902-004, Excess Steam Demand Recovery Procedure The crew is ready to perform a controlled plant cooldown Which ONE of the following describes the method and maximum rate allowed to perform the RCS cooldown in accordance with OP-902-004?

Cooldown using A. ADV(s) at no greater than 50°F per hour B. SBCS at no greater than 100°F per hour C. SBCS at no greater than 50°F per hour D. ADV(s) at no greater than 100°F per hour Facility: Waterford 3 Page 27 of 75

2017 NRC Exam RO Written Exam RO 28 To prevent motor overload in excess of the nameplate horsepower rating, the minimum RCS cold leg temperature for RCP operation is 350ºF when operating in three pump configuration using RCP ____(1)____.

This limitation is applicable since this pump requires more brake horsepower because it

___(2)___ of the four reactor coolant pumps.

(1) (2)

A. 1A has the largest flywheel B. 2A has the largest flywheel C. 2A develops the highest head D. 1A develops the highest head Facility: Waterford 3 Page 28 of 75

2017 NRC Exam RO Written Exam RO 29 Given:

The plant is at 100% power Reactor Coolant Pump (RCP) 1A seal has failed and the BOP is lowering ACC Header A CCW HX outlet TCV (ACC-126A) controller set point to restore RCP 1A controlled bleedoff temperature back into the normal band.

As a result, the ATC may be required to ________________.

A. borate due to Letdown Heat Exchanger outlet temperature lowering B. borate due to Letdown Heat Exchanger outlet temperature rising C. dilute due to Letdown Heat Exchanger outlet temperature lowering D. dilute due to Letdown Heat Exchanger outlet temperature rising Facility: Waterford 3 Page 29 of 75

2017 NRC Exam RO Written Exam RO 30 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 30 of 75

2017 NRC Exam RO Written Exam RO 31 Given:

Plant is in MODE 5 The RCS was drained to 14.5 ft. MSL LPSI pumps have been secured due to RCS leakage HPSI Pump B has been started in accordance with OP-901-131, Shutdown Cooling Malfunction RCS level has been raised to and is being maintained at 16 ft. MSL To restore a Shutdown Cooling train to service in accordance with OP-901-131, the crew will vent and start LPSI Pump ____(1)____ because HPSI Pump B is injecting to

_____(2)_____ .

(1) (2)

A. A Hot Leg 1 B. A Hot Leg 2 C. B Hot Leg 1 D. B Hot Leg 2 Facility: Waterford 3 Page 31 of 75

2017 NRC Exam RO Written Exam RO 32 Given:

Which ONE of the following describes the operations associated with SI-106A, RWSP Outlet Isolation valve, upon the receipt of a Recirculation Actuation Signal (RAS)?

A. Will automatically close immediately upon RAS B. Will automatically close once SI-602A is fully open C. Can be manually closed from CP-8 immediately upon RAS D. Can be manually closed from CP-8 once SI-602A is fully open Facility: Waterford 3 Page 32 of 75

2017 NRC Exam RO Written Exam RO 33 Given:

An Excess Steam Demand occurred inside containment SIAS, CIAS, MSIS and CSAS have been initiated Pressurizer level is 2% and starting to rise Representative CET temperature and RCS pressure start to rise Based on the current conditions, the crew will ____(1)____. The Pressurizer Safety Valves are designed to lift at ____(2)____ psia.

(1) (2)

A. stabilize RCS pressure above 2500 HPSI Pump shutoff head B. stabilize RCS pressure above 2750 HPSI Pump shutoff head C. secure one HPSI Pump at a time 2500 D. secure one HPSI Pump at a time 2750 Facility: Waterford 3 Page 33 of 75

2017 NRC Exam RO Written Exam RO 34 The normal source of makeup to the Auxiliary Component Cooling Water (ACCW) Wet Cooling Towers is the _______(1)_______. The normal source of makeup water to the Component Cooling Water Surge Tank is the _______(2)_________.

(1) (2)

A. Condensate Storage Pool Demineralized Water Storage Tank B. Condensate Storage Pool Condensate Storage Pool C. Demineralized Water Storage Tank Condensate Storage Pool D. Demineralized Water Storage Tank Demineralized Water Storage Tank Facility: Waterford 3 Page 34 of 75

2017 NRC Exam RO Written Exam RO 35 Given:

A Steam Line Break has occurred outside containment The crew has manually initiated a MSIS, CIAS and SIAS As a result, Component Cooling Water Flow has been lost to ________________.

A. the Spent Fuel Pool Heat Exchanger B. Emergency Diesel Generator B C. the Reactor Coolant Pumps D. Train B Dry Cooling Tower Facility: Waterford 3 Page 35 of 75

2017 NRC Exam RO Written Exam RO 36 Given:

Plant is at 100% power Pressurizer Pressure Channel X/Y recorder (RC-IPR-0100) indicates that the in-service Pressurizer Pressure Control Channel instrument has failed low The Pressurizer Pressure Controller output will ____(1)____. The failed control channel will energize ___(2)___ heaters.

(1) (2)

A. rise both proportional and backup B. lower both proportional and backup C. lower only proportional D. rise only proportional Facility: Waterford 3 Page 36 of 75

2017 NRC Exam RO Written Exam RO 37 OP-010-005 Attachment 9.13 Boron Equalizations directs the crew to avoid operating Pressurizer pressure near the heater cutout pressure of ____(1)____ psia while performing Boron Equalization.

Boron Equalization shall be initiated if a minimum change in RCS boron concentration of greater than ____(1)____ ppm is anticipated.

(1) (2)

A. 2275 50 B. 2275 10 C. 2270 50 D. 2270 10 Facility: Waterford 3 Page 37 of 75

2017 NRC Exam RO Written Exam RO 38 Given:

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

_______(2)______.

(1) (2)

A. 1, 2, 5, and 6 occurs B. 1, 2, 5, and 6 does not occur C. 1, 3, 5, and 7 does not occur D. 1, 3, 5, and 7 occurs Facility: Waterford 3 Page 38 of 75

2017 NRC Exam RO Written Exam RO 39 What is the power supply to MS-401A, EFW Pump Turbine Steam Supply Valve?

A. A-DC B. AB-DC C. MCC-312A D. MCC-312AB Facility: Waterford 3 Page 39 of 75

2017 NRC Exam RO Written Exam RO 40 Given:

An Excess Steam Demand event has occurred The crew has entered OP-902-004, Excess Steam Demand Recovery Procedure Following the Main Steam Isolation Signal (MSIS), indications are:

Steam Generator 1 pressure is 400 PSIA Steam Generator 2 pressure is 505 PSIA Steam Generator 1 level is 9% NR and lowering Steam Generator 2 level is 9% NR and lowering Currently, ____(1)____ initiated.

When isolating Steam Generator #1, the BOP will direct the NAO to check SG1

_____(2)________ side Main Steam Safety Valves are closed.

(1) (2)

A. only EFAS-2 is East B. only EFAS-2 is West C. neither EFAS-1 nor East EFAS-2 are D. neither EFAS-1 nor West EFAS-2 are Facility: Waterford 3 Page 40 of 75

2017 NRC Exam RO Written Exam RO 41 Given:

A Small Break LOCA has occurred The BOP reports that Component Cooling Water has been lost to one train of Containment Fan Coolers and containment temperature is rising Per OI-038-000, EOP Operations Expectations/Guidance Procedure, ____(1)____

parameter values will be used if a harsh environment exists in containment . A harsh environment is defined as Containment Temperature greater than or equal to a minimum temperature of _____(2)_____ ºF.

(1) (2)

A. underlined 180 B. underlined 200 C. bracketed 200 D. bracketed 180 Facility: Waterford 3 Page 41 of 75

2017 NRC Exam RO Written Exam RO 42 Containment Spray (CS) Pump B is powered from which bus?

A. SWGR 31B B. SWGR 3B C. SWGR 1B D. SWGR 2B Facility: Waterford 3 Page 42 of 75

2017 NRC Exam RO Written Exam RO 43 Given:

A reactor startup has commenced following a reactor trip from 100% power that occurred 4 days ago 250 EFPD SBCS valves are maintaining Tave Which ONE of the following will cause actual critical rod position to be LOWER than estimated critical rod position?

A. SBCS master controller setpoint fails upward 50 PSI B. SBCS permissive setpoint fails upward 50 PSI C. SBCS master controller setpoint fails downward 50 PSI D. SBCS permissive setpoint fails downward 50 PSI Facility: Waterford 3 Page 43 of 75

2017 NRC Exam RO Written Exam RO 44 Given:

Power is 100%

SG-ILR-1111, Steam Generator 1 Narrow Range level indicator is reading 0% on the CP-1 recorder SG-ILR-1105, Steam Generator 1 Narrow Range level indicator is reading 68%

on the CP-1 recorder All Narrow Range Steam Generator levels on CP-8 are indicating 68%

With the above conditions, a reactor trip occurs.

Main Feedwater Pump A speed controller ___(1)___ . Main Feedwater Regulating Valve A and Startup Feedwater Regulating Valve A Controllers __(2)___.

(1) (2)

A. lowers to 3900 RPM remain at their pre-trip positions B. lowers to 3900 RPM reposition to their Reactor Trip Positions C. remains at 4500 RPM remain at their pre-trip positions D. remains at 4500 RPM reposition to their Reactor Trip Positions Facility: Waterford 3 Page 44 of 75

2017 NRC Exam RO Written Exam RO 45 Given:

The BOP reports rising Turbine Cooling Water (TCW) temperatures The crew enters OP-901-512, Loss of Turbine Cooling Water The BOP will lower TCW temperature using TC-147, Turbine Cooling Water Temperature Control, by taking the control switch to the ____(1)____ position.

To maintain TCW system pressure constant, the control switch for TC-135, Turbine Cooling Water Pressure Control, will be taken to the ___(2)___ position.

(1) (2)

A. less more B. less less C. more less D. more more Facility: Waterford 3 Page 45 of 75

2017 NRC Exam RO Written Exam RO 46 The Auxiliary Feedwater Pump (AFW Pump) is powered from which bus?

A. 1A B. 2A C. 1B D. 2B Facility: Waterford 3 Page 46 of 75

2017 NRC Exam RO Written Exam RO 47 A Loss of MFW event has occurred. After a manual Reactor trip, the following conditions are observed:

SG 1 pressure is 980 PSIA SG 2 pressure is 960 PSIA SG 1 level is 51% WR level and lowering SG 2 level is 38% WR level and lowering Pressurizer pressure 1900 PSIA Containment pressure 15.3 PSIA With SG 2 EFW flow transmitter failed high, which of the following describes the EFW system response for SG 2?

A. Primary FCV and Backup FCV remain closed.

B. Primary FCV remains closed and backup FCV opens to 175 GPM.

C. Primary FCV opens to preset valve position and Backup FCV remains closed.

D. Primary FCV opens to preset valve position and Backup FCV opens to 400 GPM flow value.

Facility: Waterford 3 Page 47 of 75

2017 NRC Exam RO Written Exam RO 48 Given:

• EDG A is running paralleled in TEST mode for surveillance OP-903-068, Emergency Diesel Generator and Subgroup Relay Operability Verification

• A SIAS occurred with NO Loss of Offsite Power condition The EDG output breaker will (1) and the HPSI Pumps will be started (2) .

(1) (2)

A. OPEN by the sequencer B. OPEN immediately C. stay CLOSED by the sequencer D. stay CLOSED immediately Facility: Waterford 3 Page 48 of 75

2017 NRC Exam RO Written Exam RO 49 The A, B and AB DC Bus voltages can be read on ___(1)___.

A reading of 140 VDC on a DC battery charger is indicative of a charger in ____(2)____.

(1) (2)

A. CP-1 and the Plant float mode Monitoring Computer B. CP-1 only float mode C. CP-1 and the Plant equalize mode Monitoring Computer D. CP-1 only equalize mode Facility: Waterford 3 Page 49 of 75

2017 NRC Exam RO Written Exam RO 50 Given:

The crew is restoring Emergency Diesel Generator (EDG) B following a Station Blackout Emergency Diesel Generator B has started and the output breaker is closed The Input Transformer to MCC 315B develops a direct short to ground upon being re-energized by the 1 second Sequencer Load Block (S1 relay)

An undervoltage condition exists on 4160 Volt Bus 3B Which of the following conditions describes the Sequencer response?

A. Immediately stops the automatic loading process due to Under Voltage Override (UVO) condition.

B. Immediately stops the automatic loading process due to Sequencer Lockout (SLO) condition.

C. Stops the automatic loading process when the 7 second Load Block (S3 relay) is reached.

D. Stops the automatic loading process when the 17 second Load Block (S4 relay) is reached.

Facility: Waterford 3 Page 50 of 75

2017 NRC Exam RO Written Exam RO 51 Given:

Solid Plant operations are in progress RCS temperature is 120°F and stable Letdown Back Pressure Controller is operating in AUTO CCW flow is reduced to the in-service SDC Heat Exchanger RCS pressure will ____(1)____ until the Letdown Back Pressure Control Valve throttles

_____(2)____.

(1) (2)

A. lower closed B. rise closed C. lower open D. rise open Facility: Waterford 3 Page 51 of 75

2017 NRC Exam RO Written Exam RO 52 Given:

High Activity is detected on Industrial Waste Sump (IWS) radiation monitor PRM-IRE-6778 The high activity on the IWS radiation monitor will ____(1)____ The crew will enter

_____(2)____.

(1) (2)

A. secure the IWS pumps OP-901-414, Effluent Discharge High Radiation B. secure the IWS pumps OP-901-412, Liquid Waste Discharge High Radiation C. align the IWS pump OP-901-412, Liquid Waste discharge MOVs to the Discharge High Radiation Waste Tanks D. align the IWS pump OP-901-414, Effluent discharge MOVs to the Discharge High Radiation Waste Tanks Facility: Waterford 3 Page 52 of 75

2017 NRC Exam RO Written Exam RO 53 When aligning Auxiliary Component Cooling Water (ACCW) flow to the Essential Chillers the ACCW valves open___(1)____ .

During the transition to ACCW, the ACCW ___(2)____ valves to the Essential Chillers are interlocked to open first.

(1) (2)

A. first, then the CCW valves inlet close B. after the CCW valves outlet close C. after the CCW valves inlet close D. first, then the CCW valves outlet close Facility: Waterford 3 Page 53 of 75

2017 NRC Exam RO Written Exam RO 54 Given:

Instrument Air has been lost to Containment The crew is performing the actions of OP-901-511, Loss of Instrument Air CEDM COOLING COILS CCW INLET HDR ISOL, CC-646, is failed ____(1)____.

Containment Fan Cooler discharge air flow to the ring header is ___(2)___ .

(1) (2)

A. open unaffected B. closed unaffected C. open bypassed D. closed bypassed Facility: Waterford 3 Page 54 of 75

2017 NRC Exam RO Written Exam RO 55 If Containment to ____(1)____ differential pressure reaches 8.5 INWD, Containment Vacuum Relief Valves, CVR-101 and CVR-201, open, and will ______(2)_____ when differential pressure lowers to the reset value.

(1) (2)

A. annulus automatically close B. ambient automatically close C. ambient require manual closure D. annulus require manual closure Facility: Waterford 3 Page 55 of 75

2017 NRC Exam RO Written Exam RO 56 Given:

The crew is performing a down power in accordance with OP-901-212, Rapid Plant Power reduction Due to the down power, ASI will be trending in the ____(1)____ direction. To compensate, the ATC will ____(2)____ control rods.

(1) (2)

A. negative insert B. negative withdraw C. positive withdraw D. positive insert Facility: Waterford 3 Page 56 of 75

2017 NRC Exam RO Written Exam RO 57 To provide for detection and isolation of a Reactor Coolant leak through the Reactor Coolant Pump 1A seal cooler, the 1A RCP Seal Cooler (CC-679A/CC-6651A) isolation valves will close on a Component Cooling Water (CCW) return temperature of

____(1)____ ºF.

The 1A RCP Seal Cooler (CC-679A/CC-6651A) isolation valves interlock on high Component Cooling Water (CCW) return temperature ____(2)____ be manually overridden.

(1) (2)

A. 145 can B. 145 cannot C. 155 can D. 155 cannot Facility: Waterford 3 Page 57 of 75

2017 NRC Exam RO Written Exam RO 58 Given:

A plant Shutdown is in progress in accordance with OP-010-005, Plant Shutdown At 1X10-4 % power and dropping, the CPC trips are (can be)___(1)___ bypassed and the High Log Power Trips are (can be) __(2)___ enabled.

(1) (2)

A. manually manually B. automatically manually C. automatically automatically D. manually automatically Facility: Waterford 3 Page 58 of 75

2017 NRC Exam RO Written Exam RO 59 Given:

A Reactor trip occurred due to a loss of offsite power 20 minutes ago Pressurizer pressure is 2250 PSIA and slowly rising Tcold Loop 1A and 1B are 545°F and stable Thot Loop1 is 568°F and stable Tcold Loop 2A and 2B are 560°F and slowly rising Thot Loop 2 is 565°F and stable Representative CET temperature is 570°F and stable The minimum criteria for verifying single phase natural circulation is____(1)____. The crew should adjust feeding and steaming of Steam Generator __(2)__.

(1) (2)

A. NOT met 1 B. met 1 C. met 2 D. NOT met 2 Facility: Waterford 3 Page 59 of 75

2017 NRC Exam RO Written Exam RO 60 Given:

The RAB watch reports lowering Spent Fuel Pool level The crew enters OP-901-513, Spent Fuel Pool Cooling Malfunction The makeup source to Spent Fuel Pool can be from the ____(1)____. The ATC will verify the Spent Fuel Pool Cooling Pumps trip at __(2)__ MSL.

(1) (2)

A. Condensate Storage Pool only 416 B. Refuel Water Storage Pool or 416 Condensate Storage Pool C. Refuel Water Storage Pool or 439 Condensate Storage Pool D. Condensate Storage Pool only 439 Facility: Waterford 3 Page 60 of 75

2017 NRC Exam RO Written Exam RO 61 Given:

Plant is initially at 100% power RCS Tavg is 573 F Reactor Power Cutback system is out of service Reactor trip on Turbine trip is enabled Turbine trip occurs Which of the following describes the Steam Bypass Control system response immediately following the Turbine trip?

A. All valves quick open B. Only valves 1 through 5 quick open C. Only valves 1 through 3 quick open D. No valves quick open Facility: Waterford 3 Page 61 of 75

2017 NRC Exam RO Written Exam RO 62 Given:

Plant is at 100% power One Steam Bypass Control Valve has failed open The crew has entered OP-901-221, Secondary System Transient The BOP will attempt to close the failed open Steam Bypass Control Valve from CP-1 by placing the Valve Mode (Permissive) Select Switch to the ____(1)____ position. If the Steam Bypass fails to close, the crew will reduce reactor power to less than 100% power by ____(2)____.

(1) (2)

A. OFF adjusting main turbine load B. MANUAL adjusting main turbine load C. OFF commencing direct boration to the RCS D. MANUAL commencing direct boration to the RCS Facility: Waterford 3 Page 62 of 75

2017 NRC Exam RO Written Exam RO 63 Given:

Plant is at 100% power Condenser Vacuum Pump B has tripped To maintain a suction path for Condenser Air Evacuation PIG Rad Monitor (PRM-IRE-0004), the BOP will verify Condenser Vacuum Pump ____(1)____

is running. Condenser Vacuum Pumps are designed to automatically start at a Main Condenser Vacuum of ____(2)____ inches Hg.

(1) (2)

A. A 25 B. A 26 C. C 26 D. C 25 Facility: Waterford 3 Page 63 of 75

2017 NRC Exam RO Written Exam RO 64 Given:

The crew is scheduled to perform Section 6.4, Discharging Gas Decay Tank, per OP-007-003, Gaseous Waste Management Discharging ____(1)____ is the preferred method. The crew is required to secure the release if at least one RAB normal __(2)__ fan is not running.

(1) (2)

A. all three Gas Decay exhaust Tanks simultaneously B. all three Gas Decay supply Tanks simultaneously C. one Gas Decay Tank at a supply time D. one Gas Decay Tank at a exhaust time Facility: Waterford 3 Page 64 of 75

2017 NRC Exam RO Written Exam RO 65 Given:

A Shutdown of the Circulating Water System is in progress Circulating Water Pumps C and D are operating The BOP takes the control switch for Circulating Water Pump C to stop. Circulating Water Pump D ____(1)____.

If required, manual operation of Circ Water Pump C or D Discharge Isolation Valves (CW-103C(D)) will be performed ___(2)___ .

(1) (2)

A. can be stopped after in the turbine generator building 100 seconds B. will trip immediately at the intake structure C. will trip immediately in the turbine generator building D. can be stopped after at the intake structure 100 seconds Facility: Waterford 3 Page 65 of 75

2017 NRC Exam RO Written Exam RO 66 A Reactor Operator has not stood an on-shift watch in the previous four weeks.

Per OI-042-000, Watch Station Processes, the minimum required Station Logs to be reviewed prior to turnover is ________ week(s).

A. one B. two C. three D. four Facility: Waterford 3 Page 66 of 75

2017 NRC Exam RO Written Exam RO 67 Per OP-903-001, Technical Specification Surveillance Logs, the Reactor Operator will verify the POWER DEPENDENT INSERTION LIMIT annunciator clear to ensure Group P and ____(1)____ CEAs are within their Transient Insertion Limits.

This annunciator receives its CEA position input from the CEA ___(2)___ .

(1) (2)

A. all regulating groups Reed Switch Position transmitters B. group 6 only Reed Switch Position transmitters C. group 6 only Pulse Counters D. all regulating groups Pulse Counters Facility: Waterford 3 Page 67 of 75

2017 NRC Exam RO Written Exam RO 68 Given:

Plant is in a refueling outage Refueling Group is preparing to withdraw the first fuel assembly from the Reactor Vessel The Source Range Neutron Flux Monitors shall be operable and operating with (1) channel(s) operable with continuous visible indication in the control room and (2) channel(s) operable with audible indication in the containment and the control room.

(1) (2)

A. two one B. one one C. two two D. one two Facility: Waterford 3 Page 68 of 75

2017 NRC Exam RO Written Exam RO 69 Per OI-002-000, Annunciator and Control Room Instrumentation Status Control, annunciators that are disabled in conjunction with refuel outage windows ____(1)____

required to be documented in the Watchstation Deficiency Database. These outage annunciators will be identified by placing a __(2)__ dot on the annunciator window.

(1) (2) are not red are yellow are red are not yellow Facility: Waterford 3 Page 69 of 75

2017 NRC Exam RO Written Exam RO 70 Given the following plant conditions:

RCS average temperature: 425 F All control rods: Fully inserted What is the current plant Mode as defined in Technical Specifications for these conditions?

A. MODE 5 B. MODE 4 C. MODE 3 D. MODE 2 Facility: Waterford 3 Page 70 of 75

2017 NRC Exam RO Written Exam RO 71 In accordance with OP-100-014, Technical Specification and Technical Requirements Compliance, the crew is required to enter the appropriate cascading Technical Specifications upon declaring a(an) ___(1)____ inoperable.

The crew will be required to ____(2)____ within one hour.

(1) (2)

A. Emergency Diesel Generator complete OP-903-066, Electrical Breaker Alignment Check B. Component Cooling Water Train complete OP-903-066, Electrical Breaker Alignment Check C. Component Cooling Water Train verify Emergency Feedwater Pump AB operable D. Emergency Diesel Generator verify Emergency Feedwater Pump AB operable Facility: Waterford 3 Page 71 of 75

2017 NRC Exam RO Written Exam RO 72 Given:

The plant is at 10% Power A containment entry is desired Which of the following areas inside containment are forbidden from being entered?

A. Pressurizer Cubicle below +21 elevation B. +46 elevation at the Quench Tank C. Main Steam Line Crossovers on the +46 elevation D. RCS Cold Leg 1A penetration through the D Ring Wall Facility: Waterford 3 Page 72 of 75

2017 NRC Exam RO Written Exam RO 73 Per OI-038-000, Emergency Operating Procedures Operations Expectations/Guidance, following a momentary loss of power or voltage dip, some radiation monitors needed for Emergency Plan may require ___________.

A. a restart of the sample pump B. verification of proper setpoint C. reset of their power supply D. local purge operation Facility: Waterford 3 Page 73 of 75

2017 NRC Exam RO Written Exam RO 74 Which of the following is prohibited by OP-100-017, Emergency Operating Procedure Implementation Guide?

A. Simultaneous performance of more than one safety function concurrently while in the Functional Recovery Procedure B. Simultaneous performance of an Optimal Recovery Procedure and an Off-Normal Procedure C. Simultaneous performance of more than one Optimal Recovery Procedure D. Simultaneous performance of an Optimal Recovery Procedure and a System Operating Procedure Facility: Waterford 3 Page 74 of 75

2017 NRC Exam RO Written Exam RO 75 A site Fire Brigade of at least __(1)__ members shall be maintained on site at all times.

The fire brigade composition may be less than the minimum requirement for a period of time not to exceed a maximum of ___(2)___ hour(s).

(1) (2)

A. four one B. four two C. five one D. five two Facility: Waterford 3 Page 75 of 75

2017 NRC Written Examination Waterford 3 Reactor Operator and Senior Reactor Operator

1. C 26. C

2. A 27. A

3. A 28. C

4. B 29. A

5. C 30. D

6. D 31. B

7. C 32. D

8. C 33. A

9. D 34. D

10. B 35. A

11. A 36. B

12. B 37. C

13. B 38. D

14. D 39. B

15. D 40. D

16. B 41. C

17. A 42. B

18. A 43. C

19. D 44. A

20. B 45. B

21. B 46. C

22. C 47. C

23. A 48. A

24. D 49. C

25. B 50. D Page 1 of 2

2017 NRC Written Examination Waterford 3 Reactor Operator and Senior Reactor Operator

51. D S1. C

52. D S2. D

53. C S3. C

54. C S4. D

55. D S5. A

56. A S6. C

57. C S7. B

58. D S8. D

59. C S9. A

60. B S10. C

61. B S11. A

62. A S12. D

63. C S13. A

64. A S14. B

65. B S15. D

66. B S16. D

67. D S17. B

68. A S18. D

69. A S19. A

70. C S20. A

71. B S21. B

72. D S22. B

73. A S23. A

74. C S24. C

75. D S25. C Page 2 of 2

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000007 (CE/E02)EA1.2 Importance Rating 3.3 K/A Statement 007 Reactor Trip Recovery, EA1.2: Ability to operate and / or monitor the following as they apply to the (Reactor Trip Recovery): Operating behavior characteristics of the facility.

Proposed Question: RO 1 Rev: 2 Given:

Circulating Water Pump (CWP) A is unavailable and danger tagged Circulating Water Pumps B, C and D are running Plant tripped due to feedwater heater perturbations Upon the trip, the auto transfer to the Startup Transformers was not successful for the 1B and 2B electrical busses Following the plant trip, the plant is left with ____(1)____ Circulating Water Pump(s) running. The diagnostic flowchart will direct the crew to _____(2)_____ Recovery Procedure.

(1) (2)

A. one OP-902-006, Loss of Feedwater B. one OP-902-001, Reactor Trip C. zero OP-902-001, Reactor Trip D. zero OP-902-006, Loss of Feedwater Revision 2 Facility: Waterford 3 Page 1 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. With three CW pumps running and two trip, the remaining CW pump is designed to trip. The EOPs have been revised such that with AFW and /or 100% EFW flow equivalent available, the Reactor Trip Recovery Procedure is entered. Loss of MFW Recovery Procedure would have been correct prior to the EOP revision.

B. Incorrect. With three CW pumps running and two trip, the remaining CW pump is designed to trip. Part 2 is correct.

C. CORRECT: This question is from a W3 event (CR-WF3-2015-3565). With three CW pumps running and two trip, the remaining CW pump is designed to trip. Since CWP A is initially tagged out, the plant is left with zero CW pumps running. The plant is left without Main Feed Pumps due to an eventual loss of Condenser Vacuum. In this event, the crew diagnosed into the Loss of Main Feedwater Recovery Procedure (OP-902-006). The EOPs have since been revised such that with AFW and /or 100% EFW flow equivalent available, the Reactor Trip Recovery Procedure (OP-902-001) is entered.

D. Incorrect. Part 1 is correct. The EOPs have been revised such that with AFW and /or 100%

EFW flow equivalent available, the Reactor Trip Recovery Procedure is entered. Loss of MFW Recovery Procedure would have been correct prior to the EOP revision.

Technical Reference(s): TG-OP-902-001 page 24 Rev. 306 (Attach if not previously provided) OP-902-001 pages 8 and 16 Rev. 16 (including version/revision number) OP-902-009 Appendix 1 Rev. 315 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE01 obj. 12,16 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 7, 10 55.43 Comments:

NRC Comment: Added upon the reactor trip to the last bullet in the stem.

Revision 2 Facility: Waterford 3 Page 2 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000008 AK2.01 Importance Rating 2.7 K/A Statement 008 Pressurizer Vapor Space Accident, AK2.01: Knowledge of the interrelations between the Pressurizer Vapor Space Accident and the following: Valves.

Proposed Question: RO 2 Rev: 2 Given:

A Reactor trip occurred to due to a Pressurizer Relief Valve spuriously opening QSPDS indicates saturation conditions in the reactor vessel head Currently, Reactor Coolant System pressure is 1500 PSIA and steady Quench Tank temperature rose to 165°F and stabilized During the event, Pressurizer Level will ____(1)____.

The Pressurizer Relief Valve is currently ____(2)____.

(1) (2)

A. rise closed B. lower closed C. lower open D. rise open Revision 2 Facility: Waterford 3 Page 3 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: With saturation conditions in the vessel head, pressurizer level will rise due to bubble formation in the head and no RCPs running. Based on quench tank temperature stabilizing below the saturation temperature of containment, the applicant can determine that the rupture disc on the quench tank is intact and since temperature is steady, the relief valve is closed.

B. Incorrect. Pressurizer level will rise due to bubble formation in the head. Pressurizer level lowering is plausible because there is a mass loss of the RCS out of the relief valve. Part 2 is correct.

C. Incorrect. Pressurizer level will rise due to bubble formation in the head. Pressurizer level lowering is plausible because there is a mass loss of the RCS out of the relief valve Quench tank temperature would continue to rise if the valve were still open. Part 2 is plausible Quench tank temperature would eventually stabilize at saturation temperature for containment pressure once the QT diaphragm ruptured.

D. Incorrect. Part 1 is correct. Quench tank temperature would continue to rise if the valve were still open. Part 2 is plausible Quench tank temperature would eventually stabilize at saturation temperature for containment pressure once the QT diaphragm ruptured.

Technical Reference(s): Steam Tables (Attach if not previously provided) TG-OP-902-002 page 10 Rev. 19 (including version/revision number) WLP-OPS-PPE02 slide 58 Rev. 17 Proposed references to be provided to applicants during examination: Steam Tables Learning Objective: WLP-OPS-RCS00 obj. 2 (As available)

WLP-OPS-PPE02 obj. 3 Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 3 55.43 Comments: NRC Comment: Added Rx tripped to the stem and reversed the order of question 1 and 2 to prevent confusion between past and current conditions.

Revision 2 Facility: Waterford 3 Page 4 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000009 EK3.04 Importance Rating 4.1 K/A Statement 009 Small Break LOCA, EK3.04: Knowledge of the reasons for the following responses as they apply to the small break LOCA: Starting additional Charging Pumps Proposed Question: RO 3 Rev: 2 Given:

A SBLOCA has occurred RCS pressure is 1600 psia and lowering Pressurizer level is 15% and lowering Charging Pump AB Assignment switch is in the NORM position Two CEAs failed to insert into the core on the reactor trip The ATC informs the CRS that only Charging Pump A is running.

To meet the minimum required number of Charging Pumps running, the crew will start Charging Pump(s) ____(1)____ .

The crew started the additional charging pump(s) to ensure ______(2)_____.

(1) (2)

A. B only adequate RCS makeup is available B. B only shutdown margin requirements met C. B and AB shutdown margin requirements met D. B and AB adequate RCS makeup is available Revision 2 Facility: Waterford 3 Page 5 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: Since the Charging Pump AB Assignment switch is in Norm and a SIAS is initiated due to RCS pressure < 1684 psia, Charging Pumps A and B should be running and Charging Pump AB will be secured. OI-038-000 step 5.4.72 defines all available charging pumps with a SIAS as two running. With RCS pressure above HPSI shutoff head, charging pumps are required to maintain pressurizer level.

B. Incorrect. Part 1 is correct. Two CEAs stuck out requires emergency boration to meet shutdown margin. Only one Charging pump >40 gpm is required to meet Shutdown Margin.

C. Incorrect. If there was no SIAS, all three charging pumps would be required to be running due to a level deviation. Two CEAs stuck out requires emergency boration to meet shutdown margin. Only one Charging pump >40 gpm is required to meet Shutdown Margin.

D. Incorrect. If there was no SIAS, all three charging pumps would be required to be running due to a level deviation. Part 2 is correct.

Technical Reference(s): OI-038-000 step 5.4.47 Rev 13 (Attach if not previously provided) OP-902-002 page 69 Rev. 20 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE01 obj. 4 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam none Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 4 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comment: Free review question. Initial question did not meet the K/A. Changed part 1 such that an additional Charging pump is started. Changed part 2 to indicate the reason. NRC comment: Removed all available charging pumps from the stem.

Revision 2 Facility: Waterford 3 Page 6 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000011 EA2.03 Importance Rating 3.7 K/A Statement 011 Large Break LOCA, EA2.03: Ability to determine or interpret the following as they apply to a Large Break LOCA: Consequences of managing LOCA with loss of CCW.

Proposed Question: RO 4 Rev: 2 Given:

A large break LOCA occurred A SIAS, CIAS, MSIS and CSAS has occurred The crew has split CCW headers due to only one CCW pump available The crew has ___(1)___ train(s) of Essential Chillers available to manage the event.

The crew has ___(2)___ train(s) of Low Pressure Safety Injection available to manage the event.

(1) (2)

A. two two B. two one C. one one D. one two Revision 2 Facility: Waterford 3 Page 7 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Part 1 is correct. Only one train of LPSI is available because the C/S for one of the pumps is in OFF.

B. CORRECT: OP-902-009 directs the crew to remove the EDG, LPSI pump, HPSI Pump, and CS pump from service on the affected CCW train. The Essential Chiller on the isolated side is available because it can be supplied from its backup source (ACCW) which is still available. Only one train of LPSI is available because the C/S for one of the pumps is in OFF.

C. Incorrect: OP-902-009 directs the crew to remove the EDG, LPSI pump, HPSI Pump, and CS pump from service on the affected CCW train. The ACCW pump on the isolated side is still available to supply cooling water to the Essential Chiller. Part 2 is correct.

D. Incorrect. OP-902-009 directs the crew to remove the EDG, LPSI pump, HPSI Pump, and CS pump from service on the affected CCW train. The ACCW pump on the isolated side is still available to supply cooling water to the Essential Chiller. Only one train of LPSI is available because the C/S for one of the pumps is in OFF.

Technical Reference(s): OP-902-009 Appendix 35 Rev. 315 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE01 obj. 6 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 8, 10 55.43 Comments: NRC Comment: Using the Essential Chiller as a distractor for Part 1 is better than using ACCW (more plausible).

Revision 2 Facility: Waterford 3 Page 8 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000015/17 AK2.07 Importance Rating 2.9 K/A Statement 015/17 RCP Malfunctions, AK2.07: Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: RCP seals.

Proposed Question: RO 5 Rev: 2 The ATC notes the following indications on RCP 1A:

• Vapor Seal is 45 PSIG

• Upper Seal is 1180 PSIG

• Middle Seal is 1250 PSI

• RCS pressure is 2250 PSIA Which ONE of the following RCP 1A seals has failed or is degraded?

A. Vapor B. Upper C. Middle D. Lower Revision 2 Facility: Waterford 3 Page 9 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Normal pressure range is 25 to 45 PSIG. Pressure is high in the band due to a failed middle seal.

B. Incorrect. Normal pressure range is 585 to 915 PSIG. Upper seal pressure is outside of the band which is indicative of a failed middle seal. The upper seal is working properly.

C. CORRECT: The D/P between the middle seal and upper seal pressures are less than 100 psid. The D/P is outside of the range given in OP-901-130. These parameters are indicative of a middle seal failure.

D. Incorrect. Normal Pressure is 1237 to 1815 psig for middle seal pressure. Pressure is low in the band due to the failed middle seal.

Technical Reference(s): OP-901-130 section E1 note Rev. 11 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO10 obj. 3 (As available)

Question Source: Bank # RO4 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2009 RO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 2 10 CFR Part 55 Content: 55.41 3 55.43 Revision 2 Facility: Waterford 3 Page 10 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000022 AK1.03 Importance Rating 3.0 K/A Statement 022 Loss of Rx Coolant Makeup, AK1.03: Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Makeup: Relationship between charging flow and PZR level.

Proposed Question: RO 6 Rev: 2 Given:

Plant operating at 100% power Charging Pump B is running with Charging Pumps A and AB in standby Upon a trip of Charging Pump B, the first backup charging pump is designed to start at a pressurizer level of __(1)__ %. If uncorrected, letdown will isolate on __(2)__ heat exchanger outlet temperature.

(1) (2)

A. 51.7 Regenerative B. 51.7 Letdown C. 53.1 Letdown D. 53.1 Regenerative Revision 2 Facility: Waterford 3 Page 11 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect: The PLCS is designed such that the first Backup Charging Pump will start at a Pressurizer level deviation of 2.5%. The second Charging Pump will start at a level deviation of 3.9% which would equate to a level of 51.7% at 100% power. Part 2 is correct.

B. Incorrect. The PLCS is designed such that the first Backup Charging Pump will start at a Pressurizer level deviation of 2.5%. The second Charging Pump will start at a level deviation of 3.9% which would equate to a level of 51.7% at 100% power. A loss of Charging flow will raise Regenerative HX outlet temperature. If temperature reaches 470ºF, letdown will isolate.

The letdown HX is downstream of the Regenerative HX and is cooled by CCW.

C. Incorrect. Part 1 is correct. A loss of Charging flow will raise Regenerative HX outlet temperature. If temperature reaches 470ºF, letdown will isolate. The letdown HX is downstream of the Regenerative HX and is cooled by CCW.

D. CORRECT: The PLCS is designed such that the first Backup Charging Pump will start at a Pressurizer level deviation of 2.5%. The applicant must know that Pressurizer level at 100%

power is programmed at 55.6%. Charging flow is the cooling medium for the Regenerative HX. Therefore, a loss of Charging flow will raise Regenerative HX outlet temperature. If temperature reaches 470ºF, letdown will isolate.

Technical Reference(s): OP-901-112 pages 5 and 8. Revision 6 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CVC00 objs. 3, 6 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

NRC comment: Changed part 2 of the stem to read, If uncorrected, letdown will isolate on __(2)__ heat exchanger outlet temperature. Changed LOD from 4 to 3.

Revision 2 Facility: Waterford 3 Page 12 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000025 2.1.32 Importance Rating 3.8 K/A Statement 025 Loss of RHR System, Ability to explain system limits and precautions.

Proposed Question: RO7 Rev: 2 Given:

• The crew has entered OP-901-131, Shutdown Cooling Malfunction, due to System Leakage

• The crew has aligned LPSI Pumps for injection mode to maintain RCS level To prevent vortexing in the Safety Injection Sump following an RAS, OP-901-131, Shutdown Cooling Malfunction, directs the crew to ____(1)____.

The minimum injection flow to prevent a LPSI pump from overheating is _____(2)_____

gpm.

(1) (2)

A. verify only one LPSI 100 pump is running B. verify only one LPSI 25 pump is running C. limit SDC flow to 2000 100 gpm per LPSI train D. limit SDC flow to 2000 25 gpm per LPSI train Revision 2 Facility: Waterford 3 Page 13 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. To prevent vortexing in the SI sump, flow is reduced to 2000 gpm, securing one LPSI pump is plausible because this too will reduce the combined flow from the SI sump. Part 2 is correct.

B. Incorrect. To prevent vortexing in the SI sump, flow is reduced to 2000 gpm, securing one LPSI pump is plausible because this too will reduce the combined flow from the SI sump. The limit on injection flow to prevent overheating of a LPSI pump is 100 gpm, 25 gpm is the limit for a HPSI pump.

C. CORRECT: Following an RAS while in injection mode, OP-901-131 Shutdown Cooling Malfunction, directs the crew to limit SDC flow to a maximum of 2000 gpm per LPSI train to prevent vortexing in the SI sump. The limit on injection flow to prevent overheating of a LPSI pump is 100 gpm.

D. Incorrect. Part 1 is correct. The limit on injection flow to prevent overheating of a LPSI pump is 100 gpm, 25 gpm is the limit for a HPSI pump.

Technical Reference(s): OP-901-131 section E1 step 14, Rev. 304 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-REQ21 obj. 6 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 10 55.43 Comments: Changed the K/A and wrote a new question Revision 2 Facility: Waterford 3 Page 14 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000027 2.2.44 Importance Rating 4.2 K/A Statement 027 Pressurizer Pressure Control System Malfunction, 2.2.44: Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

Proposed Question: RO 8 Rev: 2 Given:

Plant is at 100% power RC-301A, Pressurizer Spray Valve indicates open Pressurizer Pressure is 2230 psia and dropping In accordance with OP-901-120, Pressurizer Pressure Control Malfunction, the CRS will direct the ATC to place the ____(1)____ controller in manual and close the spray valves.

The ATC will then place the spray valve selector switch to the _____(2)_____ position.

(1) (2)

A. Pressurizer Pressure 1A B. Pressurizer Pressure 1B C. Pressurizer Spray 1B D. Pressurizer Spray 1A Revision 2 Facility: Waterford 3 Page 15 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. OP-901-120 directs the crew to take the Pressurizer Spray controller to manual and adjust output to 0%. The procedure directs the crew to take manual control of the Pressurizer pressure controller for other PPC malfunctions, but not for a failed open spray valve. The spray valve selector switch will de-energize the solenoid for the position it is not selected to.

B. Incorrect. OP-901-120 directs the crew to take the Pressurizer Spray controller to manual and adjust output to 0%. The procedure directs the crew to take manual control of the Pressurizer pressure controller for other PPC malfunctions, but not for a failed open spray valve. Part 2 is correct.

C. CORRECT: The applicant must determine that the spray valve should not be open with Pressurizer pressure at 2230 psia. OP-901-120 directs the crew to take the Pressurizer Spray controller to manual and adjust output to 0%. OP-901-120 will then direct the crew to take the spray valve selector switch to the 1B position which will de-energize the 1A spray valve.

D. Incorrect. Part 1 is correct. The spray valve selector switch will de-energize the solenoid for the position it is not selected to.

Technical Reference(s): OP-901-120 section E0 and E3 Rev. 302 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO10 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 2 10 CFR Part 55 Content: 55.41 7,10 55.43 Comments: NRC Comment: Changed to a LOD-2 Revision 2 Facility: Waterford 3 Page 16 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000029 EA1.12 Importance Rating 4.1 K/A Statement 029 ATWS, EA1.12: Ability to operate and monitor the following as they apply to a ATWS: M/G set power supply and reactor trip breakers.

Proposed Question: RO 9 Rev: 2 Given:

Plant is at 100% power An event occurs and automatic reactor trips fail Manual Reactor trip at CP-2 fails Manual Diverse Reactor Trip fails The crew will attempt to de-energize the Motor Generator Sets by opening the

___(1)___ feeder breakers. If this method of tripping the reactor is unsuccessful, the ATC will direct an NAO to the ___(1)___ safety switchgear room to locally open all Reactor Trip breakers.

(1) (2)

A. 31A and 31B A B. 31A and 31B B C. 32A and 32B A D. 32A and 32B B Revision 2 Facility: Waterford 3 Page 17 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. The 31A(B) bus feeder breakers have control switches next to the 32A(B) feeder breakers on CP-1, but they do not supply power to the MG sets. The A Switchgear is located on the same elevation as the B switchgear but is not where the reactor trip switchgear breakers are located.

B. Incorrect:. The 31A(B) bus feeder breakers have control switches next to the 32A(B) feeder breakers on CP-1, but they do not supply power to the MG sets. Part 2 is correct.

C. Incorrect. Part 1 is correct. The A Switchgear is located on the same elevation as the B switchgear but is not where the reactor trip switchgear breakers are located.

D. CORRECT: If all attempts to trip the reactor at CP-2 fail, the Standard Post Trip actions direct the crew to de-energize the MG sets by opening the 32A and 32B feeder breakers. If this fails, the crew will direct an NAO to the B switchgear room to operate and monitor all Reactor Trip breakers open.

Technical Reference(s): SD-480 Figure 5 Rev. 5 (Attach if not previously provided) OP-902-000 step 1 Rev 16 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CED00 objs. 3 and 4 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 6,10 55.43 Revision 2 Facility: Waterford 3 Page 18 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000038 EK3.02 Importance Rating 4.4 K/A Statement 038 Steam Gen. Tube Rupture, EK3.02: Knowledge of the reasons for the following responses as they apply to the SGTR: Prevention of secondary PORV cycling.

Proposed Question: RO 10 Rev: 2 Given:

A Steam Generator Tube Rupture in Steam Generator #1 and Loss of Offsite Power has occurred The crew has entered OP-902-007, Steam Generator Tube Rupture and has isolated Steam Generator #1 The maximum allowed Narrow Range level for the isolated steam generator is

____(1)____. Atmospheric Dump Valve (ADV) #1 can be used only as a last resort to maintain this level because the discharge flow path for the ADVs are not _____(2)_____.

(1) (2)

A. 70% isolable B. 85% monitored C. 70% monitored D. 85% isolable Revision 2 Facility: Waterford 3 Page 19 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. The maximum allowed level for the isolated SG is 85% NR, 70% NR is plausible because this is the maximum allowed NR level for the un-isolated SG. The ADVs are isolable.

B. CORRECT: The maximum allowed level for the isolated SG is 85% NR. Per the contingency action for step 33 of OP-902-007, the ADV should be used as a last resort to maintain this limit because the ADV is an unmonitored release.

C. Incorrect. The maximum allowed level for the isolated SG is 85% NR, 70% NR is plausible because this is the maximum allowed NR level for the un-isolated SG. Part 2 is correct.

D. Incorrect. Part 1 is correct. The ADVs are isolable.

Technical Reference(s): OP-902-007 step 33 Rev. 17 (Attach if not previously provided) TG-OP-902-007 page 33 Rev. 308 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE07 obj. 8 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 10,12 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 20 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000040 CE/E05 EK1.2 Importance Rating 3.2 K/A Statement CE/E05 Steam Line Rupture, EK1.2: Knowledge of the operational implications of the following concepts as they apply to the (Excess Steam Demand): Normal, abnormal and emergency operating procedures associated with (Excess Steam Demand).

Proposed Question: RO 11 Rev: 2 OP-902-004, Excess Steam Demand Recovery Procedure, requires verifying no more than two Reactor Coolant Pumps running if Tcold is less than ___(1)___ °F to

__________(2)___________.

(1) (2)

A. 380 prevent generating excessive core uplift forces B. 380 aid in stabilizing Reactor Coolant System temperature after Steam Generator dryout C. 202 prevent generating excessive core uplift forces D. 202 aid in stabilizing Reactor Coolant System temperature after Steam Generator dryout Revision 2 Facility: Waterford 3 Page 21 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: Per OP-902-004, Tc < 380 requires 1 RCP in each loop to be secured.

TG-OP-902-004 states that the PT limit curve specifies that one RCP should be tripped although OP-902-004 directs the crew to secure one RCP in each loop for even flow between the loops. The reason for this step identified in the Tech Guide is to prevent a core uplift problem.

B. Incorrect. The temperature is correct. The basis is incorrect per TG-OP-902-004; however it is plausible that elimination of heat addition to the RCS would aid in stabilizing RCS temperature since Waterfords ADVs are not sufficient size to prevent needing to have a minimum EFW flow to aid in RCS temperature stabilization.

C. Incorrect. The temperature is incorrect. The temperature of 202°F is the minimum temperature for three pump configuration per OP-001-002. The basis is correct per TG-OP-902-004.

D. Incorrect. The temperature is incorrect. The temperature of 202°F is the minimum temperature for three pump configuration per OP-001-002. The basis is incorrect per OP-902-004; however it is plausible that elimination of heat addition to the RCS would aid in stabilizing RCS temperature since Waterfords ADVs are not sufficient size to prevent needing to have a minimum EFW flow to aid in RCS temperature stabilization Technical Reference(s): OP-902-004 step 10 Rev. 16 (Attach if not previously provided) TG-OP-902-004 Rev. 307 (including version/revision number) OP-001-002 limitation 3.1.6 Rev. 22 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE04 obj. 4 (As available)

Question Source: Bank # RO11 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2011 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Revision 2 Facility: Waterford 3 Page 22 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000054 CE/E06 EK1.1 Importance Rating 3.2 K/A Statement CE/E06 Loss of Main Feedwater, EK1.1: Knowledge of the operational implications of the following concepts as they apply to the (Loss of Feedwater):

Components, capacity, and function of emergency systems.

Proposed Question: RO 12 Rev: 2 Given:

The reactor is tripped due to an Inadvertent Main Steam Isolation Signal (MSIS)

Emergency Feedwater (EFW) Pump B is danger tagged out Both Steam Generators are 43% NR level and dropping A subsequent loss of ____(1)____ would require that all running Reactor Coolant Pumps be tripped. Per the Tech Guide for OP-902-006, Loss of Feedwater Recovery Procedure, this action is required to ____(2)____.

(1) (2)

A. EFW Pump A prevent lifting Pressurizer safety valves B. EFW Pump AB reduce the heat input into the RCS C. EFW Pump AB prevent lifting Pressurizer safety valves D. EFW Pump A reduce the heat input into the RCS Revision 2 Facility: Waterford 3 Page 23 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. EFW Pump AB supplies 100% capacity to the Steam Generators, therefore, the crew will not be required to enter OP-902-006 if EFW Pump AB is the only EFW Pump running. The applicant must determine that OP-902-006 entry is required. Part 2 is plausible because RCS temperature/pressure will rise in an inadvertent MSIS and it can be assumed that securing RCPs will reduce the pressure rise and prevent lifting Pressurizer safeties. Per the Tech guide, this is not the reason RCPs are secured during a loss of Main Feedwater event.

B. CORRECT: EFW motor driven pumps (EFW Pumps A and B) are 50% capacity. Therefore, if the only feedwater available is ONE motor driven EFW pump, all RCPs must be secured to reduce the heat input into the RCS. The applicant must determine that OP-902-006 entry is required The inadvertent MSIS in the stem eliminated FW sources from MFW pumps and the AFW pump.

C. Incorrect. Part 1 is correct. Part 2 is plausible because RCS temperature/pressure will rise in an inadvertent MSIS and it can be assumed that securing RCPs will reduce the pressure rise and prevent lifting Pressurizer safeties. Per the Tech guide, this is not the reason RCPs are secured during a loss of Main Feedwater event.

D. Incorrect. EFW Pump AB supplies 100% capacity to the Steam Generators, therefore, the crew will not be required to enter OP-902-006 if EFW Pump AB is the only EFW Pump running. The applicant must determine that OP-902-006 entry is required. Part 2 is correct.

Technical Reference(s): TG-OP-902-006 step 6 Rev. 18 (Attach if not previously provided) OP-902-006 step 6 Rev. 18 SD-EFW page 6, Rev. 12, OP-902-009 Att. 1 Rev.

(including version/revision number) 315 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE06 obj. 4 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 10 55.43 Comments: NRC comment: Added Per the Tech Guide for OP-902-006 Revision 2 Facility: Waterford 3 Page 24 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000055 EA2.03 Importance Rating 3.9 K/A Statement 055 Station Blackout, EA2.03: Ability to determine or interpret the following as they apply to a Station Blackout: Actions necessary to restore power.

Proposed Question: RO 13 Rev: 2 Given:

A Station Blackout has occurred Offsite power has been restored to buses 3A and 3B A Probable Maximum Precipitation (PMP) event just commenced To restore a DCT Sump Pump, power must be restored to the non-safety section of Motor Control Center _____(1)_____.

OP-902-009 Appendix 20, Operation of DCT Sump Pumps, directs the crew to align at least one Dry Cooling Tower Motor Driven Sump Pump within ___(2)___ of the PMP event.

(1) (2)

A. 312A or B 30 minutes B. 314A or B 30 minutes C. 312A or B 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> D. 314A or B 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Revision 2 Facility: Waterford 3 Page 25 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Wrong MCCs, however, the 312 MCCs also have safety to non-safety tie breakers.

B. CORRECT: Per OP-902-009, requires restoration of a DCT Motor Driven Sump Pump within 30 minutes from the start of a PMP event. These pumps are powered from MCCs 314A and 314B.

C. Incorrect. Wrong MCCs, however, the 312 MCCs also have safety to non-safety tie breakers Wrong time frame. Three hours correlates to the time required to have a diesel driven sump pump aligned for operation from the DCT sumps.

D. Incorrect. Correct MCCs. Three hours correlates to the time required to have a diesel driven sump pump aligned for operation from the DCT sumps.

Technical Reference(s): OP-902-005 step 5 Rev. 20 (Attach if not previously provided) OP-902-009 App. 20 Rev. 315 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE05 obj. 7 (As available)

Question Source: Bank # RO13 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2011 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 26 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000056 2.4.18 Importance Rating 3.3 K/A Statement 056 Loss of Off-site Power, 2.4.18: Knowledge of the specific bases for the EOPs.

Proposed Question: RO 14 Rev: 2 Given:

Loss of offsite power has occurred Crew has entered OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery The sequencers for both Emergency Diesel Generators are timed out The CRS has directed the BOP to Verify Containment Cooling The BOP will ____(1)____ . Per the Tech Guide for OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery, this action is required to ____ (2) .

(1) (2)

A. secure one Containment Fan ensure emergency diesel Cooler generator fuel oil consumption is minimized B. align the Containment Fan ensure emergency diesel Coolers to slow speed generator fuel oil consumption is minimized C. align the Containment Fan prevent damage to Containment Coolers to slow speed Cooling ductwork D. secure one Containment Fan prevent damage to Containment Cooler Cooling ductwork Revision 2 Facility: Waterford 3 Page 27 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Part 1 is correct. Securing one CFC will help EDG fuel oil consumption, but with no SIAS, fuel oil consumption is not a concern.

B. Incorrect. The only time four CFCs should be running together in slow speed is following a SIAS or surveillance testing. Neither of these events/evolutions are in progress, so going to slow speed is not required. Aligning the CFCs to slow speed will help EDG fuel oil consumption, but with no SIAS, fuel oil consumption is not a concern.

C. Incorrect. The only time four CFCs should be running together in slow speed is following a SIAS or surveillance testing. Neither of these events/evolutions or in progress, so going to slow speed is not required. Part 2 is correct.

D. CORRECT: Following a LOOP without a SIAS, all CFCs will start in Fast speed. If all four CFCs start in Fast there is a concern for damaging duct work.

Technical Reference(s): OP-902-003 step 13 Rev. 10 (Attach if not previously provided) TG-OP-902-003 step 13 Rev. 306 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE05 obj. 6 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8,10 55.43 Comment: NRC comment: Added Per the Tech Guide for OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery Revision 2 Facility: Waterford 3 Page 28 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000058 AK3.01 Importance Rating 3.4 K/A Statement 058 Loss of DC Power, AK3.01: Knowledge of the reasons for the following responses as they apply to the Loss of DC Power: Use of dc control power by D/Gs.

Proposed Question: RO 15 Rev: 2 Given:

A loss of the 125 Volt DC bus A-DC has occurred The BOP will direct the NAO to secure the Emergency Diesel Generator (EDG) A Fuel Oil Transfer pump by ____(1)____. This action is required to ____(2)____.

(1) (2)

A. taking the local control prevent overflowing the Fuel Oil switch to off Day Tank B. taking the local control prevent pump overheating switch to off C. opening the pump supply prevent pump overheating breaker D. opening the pump supply prevent overflowing the Fuel Oil breaker Day Tank Revision 2 Facility: Waterford 3 Page 29 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect: On a loss of DC, the Fuel Oil Day Tank level switch fails low, causing the fuel oil transfer pump to run continuously. The local switch is an auto/on switch, therefore the pump cannot be secured via the c/s. Part 2 is correct.

B. Incorrect: On a loss of DC, the Fuel Oil Day Tank level switch fails low, causing the fuel oil transfer pump to run continuously. The local switch is an auto/on switch, therefore the pump cannot be secured via the c/s. The fuel oil transfer pump requires 10 gpm recirc flow to prevent overheating. The discharge flowpath is not isolated during normal or abnormal operations, therefore overheating is not a reason to secure the pump in this instance.

C. Incorrect. Part 1 is correct. The fuel oil transfer pump requires 10 gpm recirc flow to prevent overheating. The discharge flowpath is not isolated during normal or abnormal operations, therefore overheating is not a reason to secure the pump in this instance D. CORRECT: The loss of DC off-normal, OP-901-313, directs the crew to open the EDG A Fuel Oil Transfer Pump breaker, EGF-312A-3F on a loss of A DC. This same step states that this action is performed to prevent overflowing the Fuel Oil Day Tank.

Technical Reference(s): OP-901-313 page 19 Rev. 305 (Attach if not previously provided) SD-EDG page 70 Rev. 24 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO30 obj. 3 (As available)

Question Source: Bank # RO52 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2007 RO Makeup Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8 55.43 Revision 2 Facility: Waterford 3 Page 30 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000026 AA2.01 Importance Rating 2.9 K/A Statement 026 Loss of Component Cooling Water, AA2.01: Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: Location of a leak in the CCW System.

Proposed Question: RO 16 Rev: 2 Given:

A leak is occurring in the Component Cooling Water System Initially CCW Surge Tank Level A and B lowered to 0%

CCW Surge Tank level A remains at 0%

CCW Surge Tank level B recovered to ~ 55% and stabilized Which of the following is a potential location of the leak?

A. Supply pipe to Waste Gas Compressor A B. Supply pipe to Shutdown Cooling HX A C. Return pipe from Spent Fuel Pool HX A D. Return pipe from CEDM Fan Cooler A Revision 2 Facility: Waterford 3 Page 31 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. The Waste Gas compressor is an NNS Loop load. This pipe would have been automatically isolated by the AB loop isolation valves and level in both sides of the CCW surge tank would have recovered.

B. CORRECT: Shutdown HX A is a Safety Loop A load. Safety Loops A and B would be split out such that the leak no longer affects Loop B until CCW Surge Tank Level B exceeds 55% which is the top of the baffle separating A and B sides of the CCW surge tank.

C. Incorrect. SFP HX A is an AB Loop load. This pipe would have been automatically isolated by the AB Loop isolation valves and level in both sides of the CCW surge tank would have recovered.

D. Incorrect. CEDM Fan Cooler A is an AB Loop load. This pipe would have been automatically isolated by the AB Loop isolation valves and level in both sides of the CCW surge tank would have recovered Technical Reference(s): OP-901-510 page 6 Rev. 303 (Attach if not previously provided) SD-CC Fig. 2 Rev. 21 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO50 obj. 3 (As available)

Question Source: Bank # RO 45 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2010 RO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 7 55.43 Comments: Free review question. Randomly selected a new K/A. NRC comment.

Changed to a level difficulty of 3.

Revision 2 Facility: Waterford 3 Page 32 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000065 AA1.01 Importance Rating 2.7 K/A Statement 065 Loss of Instrument Air, AA1.01: Ability to operate and / or monitor the following as they apply to the Loss of Instrument Air: Remote manual loaders.

Proposed Question: RO 17 Rev: 2 Given:

Plant is at 100% power An instrument air leak has occurred Crew has entered OP-901-511, Instrument Air Malfunction The BOP will direct the NAO to ____(1)____ the set point for SA-125, SA Backup Supply for IA Press Cntl Valve, to force it open. When instrument air pressure lowers to 95 psig, _____(2)_____ .

(1) (2)

A. raise IA-123, Instrument Air Dryers Bypass solenoid, opens B. raise a plant shutdown in accordance with OP-010-005, Plant Shutdown, is required C. lower IA-123, Instrument Air Dryers Bypass solenoid, opens D. lower a plant shutdown in accordance with OP-010-005, Plant Shutdown, is required Revision 2 Facility: Waterford 3 Page 33 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: The set point on SA-125 must be raised to force the valve open. The set point is the pressure at which the valve will start to open. Usually set at 105 psig.

Raising the set point will make the valve open sooner. IA-123 is designed to open and bypass the IA dryers at 95 psig.

B. Incorrect. Part 1 is correct. The crew will commence a plant shutdown in accordance with OP-010-005, Plant Shutdown when Instrument Air pressure reaches 80 psig.

C. Incorrect. The set point on SA-125 must be raised to force the valve open. The set point is the pressure at which the valve will start to open. Usually set at 105 psig.

Raising the set point will make the valve open sooner. Part 2 is correct.

D. Incorrect. The set point on SA-125 must be raised to force the valve open. The set point is the pressure at which the valve will start to open. Usually set at 105 psig.

Raising the set point will make the valve open sooner. The crew will commence a plant shutdown in accordance with OP-010-005, Plant Shutdown when Instrument Air pressure reaches 80 psig.

Technical Reference(s): OP-901-511 page 6 and 7 Rev. 15 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO50 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 10 55.43 Comments: NRC comment: Deleted the crew will. Changed distractor B and D by adding is required.

Revision 2 Facility: Waterford 3 Page 34 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000077 AK2.07 Importance Rating 3.6 K/A Statement 077 Generator Voltage and Electric Grid Disturbances, AK2.07: Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and the following: Turbine/Generator Control.

Proposed Question: RO 18 Rev: 2 Given:

Reactor power is 100%

A large load connected to the grid is lost causing a grid disturbance MVAR load changed from 60 MVAR out to 100 MVAR in The grid disturbance caused grid voltage to __(1)__.

To restore MVAR load to 60 MVAR out, the crew will adjust the Main Generator voltage adjust regulator control switch to ____(2)____.

(1) (2)

A. rise raise B. rise lower C. lower raise D. lower lower Revision 2 Facility: Waterford 3 Page 35 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: Losing a large load on the grid will cause grid voltage to rise because Reactive Power (VAR) decreases. To change MVAR from leading to lagging the voltage regulator C/S must be taken to raise.

B. Incorrect. Part 1 is correct. To change MVAR from leading to lagging the voltage regulator C/S must be taken to raise.

C. Incorrect. Losing a large load on the grid will cause grid voltage to rise. Part 2 is correct.

D. Incorrect. Losing a large load on the grid will cause grid voltage to rise. To change MVAR from leading to lagging the voltage regulator C/S must be taken to raise.

Technical Reference(s): WLP-OPS-TYC05 slide 247, 257, 258, 275 Rev. 4 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-TYC05 obj. 20 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 4 10 CFR Part 55 Content: 55.41 5, 10 55.43 Revision 2 Facility: Waterford 3 Page 36 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # CE/A16 AK1.1 Importance Rating 3.2 K/A Statement CE/A16 Excess RCS Leakage, AK1.1: Knowledge of the operational implications of the following concepts as they apply to the (Excess RCS Leakage):

Components, capacity, and function of emergency systems.

Proposed Question: RO 19 Rev: 2 Given:

Plant is at 100% power AB Charging pump is out of service with Charging Pumps A and B running An RCS leak is in progress and the crew is performing the required actions of OP-901-111, RCS Leak Subsequently, the STA reports that RCS leakage has been verified to be 90 gpm.

Which of the following is the appropriate action(s) to be performed?

A. Remain in OP-901-111, Reactor Coolant System Leak, and attempt to locate the leak.

B. Commence a normal shutdown in accordance with OP-010-005, Plant Shutdown.

C. Commence a rapid plant shutdown in accordance with OP-901-212, Rapid Plant Power Reduction.

D. Initiate a manual reactor trip, SIAS/CIAS, and go to OP-902-000, Standard Post Trip Actions.

Revision 2 Facility: Waterford 3 Page 37 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. RCS leakage exceeds the capacity of two charging pumps. This is an option only if pressurizer level can be maintained (leak within the capacity of two charging pumps.

B. Incorrect: OP-901-111 step 17 directs a normal shutdown, if required, in accordance with OP-010-005. In this case, RCS leakage exceeds the capacity of the Charging Pumps, therefore a Reactor trip is required.

C. Incorrect. RCS leakage exceeds the capacity of two charging pumps. This is a valid shutdown option in other conditions; however, OP-901-111 specifically ignores this option based on the possible inability to control pressurizer level on the shutdown.

D. CORRECT: The Charging Pump capacity is 44 gpm per pump. With two Charging Pumps running, there is 88 gpm capacity. Based on the total inventory loss from the RCS exceeding Charging pump capacity, Pressurizer level cannot be maintained.

OP-901-111 requires a reactor trip and a manual initiation of SIAS/CIAS be performed.

Technical Reference(s): OP-901-111 page 7 Rev. 303 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO10 obj. 3 (As available)

Question Source: Bank # RO65 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2010 RO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 2 10 CFR Part 55 Content: 55.41 10 55.43 Comments: NRC Comment: Changed to a level difficulty of 2.

Revision 2 Facility: Waterford 3 Page 38 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 000024 AK2.01 Importance Rating 2.7 K/A Statement 024 Emergency Boration, AK2.01: Knowledge of the interrelations between Emergency Boration and the following: Valves.

Proposed Question: RO 20 Rev: 2 Given:

Plant is in MODE 3 Emergency Diesel Generator A is Danger Tagged out Plant has experienced a steam line leak resulting in an uncontrolled cooldown Loss of power to the 3A safety bus has occurred The AB safety busses are powered from the A Train CRS directs ATC operator to commence emergency boration Which of the following will be the emergency boration flow path aligned by the ATC?

A. BAM Tanks via BAM-143, Direct Boration Valve B. BAM Tanks via BAM-113 A and B, Boric Acid Gravity Feed Valves C. Boric Acid Makeup (BAM) Tank B via BAM Pump B and BAM-133, Emergency Boration Valve D. Refueling Water Storage Pool (RWSP) via CVC-507, RWSP to Charging Pump Suction Isolation Revision 2 Facility: Waterford 3 Page 39 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. BAM-143 is the direct boration valve from the BAMTs. BAM-143 is not an optional emergency boration flowpath per OP-901-103, Emergency Boration..

B. CORRECT: The loss of the 3A bus resulted in a loss of the BAM pumps. Emergency boration must be aligned from the BAMTs via BAM-113A and B (both gravity feed valves are B train powered).

C. Incorrect. The loss of the 3A bus resulted in a loss of both Boric Acid Makeup (BAM) pumps (both BAM pumps are A train powered). Emergency boration must be aligned from the BAMTs via BAM-113A and B (both gravity feed valves are B train powered).

D. Incorrect. CVC-507 is AB powered and does not have power in the given conditions since the AB bus is powered from the de-energized train.

Technical Reference(s): OP-901-103, Emergency Boration, Rev. 3 OP-002-005, Chemical And Volume Control (Attach if not previously provided) System, Rev. 56 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CVC00 obj. 3,5 (As available)

Question Source: Bank # RO20 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2012 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 6,10 55.43 Comments: NRC Comment: Added the AB bus is aligned to the A train to the stem.

This would mean that CVC-507 has no power and cannot be used for Emergency Boration. Changed to a LOD-3 from a LOD-4.

Revision 2 Facility: Waterford 3 Page 40 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 000028 AA2.12 Importance Rating 3.1 K/A Statement 028 Pressurizer Level Malfunction, AA2.12: Ability to determine and interpret the following as they apply to the Pressurizer Level Control Malfunctions: Cause for PZR level deviation alarm: controller malfunction or other instrumentation malfunction.

Proposed Question: RO 21 Rev: 2 Given:

Plant is at 100% power The Pressurizer Level Control Channel Select Switch is in the Channel Y position The ATC reports that the Pressurizer Level Hi/Lo and Pressurizer Level Hi/Hi annunciators are in alarm One Charging Pump is running Pressurizer level is steady This event could be caused by which of the following failing high?

A. Reactor Regulating System RCS temperature Loop 1 hot leg indicator B. Pressurizer Level Control Channel X C. Pressurizer Level Control Channel Y D. Reactor Regulating System RCS temperature Loop 2 hot leg indicator Revision 2 Facility: Waterford 3 Page 41 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. At 100% power, the pressurizer programmed level setpoint cannot go greater than 55.6%. The hot leg indicator is an input to the level setpoint but since the cap for pressurizer level is 55.6%, the setpoint is not affected.

B. CORRECT: The annunciators given in the stem will still annunciate on the non-selected channel failing high because the annunciator inputs are located upstream of the channel select switch. Since channel X is the non-selected channel, the inputs to Charging and Letdown are not affected.

C. Incorrect. Pressurizer Level Channel Y failing high would bring in the annunciators located in the stem but would also affect Charging and Letdown. Charging pumps running would remain at one running but letdown flow would go to maximum. The stem indicated normal letdown flow and steady.

D. Incorrect. This is a different indicator than distractor A but has the same affect. At 100% power, the pressurizer programmed level setpoint cannot go greater than 55.6%. The hot leg indicator is an input to the level setpoint but since the cap for pressurizer level is 55.6%, the setpoint is not affected.

Technical Reference(s): SD-PLC page 25 Rev. 10 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO10 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 7, 10 55.43 Comments: NRC Comment: Removed Letdown flow is 40 gpm and steady from the stem and replaced it with Pressurizer level is steady. Replaced distractor D with a hot leg indicator.

Revision 2 Facility: Waterford 3 Page 42 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 051 AK3.01 Importance Rating 2.8 K/A Statement 051 Loss of Condenser Vacuum, AK3.01: Knowledge of the reasons for the following responses as they apply to the Loss of Condenser Vacuum and the following: Loss of steam dump capability upon loss of condenser vacuum.

Proposed Question: RO 22 Rev: 2 Given:

A Loss of offsite power has occurred and the crew is performing actions of OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery Condenser Vacuum has lowered to less than 14 INHG The Steam Bypass Control Valves are designed to close at a Condenser vacuum of

__(1)__ INHG.

The BOP will close the Main Steam Isolation Valves to ______(2)______.

(1) (2)

A. 6.4 prevent excessive cooldown B. 3.4 prevent excessive cooldown C. 3.4 ensure the Main Condenser is protected from over-pressurization D. 6.4 ensure the Main Condenser is protected from over-pressurization Revision 2 Facility: Waterford 3 Page 43 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Part 2 is plausible but not the reason we close the MSIVs. Closing the MSIVs is located under the Protect the Main Condenser step. The MSR TCVs were closed manually during SPTAs. Closing the MSR TCVs prevents excessive cooldown. The SBCVs are designed to auto close at 3.4 INHG. The reset value that the SBCVs will come back open is a Main Condenser Vacuum of 6.4 INHG.

B. Incorrect. Part 1 is correct. Part 2 is plausible but not the reason we close the MSIVs. Closing the MSIVs is located under the Protect the Main Condenser step. The MSR TCVs were closed manually during SPTAs. Closing the MSR TCVs prevents excessive cooldown.

C. CORRECT: The Main Steam Isolation Valves (MSIVs) are closed to isolate steam going through the Steam Bypass Control Valves (SBCVs) to the main condenser. This action is performed in Step 9 of OP-902-003, (Protect the Main Condenser) and the tech guide for this step states that the reason is to protect the Main Condenser from over-pressurization. The SBCVs are designed to auto close at 3.4 INHG.

D. Incorrect. The SBCVs are designed to auto close at 3.4 INHG. The reset value that the SBCVs will come back open is a Main Condenser Vacuum of 6.4 INHG. Part 2 is correct.

Technical Reference(s): OP-902-003 step 9 Rev. 10 (Attach if not previously provided) TG-OP-902-003 step 9 Rev. 306 (including version/revision number) OP-500-005 Att. 4.63 Rev. 14 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE05 obj. 7 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 10 55.43 Comments: NRC comment: Changed the order of Part 1 and Part of the stem questions so the question will flow better. Changed distractors A and B in part 2 to a more plausible action prevent excessive cooldown.

Revision 2 Facility: Waterford 3 Page 44 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 000037 AK1.02 Importance Rating 3.5 K/A Statement 037 Steam Generator Tube Leak, AK1.02: Knowledge of the operational implications of the following concepts as they apply to Steam Generator Tube Leak: Leak rate vs. pressure drop.

Proposed Question: RO 23 Rev: 2 With a Steam Generator Tube leak in progress it is ultimately desired to depressurize the RCS to within ___(1)___ psid of the ruptured Steam Generator to ___(2)___ and minimize the potential for Steam Generator overfill.

(1) (2) minimize the potential release to the A. 50 environment 50 prevent a loss of subcooled margin B.

minimize the potential release to the C. 100 environment prevent a loss of subcooled margin D. 100 Revision 2 Facility: Waterford 3 Page 45 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: Per step 21.5 of OP-901-202, 50 psid is the correct pressure differential. This minimizes pri-to-sec leakage which minimizes release magnitude and helps to prevent S/G overfill. The basis for 50 psid is located in TG-OP-902-007. The first bullet of this same step (maintain pressure within the PT curves) is the action required to maintain subcool margin.

B. Incorrect. Part 1 is correct. The bullet within step 21.5 provides instructions for maintaining RCS pressure within the P/T curve limits prevents loss of subcooled margin and allows continued operation of RCPs.

C. Incorrect. Per step 21.5 of OP-901-202, 50 psid is the correct pressure differential. Part 2 is correct.

D. Incorrect. Per step 21.5 of OP-901-201, 50 psid is the correct pressure differential. The substep within step 12 that provides instructions for maintaining RCS pressure within the P/T curve limits prevents loss of subcooled margin and allows continued operation of RCPs.

Technical Reference(s): OP-901-202 page 18 Rev. 15 (Attach if not previously provided) TG-OP-902-007 page 33 Rev. 308 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO2 obj. 3 (As available)

Question Source: Bank # RO10 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014 NRC RO Exam Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

Free review question. Developed a new question with the same K/A.

Revision 2 Facility: Waterford 3 Page 46 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 000060 2.4.31 Importance Rating 4.2 K/A Statement 060 Accidental Gaseous Radwaste Rel., 2.4.31: Knowledge of annunciator alarms, indications, or response procedures.

Proposed Question: RO 24 Rev: 2 Given:

Gas Decay Tank(s) discharge is in progress in accordance with OP-007-003, Gaseous Waste Management The RM-11 alarms and the associated annunciator is received The validity of this annunciator is verified by checking Waste Gas Flow and Rad Recorder (GWMIFRR0648) located on __(1)__ .

High radiation on __(2)__ Radiation Monitor will cause the Gas Decay Tank discharge to automatically isolate.

(1) (2)

A. LCP-42 either Plant Stack Vent B. CP-4 either Plant Stack Vent C. LCP-42 the Gaseous Waste Management D. CP-4 the Gaseous Waste Management Revision 2 Facility: Waterford 3 Page 47 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. LCP-42 is the location for the Waste Gas Decay Tanks to Plant Vent Flow Indicator as mentioned in the ARP. This is not the indicator the off-normal directs use of to verify the validity of the annunciator. On high radiation during a GDT release, the Gaseous Waste Management Rad Monitor will automatically close GWM-309. The Plant Stack Vent Rad monitor is plausible because it is listed as one of the indications in OP-901-413.

B. Incorrect. Part 1 is correct. On high radiation during a GDT release, the Gaseous Waste Management Rad Monitor will automatically close GWM-309. The Plant Stack Vent Rad monitor is plausible because it is listed as one of the indications in OP-901-413.

C. Incorrect. LCP-42 is the location for the Waste Gas Decay Tanks to Plant Vent Flow Indicator as mentioned in the ARP. This is not the indicator the off-normal directs use of to verify the validity of the annunciator. Part 2 is correct.

D. CORRECT: From the annunciator response and off-normal procedure, the validity of this annunciator is verified by checking Waste Gas Flow and Rad Recorder (GWMIFRR0648).

This recorder is located on CP-4. On high radiation during a GDT release, the Gaseous Waste Management Rad Monitor will automatically close GWM-309.

Technical Reference(s): OP-500-007 Att. 4.50 Rev. 16 (Attach if not previously provided) OP-901-413, page 4 and 6 Rev. 2 (including version/revision number) SD-GWM page 13 Rev. 6 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO40 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10, 13 55.43 Comments: Removed The ATC will verify from the stem because it could be considered cueing. Changed part 2 of the distractors to test if the applicant knows which Radiation Monitor will isolate the GDT discharge.

Revision 2 Facility: Waterford 3 Page 48 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 000068 AK2.03 Importance Rating 2.9 K/A Statement 068 Control Room Evac., AK2.03 Knowledge of the interrelations between the Control Room Evacuation and the following: Controllers and positioners.

Proposed Question: RO 25 Rev: 2 Given:

A fire developed in the Control Room, requiring the Control Room to be evacuated The crew is performing OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown MS-116A, SG1 Atmospheric Dump, has spuriously opened Prior to leaving the Control Room, the BOP will place ____(1)____ to manual and lower output to 0% and ____(2)____ .

(1) (2)

A. only the MS-116A manually initiate a Main controller Steam Isolation Signal B. only the MS-116A close both Main Steam controller Isolation Valves using its C/S C. both MS-116A and B close both Main Steam controllers Isolation Valves using its C/S D. both MS-116A and B manually initiate a Main controllers Steam Isolation Signal Revision 2 Facility: Waterford 3 Page 49 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Part 1 is correct. The MSIS would close the MSIVs. An MSIS is actuated later in the procedure, but not until controls are established at LCP-43.

B. CORRECT: If evacuating the control room due to a fire, the BOP immediate action is to take the ADV controller to manual and lower output to 0% for any ADV that is acting spuriously. The next action for the BOP is to close the MSIVs.

C. Incorrect. The action is to manually close the ADV if it is acting spuriously. The MSIS would close the MSIVs. Part 2 is correct.

D. Incorrect. The action is to manually close the ADV if it is acting spuriously. The MSIS would close the MSIVs. An MSIS is actuated later in the procedure, but not until controls are established at LCP-43.

Technical Reference(s): OP-901-502 step 2.4 Rev. 33 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO51 obj. 2 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments: NRC comment: Placed the initial condition that MS-116A has spuriously opened in the stem and adjusted the distractors accordingly.

Revision 2 Facility: Waterford 3 Page 50 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 000074 EA1.01 Importance Rating 4.2 K/A Statement 074 Inad. Core Cooling, EA1.01: Ability to operate and monitor the following as they apply to a Inadequate Core Cooling: RCS Water Inventory.

Proposed Question: RO 26 Rev: 2 Given:

Small Break LOCA occurred one hour ago Pressurizer level is 0%

RCS is saturated The Reactor Vessel Level Monitoring System can be monitored using QSPDS and recorders on ____(1)____.

To meet the requirements to perform Hot and Cold Leg Injection, the CRS will direct the ATC to report when vessel plenum level is less than 80%. The equivalent level will be indicated on the RVLMS QSPDS mimic when level ___(2)___ indicates voided.

(1) (2)

A. CP-8 6 B. CP-7 6 C. CP-7 5 D. CP-8 5 Revision 2 Facility: Waterford 3 Page 51 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. RVLMS can be read on recorders located on CP-7, a large portion of the accident indicators are located on CP-8, but not RVLMS. The applicant needs to be aware that RVLMS numbering starts at the top of the head is numbered from 1-8.

Level 6 is plausible since it is a level in the plenum that is not at the top or bottom.

B. Incorrect. Part 1 is correct. The applicant needs to be aware that RVLMS numbering starts at the top of the head is numbered from 1-8. Level 6 is plausible since it is a level in the plenum that is not at the top or bottom.

C. CORRECT: RVLMS can be read on recorders located on CP-7. Level 5 being voided is an indication that Reactor Vessel level is less than 80% in the plenum.

D. Incorrect. RVLMS can be read on recorders located on CP-7, a large portion of the accident indicators are located on CP-8, but not RVLMS. Level 5 being voided is an indication that Reactor Vessel level is less than 80% in the plenum.

Technical Reference(s): OP-902-002 step 53 Rev. 20 (Attach if not previously provided) SD-QSP page 13 Rev. 5 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE02 obj. 17 (As available)

WLP-OPS-QSP00 obj. 6 Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2, 10 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 52 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # CE/A11 AA2.2 Importance Rating 3.0 K/A Statement CE/A11 RCS Overcooling, AA2.2: Ability to determine and interpret the following as they apply to the (RCS Overcooling): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

Proposed Question: RO 27 Rev: 2 Given:

A steam line rupture has occurred on Steam Generator #1 and the crew is performing the actions of OP-902-004, Excess Steam Demand Recovery Procedure RCS pressure is 1600 PSIA Containment pressure is 18 PSIA Steam Generator #1 has been isolated in accordance with OP-902-004, Excess Steam Demand Recovery Procedure The crew is ready to perform a controlled plant cooldown Which ONE of the following describes the method and maximum rate allowed to perform the RCS cooldown in accordance with OP-902-004?

Cooldown using A. ADVs at no greater than 50°F per hour B. SBCS at no greater than 100°F per hour C. SBCS at no greater than 50°F per hour D. ADVs at no greater than 100°F per hour Revision 2 Facility: Waterford 3 Page 53 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: The Steam Bypass Control System will be unavailable due to the MSIS signal (occurred at 17.1 psia). ADVs will be required. The cooldown limit for natural circulation conditions with an assymetric S/G is 50ºF/hr. An assymetric S/G cooldown occurs when one S/G is used for the cooldown and the other S/G is not being steamed by either the SBCS or the ADV. S/G #1 has been isolated per OP-902-004, therefore, the SBCS is not available and the ADV is in manual and closed.

B. Incorrect. The Steam Bypass Control System will be unavailable due to the MSIS signal (occurred at 17.1 psia). ADVs will be required. The cooldown limit for natural circulation conditions without an assymetric S/G is 100 ºF/hr.

C. Incorrect. The Steam Bypass Control System will be unavailable due to the MSIS signal (occurred at 17.1 psia). ADVs will be required. The cooldown limit for natural circulation conditions with an assymetric S/G is 50ºF/hr.

D. Incorrect. The Steam Bypass Control System will be unavailable due to the MSIS signal (occurred at 17.1 psia). ADVs will be required. The cooldown limit for natural circulation conditions without an assymetric S/G is 100 ºF/hr.

Technical Reference(s): TG-OP-902-004 step 49 revision 307 OP-902-004 steps 16, 49 and note prior to step 49 (Attach if not previously provided) Rev. 16 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE04 objs. 7 and 8 (As available)

Question Source: Bank # RO41 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2008 NRC RO Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comment: NRC comment: Changed from a LOD-4 to a LOD-3.

Revision 2 Facility: Waterford 3 Page 54 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 003 K6.14 Importance Rating 2.6 K/A Statement 003 Reactor Coolant Pump, K6.14: Knowledge of the effect of a loss or malfunction on the following will have on the RCPS: Starting requirements.

Proposed Question: RO 28 Rev: 2 To prevent motor overload in excess of the nameplate horsepower rating, the minimum RCS cold leg temperature for RCP operation is 350ºF when operating in three pump configuration using RCP ____(1)____.

This limitation is applicable since this pump requires more brake horsepower because it

___(2)___ of the four reactor coolant pumps.

(1) (2)

A. 1A has the largest flywheel B. 2A has the largest flywheel C. 2A develops the highest head D. 1A develops the highest head Revision 2 Facility: Waterford 3 Page 55 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. RCP 1A is plausible because OI-038-000, Expectations for EOPs, has the crew trip RCP 1A and 2A first so that we dont exceed this limitation in the question and keep one RCP in each loop running. Plausible because RCPs have a flywheel and a larger one would require more horsepower.

B. Incorrect. Part 1 is correct. Plausible because RCPs have a flywheel and a larger one would require more horsepower.

C. CORRECT: This question is an administrative start interlock (starting the third pump if it is RCP 2A). Per OP-001-002, To prevent motor overload in excess of the nameplate horsepower rating, the minimum RCS cold leg temperature for RCP operation is 350ºF when operating in three pump configuration using RCP2A. This is because RCP 2A develops higher head and requires more horsepower. Important concept for the applicant to know since this is the reason for the securing sequence directed in the EOPs.

D. Incorrect. RCP 1A is plausible because OI-038-000, Expectations for EOPs, has the crew trip RCP 1A and 2A first so that we dont exceed this limitation in the question and keep one RCP in each loop running Technical Reference(s): OP-001-002 Precaution 3.1.5 Rev. 22 (Attach if not previously provided) OI-038-000 step 5.4.71 Rev 13 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-RCP00 obj. 10 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 56 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 004 A4.07 Importance Rating 3.9 K/A Statement 004 Chemical and Volume Control, A4.07: Ability to manually operate and/or monitor in the control room: Boration/dilution.

Proposed Question: RO 29 Rev: 2 Given:

The plant is at 100% power Reactor Coolant Pump (RCP) 1A seal has failed and the BOP is lowering ACC Header A CCW HX outlet TCV (ACC-126A) controller set point to restore RCP 1A controlled bleedoff temperature back into the normal band.

As a result, the ATC may be required to ________________.

A. borate due to Letdown Heat Exchanger outlet temperature lowering B. borate due to Letdown Heat Exchanger outlet temperature rising C. dilute due to Letdown Heat Exchanger outlet temperature lowering D. dilute due to Letdown Heat Exchanger outlet temperature rising Revision 2 Facility: Waterford 3 Page 57 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: Lowering ACC-126A set point will cause increased cooling flow from ACCW to the CCW Heat Exchanger. CCW from the outlet of the CCW HX is the cooling medium for the Letdown HX. Precaution 3.17 of OP-002-005 states Reactivity should be monitored for changes when Letdown temperature changes. Lowering letdown temperature may remove boron from the CVC IX effluent. This would result in a dilution to the RCS and the need to borate.

B. Incorrect. Part 1 is correct. Letdown HX outlet temperature will lower if ACC-126A setpoint is reduced.

C. Incorrect. Letdown HX outlet temperature lowering will cause IX effluent boron concentration to lower. Boration will be required.

D Incorrect. Letdown HX outlet temperature will lower if ACC-126A setpoint is reduced.

Letdown HX outlet temperature lowering will cause IX effluent boron concentration to lower.

Boration will be required.

Technical Reference(s): OP-002-005 precaution 3.17 Rev. 56 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CVC00 OBJ. 10 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 2 10 CFR Part 55 Content: 55.41 6, 10 55.43 Comments: Changed the question due to NRC comment. New question is written to the same K/A.

Revision 2 Facility: Waterford 3 Page 58 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 005 A4.02 Importance Rating 3.4 K/A Statement 005 Residual Heat Removal, A4.02: Ability to manually operate and/or monitor in the control room: Heat exchanger bypass flow control.

Proposed Question: RO 30 Rev: 2 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 Revision 2 Facility: Waterford 3 Page 59 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. To prevent entry into Mode 5 (RCS temp <200°F), less SDC flow is required through the SDC HX to compensate for CCW temperature dropping. This is done by closing the TCV (SI-415A). Part 2 is correct B. Incorrect. To prevent entry into Mode 5 (RCS temp <200°F), less SDC flow is required through the SDC HX to compensate for CCW temperature dropping. This is done by closing the TCV (SI-415A). To maintain flow constant, the FCV (SI-129A) will automatically open since there is now less flow going through the HX.

C. Incorrect. Part 1 is correct. SI-129A will open to maintain flow constant since there is now less flow going through the SDC HX.

D. CORRECT: To prevent entry into Mode 5 (RCS temp <200°F), less SDC flow is required through the SDC HX to compensate for CCW temperature dropping. This is done by closing the TCV (SI-415A). To maintain flow constant, the FCV (SI-129A) will automatically open since there is now less flow going through the HX. SI-129A is the bypass around Shutdown Cooling HX A.

Technical Reference(s): SD-SDC pp. 5,6,13 revision 8 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-SDC00 obj 4 (As available)

Question Source: Bank # RO31 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2015 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 60 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 005 2.1.20 Importance Rating 4.6 K/A Statement 005 Residual Heat Removal, 2.1.20: Ability to interpret and execute procedure steps.

Proposed Question: RO 31 Rev: 2 Given:

Plant is in MODE 5 The RCS was drained to 14.5 ft. MSL LPSI pumps have been secured due to RCS leakage HPSI Pump B has been started in accordance with OP-901-131, Shutdown Cooling Malfunction RCS level has been raised to and is being maintained at 16 ft. MSL To restore a Shutdown Cooling train to service in accordance with OP-901-131, the crew will vent and start LPSI Pump ____(1)____ because HPSI Pump B is injecting to

_____(2)_____ .

(1) (2)

A. A Hot Leg 1 B. A Hot Leg 2 C. B Hot Leg 1 D. B Hot Leg 2 Revision 2 Facility: Waterford 3 Page 61 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. The crew will start LPSI pump A because HPSI Pump B is injecting to the suction of LPSI pump A. HPSI Pump B injects to Hot leg #2 (not hot leg #1). LPSI pump A takes a suction from hot leg 2.

B. CORRECT: The crew will start LPSI pump A because HPSI Pump B is injecting to the suction of LPSI pump A. HPSI Pump B injects to Hot leg #2. LPSI pump A takes a suction from hot leg 2.

C. Incorrect. The crew will start LPSI pump A because HPSI Pump B is injecting to the suction of LPSI pump A. HPSI Pump B injects to Hot leg #2 (not hot leg #1). LPSI pump A takes a suction from hot leg 2.

D. Incorrect. The crew will start LPSI pump A because HPSI Pump B is injecting to the suction of LPSI pump A. HPSI Pump A (not running) injects to Hot leg #1. LPSI pump A takes a suction from hot leg 2.

Technical Reference(s): OP-901-131 section E1 Rev. 304 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-REQ21 obj. 6 (As available)

Question Source: Bank # RO26 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 4 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 62 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 006 K4.17 Importance Rating 3.8 K/A Statement 006 Emergency Core Cooling, K4.17: Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following: Safety Injection valve interlocks.

Proposed Question: RO 32 Rev: 2 Given:

Which ONE of the following describes the operations associated with SI-106A, RWSP Outlet Isolation valve, upon the receipt of a Recirculation Actuation Signal (RAS)?

A. Will automatically close immediately upon RAS B. Will automatically close once SI-602A is fully open C. Can be manually closed from CP-8 immediately upon RAS D. Can be manually closed from CP-8 once SI-602A is fully open Revision 2 Facility: Waterford 3 Page 63 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. SI-106 valves do not reposition on a RAS (the open signal from the SIAS is removed). This valve is required to be manually closed upon a RAS and this manual closure is interlocked with SI-602 being full open.

B. Incorrect. SI-106 valves do not reposition on a RAS (the open signal from the SIAS is removed). This valve is required to be manually closed upon a RAS and this manual closure is interlocked with SI-602 being full open.

C. Incorrect. SI-106 valves do not reposition on a RAS (the open signal from the SIAS is removed). This valve is required to be manually closed upon a RAS and this manual closure is interlocked with SI-602 being full open.

D. CORRECT: SI-106 valves do not reposition on a RAS (the open signal from the SIAS is removed). This valve is required to be manually closed upon a RAS and this manual closure is interlocked with SI-602 being full open.

Technical Reference(s): SD-SI page 16 Rev. 15 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-SI00 obj. 4 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments: NRC comment: Changed the question to meet the K/A. Revised distractors A and C to fix subset issue.

Revision 2 Facility: Waterford 3 Page 64 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 007 A2.03 Importance Rating 3.6 K/A Statement 007 Pressurizer Relief/Quench Tank, A2.03: Ability to (a) predict the impacts of the following malfunctions or operations on the PRTS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Overpressurization of the PZR.

Proposed Question: RO 33 Rev: 2 Given:

An Excess Steam Demand occurred inside containment SIAS, CIAS, MSIS and CSAS have been initiated Pressurizer level is 2% and starting to rise Representative CET temperature and RCS pressure start to rise Based on the current conditions, the crew will ____(1)____. The Pressurizer Safety Valves are designed to lift at ____(2)____ psia.

(1) (2)

A. stabilize RCS pressure above 2500 HPSI Pump shutoff head B. stabilize RCS pressure above 2750 HPSI Pump shutoff head C. secure one HPSI Pump at a time 2500 D. secure one HPSI Pump at a time 2750 Revision 2 Facility: Waterford 3 Page 65 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: OP-902-004 step for stabilizing RCS temperature directs the crew to maintain RCS pressure within 1500-1600 psia of SG pressure. The shutoff head of the HPSI pump is just below 1500 psia. The lift set point of the Pressurizer safeties is 2500 psia. This part of the question is what meets the predict the impact part of the K/A.

B. Incorrect. Part 1 is correct. The safety limit for RCS pressure is 2750 psia, but the pressurizer safety valves lift at 2500 psia.

C. Incorrect. With pressurizer level at 2%, HPSI throttle criteria is not met. HPSI pumps cannot be secured until Pressurizer level has risen above 7%. There is a step in 902-004 to secure HPSI pumps one at a time once HPSI throttle criteria is met. Part 2 is correct.

D. Incorrect. With pressurizer level at 2%, HPSI throttle criteria is not met. HPSI pumps cannot be secured until Pressurizer level has risen above 7%. There is a step in 902-004 to secure HPSI pumps one at a time once HPSI throttle criteria is met. The safety limit for RCS pressure is 2750 psia, but the pressurizer safety valves lift at 2500 psia.

Technical Reference(s): OP-902-004 steps 18 and 20 Rev. 16 (Attach if not previously provided) SD-RCS page 55 Rev. 21 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE04 objs. 4 and 7 (As available)

WLP-OPS-RCS00 obj. 4 Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 4 10 CFR Part 55 Content: 55.41 3, 10 55.43 Comments: Submitted for free review. No changes are required to the question. NRC Comment: Removed wording in the stem take actions to control Pressurizer level and prevent challenging Pressurizer safeties by. Also changed the distractors C and D to secure one HPSI pump at a time from secure HPSI pumps.

Revision 2 Facility: Waterford 3 Page 66 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 008 K1.05 Importance Rating 3.0 K/A Statement 008 Component Cooling Water, K1.05: Knowledge of the physical connections and/or cause-effect relationships between the CCWS and the following systems:

Sources of makeup water.

Proposed Question: RO 34 Rev: 2 The normal source of makeup to the Auxiliary Component Cooling Water (ACCW) Wet Cooling Towers is the _______(1)_______. The normal source of makeup water to the Component Cooling Water Surge Tank is the _______(2)_________.

(1) (2)

A. Condensate Storage Pool Demineralized Water Storage Tank B. Condensate Storage Pool Condensate Storage Pool C. Demineralized Water Storage Tank Condensate Storage Pool D. Demineralized Water Storage Tank Demineralized Water Storage Tank Revision 2 Facility: Waterford 3 Page 67 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Wrong makeup source for WCTs. Correct Makeup source for CCW Surge Tank.

B. Incorrect. Wrong Makeup source to the WCTs and wrong source to the CCW Surge Tank. The CSP is the backup makeup source to the CCW Surge Tank.

C. Incorrect. The normal source of makeup to the WCTs is the DWST; however, the CSP is not the normal makeup source to the CCW Surge Tank.

D. CORRECT: The normal source of makeup to the WCTs and the CCW Surge Tank is the Demineralized Water Storage Tank.

Technical Reference(s): SD-CMU figure 2, Rev. 8 (Attach if not previously provided) SD-CC page 11,13 Rev. 22 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CC00 obj. 2,3 (As available)

Question Source: Bank # RO34 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2012 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Revision 2 Facility: Waterford 3 Page 68 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 008 A3.08 Importance Rating 3.6 K/A Statement 008 Component Cooling Water, A3.08: Ability to monitor automatic operation of the CCWS, including: Automatic actions associated with the CCWS that occur as a result of a safety injection signal.

Proposed Question: RO 35 Rev: 2 Given:

A Steam Line Break has occurred outside containment The crew has manually initiated a MSIS, CIAS and SIAS As a result, Component Cooling Water Flow has been lost to ________________.

A. the Spent Fuel Pool Heat Exchanger B. Emergency Diesel Generator B C. the Reactor Coolant Pumps D. Train B Dry Cooling Tower Revision 2 Facility: Waterford 3 Page 69 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: CCW flow is lost to the Spent Fuel Pool Heat Exchanger due to CC-620, Spent Fuel Pool Heat Exchanger TCV, going closed on a SIAS.

B. Incorrect. EDG B is located on the safety train and CCW flow is not isolated by the SIAS.

C. Incorrect. The reactor coolant Pumps are located on the CCW AB header. Flow will be isolated on the B train going to the AB header but will still be supplied from the A train going to the AB header.

D. Incorrect. Train B Dry Cooling Tower will isolate in the event of a low level in the CCW surge tank but flow is maintained through the tower upon a receipt of a SIAS with no low level.

Technical Reference(s): SD-CC page 37, 46, figure 22 Rev. 22 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CC00 obj. 5 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 7 55.43 Comments: NRC Comment: Change to a LOD-3 from LOD-4 Revision 2 Facility: Waterford 3 Page 70 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 010 K6.01 Importance Rating 2.7 K/A Statement 010 Pressurizer Pressure Control, K6.01 Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: Pressure Detection Systems.

Proposed Question: RO 36 Rev: 2 Given:

Plant is at 100% power Pressurizer Pressure Channel X/Y recorder (RC-IPR-0100) indicates that the in-service Pressurizer Pressure Control Channel instrument has failed low The Pressurizer Pressure Controller output will ____(1)____. The failed control channel will energize ___(2)___ heaters.

(1) (2)

A. rise both proportional and backup B. lower both proportional and backup C. lower only proportional D. rise only proportional Revision 2 Facility: Waterford 3 Page 71 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. The in-service pressurizer pressure control channel failing low will cause the PPC system to see actual pressure less than setpoint. The pressurizer pressure controller output will lower to raise pressure (energize heaters). Part 2 is correct.

B. CORRECT: The in-service pressurizer pressure control channel failing low will cause the PPC system to see actual pressure less than setpoint. The pressurizer pressure controller output will lower to raise pressure (energize heaters). The pressurizer pressure controller controls only the proportional heaters. The control channel that inputs to the pressure controller is the same instrument that energizes the backup heaters at 2200 psia. The pressure controller output does not input to the backup heaters.

C. Incorrect. Part 1 is correct. A high pressure heater cutout will de-energize all heaters at 2270 psia through the low level heater cutout switch. A pressure of 2300 psia is plausible since this is the pressure at which the Pressurizer spray valves are full open on rising pressure.

D. Incorrect. The in-service pressurizer pressure control channel failing low will cause the PPC system to see actual pressure less than setpoint. The pressurizer pressure controller output will lower to raise pressure (energize heaters). A pressure of 2300 psia is plausible since this is the pressure at which the Pressurizer spray valves are full open on rising pressure.

Technical Reference(s): SD-PLC pages 27, 37,38 Rev. 10 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO10 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 7, 10 55.43 Comment: Changed the second part of the question due to conflict with RO37.

Revision 2 Facility: Waterford 3 Page 72 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 010 A1.01 Importance Rating 2.8 K/A Statement 010 Pressurizer Pressure Control, A1.01: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including: PZR and RCS boron concentrations.

Proposed Question: RO 37 Rev: 2 OP-010-005 Attachment 9.13 Boron Equalizations directs the crew to avoid operating Pressurizer pressure near the heater cutout pressure of ____(1)____ psia while performing Boron Equalization.

Boron Equalization shall be initiated if a minimum change in RCS boron concentration of greater than ____(1)____ ppm is anticipated.

(1) (2)

A. 2275 50 B. 2275 10 C. 2270 50 D. 2270 10 Revision 2 Facility: Waterford 3 Page 73 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Pressurizer pressure of 2275 psia is the heater cutout bistable that will secure the heaters on a 4% level deviation between pressurizer level and the setpoint. Part 2 is correct.

B. Incorrect. Pressurizer pressure of 2275 psia is the heater cutout bistable that will secure the heaters on a 4% level deviation between pressurizer level and the setpoint. Boron Equalization is initiated to maintain the RCS and Pressurizer within 10 ppm of each other, but must be initiated if the anticipated change in RCS concentration is 50 ppm.

C. CORRECT: The note preceding step 9.13.1 states to avoid operating with Pressurizer pressure near 2270 psia to prevent a heater cutout. (References CR-2012-1861). A different not preceding step 9.13.1 states that Boron Equalization shall be initiated if the anticipated change in RCS concentration is 50 ppm.

D. Incorrect. Part 1 is correct. Boron Equalization is initiated to maintain the RCS and Pressurizer within 10 ppm of each other, but must be initiated if the anticipated change in RCS concentration is 50 ppm.

Technical Reference(s): OP-010-005 notes before step 9.13.1 Rev. 329 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPN02 obj. 2 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 3 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 6, 10 55.43 Comments: Changed the question due to NRC comments. Kept the same K/A.

Revision 2 Facility: Waterford 3 Page 74 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 012 K1.02 Importance Rating 3.4 K/A Statement 012 Reactor Protection, K1.02: Knowledge of the physical connections and/or cause effect relationships between the RPS and the following systems: 125V dc system.

Proposed Question: RO 38 Rev: 2 Given:

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

_______(2)______.

(1) (2)

A. 1, 2, 5, and 6 occurs B. 1, 2, 5, and 6 does not occur C. 1, 3, 5, and 7 does not occur D. 1, 3, 5, and 7 occurs Revision 2 Facility: Waterford 3 Page 75 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. This arrangement of breakers opening is the same as losing an instrument SUPS. With this combination of breakers, the reactor does not trip. Part 2 is correct.

B. Incorrect. This arrangement of breakers opening is the same as losing an instrument SUPS. With this combination of breakers, the reactor does not trip.

C. Incorrect. Part 1 is correct. . The arrangement of the reactor trip switchgear breakers is such that this combination of RTSG breakers will de-energize the CEDM coils.

D. CORRECT: A Reactor trip will occur on a loss of the A-DC bus. The arrangement of the reactor trip switchgear breakers is such that this combination of RTSG breakers will de-energize the CEDM coils. There are arrangements such that four RTSG breakers will open and not trip the reactor. This question is comprehensive since the applicant must know what breakers are affected and then apply it to the RTSG flow path to the CEDM coils.

Technical Reference(s): OP-901-313 page 13 Rev. 305 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO3 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 2 10 CFR Part 55 Content: 55.41 6, 10 55.43 Comments: NRC Comment: Changed from a LOD-3 to a LOD-2 Revision 2 Facility: Waterford 3 Page 76 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 013 K2.01 Importance Rating 3.6 K/A Statement 013 Engineered Safety Features Actuation, K2.01: Knowledge of bus power supplies to the following: ESFAS/safeguards equipment control.

Proposed Question: RO 39 Rev: 2 What is the power supply to MS-401A, EFW Pump Turbine Steam Supply Valve?

A. A-DC B. AB-DC C. MCC-312A D. MCC-312AB Revision 2 Facility: Waterford 3 Page 77 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. MS-401A motor operated valve receives power from the AB-DC bus.

B. CORRECT: MS-401A motor operated valve receives power from the AB-DC bus.

C. Incorrect. MCC-312A is a safety related 480 VAC power supply. MS-401A motor operated valve receives power from the AB-DC bus.

D. Incorrect. MCC-312AB is a safety related 480 VAC power supply. MS-401A motor operated valve receives power from the AB-DC bus Technical Reference(s): OP-005-004 page 73 Rev. 33 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-EFW00 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments: NRC comment: Changed distractors C and D to a 480V MCC power supply instead of a vital SUPS power supply for better plausibility.

Revision 2 Facility: Waterford 3 Page 78 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 013 A2.02 Importance Rating 4.3 K/A Statement 013 Engineered Safety Features Actuation, A2.02: Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; Excess steam demand.

Proposed Question: RO 40 Rev: 2 Given:

An Excess Steam Demand event has occurred The crew has entered OP-902-004, Excess Steam Demand Recovery Procedure Following the Main Steam Isolation Signal (MSIS), indications are:

Steam Generator 1 pressure is 400 PSIA Steam Generator 2 pressure is 505 PSIA Steam Generator 1 level is 9% NR and lowering Steam Generator 2 level is 9% NR and lowering Currently, ____(1)____ initiated.

When isolating Steam Generator #1, the BOP will direct the NAO to check SG1

_____(2)________ side Main Steam Safety Valves are closed.

(1) (2)

A. only EFAS-2 is East B. only EFAS-2 is West C. neither EFAS-1 nor East EFAS-2 are D. neither EFAS-1 nor West EFAS-2 are Revision 2 Facility: Waterford 3 Page 79 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Neither EFAS 1 nor EFAS 2 will be initiated because S/G #1 and S/G #2 pressures are less than 666 PSIA and S/G #2 pressure is not 123 psid greater than S/G #1 pressure.

Part 2 is correct.

B. Incorrect. Neither EFAS 1 nor EFAS 2 will be initiated because S/G #1 and S/G #2 pressures are less than 666 PSIA and S/G #2 pressure is not 123 psid greater than S/G #1 pressure.

The MSSVs for SG#1 are on the west side of the plant. SG#2 MSSVs are on the east side.

C. Incorrect. Part 1 is correct. The MSSVs for SG#1 are on the west side of the plant. SG#2 MSSVs are on the east side.

D. CORRECT: Neither EFAS 1 nor EFAS 2 will be initiated because S/G #1 and S/G #2 pressures are less than 666 PSIA and S/G #2 pressure is not 123 psid greater than S/G #1 pressure. The last step for isolating a SG is to check MSSVs closed for that generator. The location is important for the RO to know because he must direct the AO to look at the correct side or he/she may field a call stating there is a steam release on the west side.

Technical Reference(s): SD-PPS page 36 Rev. 17 (Attach if not previously provided) OP-902-004 step 16 Rev. 16 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPS obj. 5 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 7, 10 55.43 Comment: NRC Comment: Raised SG2 pressure in the stem from 475 psia to 505 psia to make it closer to the 123 psid. Changed part 2 of the distractors to the location of the MSSVs.

Revision 2 Facility: Waterford 3 Page 80 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 022 K3.02 Importance Rating 3.0 K/A Statement 022 Containment Cooling, K3.02: Knowledge of the effect that a loss or malfunction of the CCS will have on the following: Containment instrumentation readings.

Proposed Question: RO 41 Rev: 2 Given:

A Small Break LOCA has occurred The BOP reports that Component Cooling Water has been lost to one train of Containment Fan Coolers and containment temperature is rising Per OI-038-000, EOP Operations Expectations/Guidance Procedure, ____(1)____

parameter values will be used if a harsh environment exists in containment . A harsh environment is defined as Containment Temperature greater than or equal to a minimum temperature of _____(2)_____ ºF.

(1) (2)

A. underlined 180 B. underlined 200 C. bracketed 200 D. bracketed 180 Revision 2 Facility: Waterford 3 Page 81 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Part 1 is plausible because some numbers in the EOPs are underlined but are not harsh environment numbers. 180 ºF is an number less than 212F, so it is plausible.

B. Incorrect. . Part 1 is plausible because some numbers in the EOPs are underlined but are not harsh environment numbers. Part 2 is correct.

C. CORRECT: The effect of losing CCW flow to a train of CFCs is that containment temperature will rise and cause inaccuracies of some containment instruments. The EOPs account for this inaccuracy by supplying the operators with bracketed parameter values that must be used when containment temperature is greater than or equal to 200ºF.

D. Incorrect. Part 1 is correct. 180 ºF is an number less than 212F, so it is plausible.

Technical Reference(s): OI-038-000 page 6 Rev. 13 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE01 obj. 4 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 10 55.43 Comments: Changed 220F distractor in part 2 distractors to a number less than 212F.

Revision 2 Facility: Waterford 3 Page 82 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 026 K2.01 Importance Rating 3.4 K/A Statement 026 Containment Spray, K2.01: Knowledge of bus power supplies to the following: Containment spray pumps.

Proposed Question: RO 42 Rev: 2 Containment Spray (CS) Pump B is powered from which bus?

A. SWGR 31B B. SWGR 3B C. SWGR 1B D. SWGR 2B Revision 2 Facility: Waterford 3 Page 83 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect: Containment Spray (CS) Pump B is powered from the 3B bus. The 31B is a 480 V safety bus fed from the 3B bus.

B. CORRECT: Containment Spray (CS) Pump B is powered from the 3B bus.

C. Incorrect: Containment Spray (CS) Pump B is powered from the 3B bus. The 1B bus is a 6.9 Kv which carries large loads.

D. Incorrect: Containment Spray (CS) Pump B is powered from the 3B bus. The 2B bus is a 4.16 Kv non-safety bus.

Technical Reference(s): OP-009-001 page 40 Rev. 306 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-ED00 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4 55.43 Revision 2 Facility: Waterford 3 Page 84 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 039 K5.08 Importance Rating 3.6 K/A Statement 039 Main and Reheat Steam, K5.08: Knowledge of the operational implications of the following concepts as the apply to the MRSS: Effect of steam removal on reactivity.

Proposed Question: RO 43 Rev: 2 Given:

A reactor startup has commenced following a reactor trip from 100% power that occurred 4 days ago 250 EFPD SBCS valves are maintaining Tave Which ONE of the following will cause actual critical rod position to be LOWER than estimated critical rod position?

A. SBCS master controller setpoint fails upward 50 PSI B. SBCS permissive setpoint fails upward 50 PSI C. SBCS master controller setpoint fails downward 50 PSI D. SBCS permissive setpoint fails downward 50 PSI Revision 2 Facility: Waterford 3 Page 85 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Raising the master controller setpoint will result in a higher Tave and add negative reactivity due to negative MTC (MOC conditions). Critical rod height would be higher than estimated.

B. Incorrect. Raising the permissive setpoint by 50 PSI simply moves the permissive closer to the demand setpoint. It does not change the modulation point of the valves.

C. CORRECT: Lowering the master controller setpoint will result in SBCS valves opening sooner, reducing RCS temperature (250 EFPD ensures a negative MTC).

Colder moderator will produce more thermal neutrons, lowering the required critical rod position.

D. Incorrect. Lowering the permissive setpoint will bring the permissive signal in earlier, but the master controller setpoint will be the same, meaning no change in RCS temperature.

Technical Reference(s): SD-SBC page 9 and figure 3. Rev. 10 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-SBC00 obj. 8 (As available)

Question Source: Bank # RO15 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2008 RO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 14 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 86 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 059 K4.18 Importance Rating 2.8 K/A Statement 059 Main Feedwater, K4.18: Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following: Automatic feedwater reduction on plant trip.

Proposed Question: RO 44 Rev: 2 Given:

Power is 100%

SG-ILR-1111, Steam Generator 1 Narrow Range level indicator is reading 0% on the CP-1 recorder SG-ILR-1105, Steam Generator 1 Narrow Range level indicator is reading 68%

on the CP-1 recorder All Narrow Range Steam Generator levels on CP-8 are indicating 68%

With the above conditions, a reactor trip occurs.

Main Feedwater Pump A speed controller ___(1)___ . Main Feedwater Regulating Valve A and Startup Feedwater Regulating Valve A Controllers __(2)___.

(1) (2)

A. lowers to 3900 RPM remain at their pre-trip positions B. lowers to 3900 RPM reposition to their Reactor Trip Positions C. remains at 4500 RPM remain at their pre-trip positions D. remains at 4500 RPM reposition to their Reactor Trip Positions Revision 2 Facility: Waterford 3 Page 87 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: All controllers on the FWCS #1 side are in manual due to a level deviation. Upon a reactor trip, the design of the FWCS is to return the MFP controller to auto for 5 seconds such that MFP minimum speed is obtained (3900 RPM). The Main Feedwater Reg and Startup Feedwater Reg Valve controllers do not have this feature and will remain in their pre-trip position.

B. Incorrect. Part 1 is correct. All controllers on the FWCS #1 side are in manual due to a level deviation. The Main Feedwater Reg Valve and Startup Feedwater Reg Valve controllers will remain in their pre-trip position.

C. Incorrect. All controllers on the FWCS #1 side are in manual due to a level deviation. Upon a reactor trip, the design of the FWCS is to return the MFP controller to auto for 5 seconds such that MFP mimimum speed is obtained (3900 RPM). Part 2 is correct.

D. Incorrect. All controllers on the FWCS #1 side are in manual due to a level deviation. Upon a reactor trip, the design of the FWCS is to return the MFP controller to auto for 5 seconds such that mimimum speed is obtained (3900 RPM). The Main Feedwater Reg and Startup Feedwater Reg Valve controllers do not have this feature and will remain in their pre-trip position.

Technical Reference(s): SD-FWC00 page 24,25 Rev. 13 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-FWC00 obj. 5 (As available)

Question Source: Bank # RO 45 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2011 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 4 10 CFR Part 55 Content: 55.41 4 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 88 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 076 A1.02 Importance Rating 2.6 K/A Statement 076 Service Water, A1.02: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including: Reactor and turbine building closed cooling water temperatures.

Proposed Question: RO 45 Rev: 2 Given:

The BOP reports rising Turbine Cooling Water (TCW) temperatures The crew enters OP-901-512, Loss of Turbine Cooling Water The BOP will lower TCW temperature using TC-147, Turbine Cooling Water Temperature Control, by taking the control switch to the ____(1)____ position.

To maintain TCW system pressure constant, the control switch for TC-135, Turbine Cooling Water Pressure Control, will be taken to the ___(2)___ position.

(1) (2)

A. less more B. less less C. more less D. more more Revision 2 Facility: Waterford 3 Page 89 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Part 1 is correct. Opening TC-147 will raise system pressure, TC-135 is required to be closed to lower system pressure.

B. CORRECT: To lower TCW temperature, the C/S for TC-147 must be taken to LESS (less temperature). Opening TC-147 will raise system pressure, the C/S for TC-135 must be taken to LESS (will close the valve) to restore system pressure to the previous value.

C. Incorrect. The individual TCVs for components served by TCW have less/more switches which correlates to the valve being more open or less open. The opposite of how the TC-147 works.

D. Incorrect. The individual TCVs for components served by TCW have less/more switches which correlates to the valve being more open or less open. The opposite of how the TC-147 works. Opening TC-147 will raise system pressure, TC-135 is required to be closed to lower system pressure.

Technical Reference(s): OP-901-512 section E3 Rev. 3 (Attach if not previously provided) SD-TCW page 11, Figure 1 Rev. 8 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-TC00 obj. 4 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 10 55.43 Comments: NRC Comment: Changed to a LOD-3 from LOD-4 Revision 2 Facility: Waterford 3 Page 90 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 061 K2.02 Importance Rating 3.7 K/A Statement 061 Auxiliary/Emergency Feedwater, K2.02: Knowledge of bus power supplies to the following: AFW electric drive pumps.

Proposed Question: RO 46 Rev: 2 The Auxiliary Feedwater Pump (AFW Pump) is powered from which bus?

A. 1A B. 2A C. 1B D. 2B Revision 2 Facility: Waterford 3 Page 91 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. The Auxiliary Feedwater (AFW) Pump is a 6.9 KV pump, but is powered from the 1B bus.

B. Incorrect. The Auxiliary Feedwater (AFW) Pump is a 6.9 KV (not 4.16 KV) motor powered from the 1B bus C. CORRECT: The Auxiliary Feedwater (AFW) Pump is a 6.9 KV motor powered from the 1B bus.

D. Incorrect. The Auxiliary Feedwater (AFW) Pump is a 6.9 KV (not 4.16 KV) motor powered from the 1B bus.

Technical Reference(s): OP-003-035 page 20, Rev. 305 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-ED00 obj. 1 (As available)

Question Source: Bank # RO47 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2012 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 92 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 061 A3.03 Importance Rating 3.9 K/A Statement 061 Auxiliary/Emergency Feedwater, A3.03: Ability to monitor automatic operation of the AFW, including: AFW S/G level control on automatic start.

Proposed Question: RO 47 Rev: 2 A Loss of MFW event has occurred. After a manual Reactor trip, the following conditions are observed:

SG 1 pressure is 980 PSIA SG 2 pressure is 960 PSIA SG 1 level is 51% WR level and lowering SG 2 level is 38% WR level and lowering Pressurizer pressure 1900 PSIA Containment pressure 15.3 PSIA With SG 2 EFW flow transmitter failed high, which of the following describes the EFW system response for SG 2?

A. Primary FCV and Backup FCV remain closed.

B. Primary FCV remains closed and backup FCV opens to 175 GPM.

C. Primary FCV opens to preset valve position and Backup FCV remains closed.

D. Primary FCV opens to preset valve position and Backup FCV opens to 400 GPM flow value.

Revision 2 Facility: Waterford 3 Page 93 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. At 55% WR level, the Primary FCV opens to a preset valve position. The EFW flow transmitter failing high has no effect on the Primary FCV at this level.

B. Incorrect. At 55% WR level, the Primary FCV opens to a preset valve position. The EFW flow transmitter failing high has no effect on the Primary FCV at this level. Part 2 is plausible because the backup FCV would open to 175 gpm if the Primary FCV did not open and there was no failed transmitter.

C. CORRECT: At 55% WR level, the Primary FCV opens to a preset valve position. The EFW flow transmitter failing high has no effect on the Primary FCV at this level. At 45% WR, the Backup FCV would have opened to 400 gpm, but with the EFW flow transmitter failed high, the Backup FCV will remain closed D. Incorrect. This would be the correct answer if the EFW flow transmitter was not failed high. At 45% WR, the Backup FCV would have opened to 400 gpm, but with the EFW flow transmitter failed high, the Backup FCV will remain closed.

Technical Reference(s): SD-EFW page 7, Figure 19 Revision 13 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-EFW obj. 6 (As available)

Question Source: Bank # RO46 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2012 NRC RO Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 4 10 CFR Part 55 Content: 55.41 4,8 55.43 Revision 2 Facility: Waterford 3 Page 94 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 062 A3.05 Importance Rating 3.5 K/A Statement 062 AC Electrical Distribution, A3.05: Ability to monitor automatic operation of the ac distribution system, including: Safety-related indicators and controls.

Proposed Question: RO 48 Rev: 2 Given:

• EDG A is running paralleled in TEST mode for surveillance OP-903-068, Emergency Diesel Generator and Subgroup Relay Operability Verification

• A SIAS occurred with NO Loss of Offsite Power condition The EDG output breaker will (1) and the HPSI Pumps will be started (2) .

(1) (2)

A. OPEN by the sequencer B. OPEN immediately C. stay CLOSED by the sequencer D. stay CLOSED immediately Revision 2 Facility: Waterford 3 Page 95 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: EDG output breaker OPENs and after 2 seconds the sequencer loading begins since NO undervoltage conditions existed on the safety bus.

B. Incorrect. EDG output breaker OPENs and after 2 seconds the sequencer loading begins since NO undervoltage conditions existed on the safety bus to ensure NO excess loading if IMMEDIATELY started.

C. Incorrect. EDG output breaker OPENs and after 2 seconds the sequencer loading begins since NO undervoltage conditions existed on the safety bus.

D. Incorrect. EDG output breaker OPENs and after 2 seconds the sequencer loading begins since NO undervoltage conditions existed on the safety bus to ensure NO excess loading if IMMEDIATELY started.

Technical Reference(s): SD-EDG page 40, 49 Rev. 25 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-SEQ00 obj. 1 and 2 (As available)

Question Source: Bank # RO12 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2010 RO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 8 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 96 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 063 A4.02 Importance Rating 2.8 K/A Statement 063 DC Electrical Distribution, A4.02: Ability to manually operate and/or monitor in the control room: Battery voltage indicator.

Proposed Question: RO 49 Rev: 2 The A, B and AB DC Bus voltages can be read on ___(1)___.

A reading of 140 VDC on a DC battery charger is indicative of a charger in ____(2)____.

(1) (2)

A. CP-1 and the Plant float mode Monitoring Computer B. CP-1 only float mode C. CP-1 and the Plant equalize mode Monitoring Computer D. CP-1 only equalize mode Revision 2 Facility: Waterford 3 Page 97 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect: Part 1 is correct. Part 2 is plausible because 140VDC is on the low end of the equalize charge normal values. The high end of the normal range is 135 VDC.

B. Incorrect: Part 1 is plausible because the PMC does not have all the information found on the control boards. Part 2 is plausible because 140VDC is on the low end of the equalize charge normal values. The high end of the normal range is 135 VDC.

C. CORRECT: This question tests on how to find the information and monitor the parameter to determine whether or not the condition is normal. (Float Mode is 132-135 VDC, Equalize Mode is 138.8-142.8 VDC). A value of 140 VDC is above the normal float range and within the equalize mode range.

D. Incorrect: Part 1 is plausible because the PMC does not have all the information found on the control boards. Part 2 is correct.

Technical Reference(s): OP-006-003, page 18 Rev. 306 (Attach if not previously provided) SD-DC page 13 Rev. 9 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-DC00 obj. 3 & 4 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 3 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments: written by the NRC Revision 2 Facility: Waterford 3 Page 98 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 064 K4.10 Importance Rating 3.5 K/A Statement 064 Emergency Diesel Generator, K4.10: Knowledge of ED/G system design feature(s) and/or interlock(s) which provide for the following: Automatic load sequencer: blackout.

Proposed Question: RO 50 Rev: 2 Given:

The crew is restoring Emergency Diesel Generator (EDG) B following a Station Blackout Emergency Diesel Generator B has started and the output breaker is closed The Input Transformer to MCC 315B develops a direct short to ground upon being re-energized by the 1 second Sequencer Load Block (S1 relay)

An undervoltage condition exists on 4160 Volt Bus 3B Which of the following conditions describes the Sequencer response?

A. Immediately stops the automatic loading process due to Under Voltage Override (UVO) condition.

B. Immediately stops the automatic loading process due to Sequencer Lockout (SLO) condition.

C. Stops the automatic loading process when the 7 second Load Block (S3 relay) is reached.

D. Stops the automatic loading process when the 17 second Load Block (S4 relay) is reached.

Revision 2 Facility: Waterford 3 Page 99 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. The Undervoltage Override (UVO) of the Sequencer occurs at 0.5 seconds. UVO is the interlock that allows the sequencer to remain running between 0.5 and 17 seconds while large transformer loads are sequenced on.

B. Incorrect. Sequencer Lockout is blocked between the 0.5 second Sequencer Load block and the 17 Second load block (due to the UVO feature). The short occurs on the 1 Second load block so the sequencer will not stop immediately C. Incorrect. A SLO condition occurs at 17 seconds not 7 seconds as stated in the distractor. Sequencer Lockout is active at the 7 second load block but is blocked by the UVO feature.

D. CORRECT: A SLO condition will occur at Load Block S4 due to the undervoltage condition on Bus 3A.

Technical Reference(s): SD-EDG pg. 53 Rev. 25 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-SEQ obj. 2 (As available)

Question Source: Bank # RO23 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2010 NRC RO Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 100 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 004 K5.30 Importance Rating 3.8 K/A Statement 004 Chemical and Volume Control, K5.30: Knowledge of the operational implications of the following concepts as they apply to the CVCS: Relationship between temperature and pressure in CVCS components during solid plant operation.

Proposed Question: RO 51 Rev: 2 Given:

Solid Plant operations are in progress RCS temperature is 120°F and stable Letdown Back Pressure Controller is operating in AUTO CCW flow is reduced to the in-service SDC Heat Exchanger RCS pressure will ____(1)____ until the Letdown Back Pressure Control Valve throttles

_____(2)____.

(1) (2)

A. lower closed B. rise closed C. lower open D. rise open Revision 2 Facility: Waterford 3 Page 101 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Lowering CCW flow will cause temperature and RCS pressure to rise. To restore RCS pressure to setpoint the letdown backpressure valve will be opened (not closed) to raise letdown flow to lower RCS pressure to setpoint.

B. Incorrect. Lowering CCW flow will cause temperature and RCS pressure to rise. To restore RCS pressure to setpoint the letdown backpressure valve will be opened (not closed) to raise letdown flow to lower RCS pressure to setpoint.

C. Incorrect. Lowering CCW flow will cause temperature and RCS pressure to rise. To restore RCS pressure to setpoint the letdown backpressure valve will be opened to raise letdown flow to lower RCS pressure to setpoint.

D. CORRECT: Per OP-001-001, solid pressurizer pressure is maintained at 150 psia using the backpressure controller. Lowering CCW flow to the in-service SDC Heat Exchanger when RCS temperature is initially stable will cause temperature and RCS pressure to rise. To restore RCS pressure to setpoint the letdown backpressure valve must open to raise letdown flow to lower RCS pressure to setpoint.

Technical Reference(s): OP-001-001 pg. 25 Revision 34 (Attach if not previously provided) SD-SDC Figure 2 Revision 2 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CVC00 obj. 3 (As available)

Question Source: Bank # RO29 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2012 RO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 4 10 CFR Part 55 Content: 55.41 5 55.43 Comment:

Revision 2 Facility: Waterford 3 Page 102 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 073 2.4.4 Importance Rating 4.5 K/A Statement 073 Process Radiation Monitoring, 2.4.4: Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

Proposed Question: RO 52 Rev: 2 Given:

High Activity is detected on Industrial Waste Sump (IWS) radiation monitor PRM-IRE-6778 The high activity on the IWS radiation monitor will ____(1)____ The crew will enter

_____(2)____.

(1) (2)

A. secure the IWS pumps OP-901-414, Effluent Discharge High Radiation B. secure the IWS pumps OP-901-412, Liquid Waste Discharge High Radiation C. align the IWS pump OP-901-412, Liquid Waste discharge MOVs to the Discharge High Radiation Waste Tanks D. align the IWS pump OP-901-414, Effluent discharge MOVs to the Discharge High Radiation Waste Tanks Revision 2 Facility: Waterford 3 Page 103 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. The IWS sump pumps will secure but not due to the high radiation. They will secure because of a momentary loss of their discharge path. Part 2 is correct.

B. Incorrect. The IWS sump pumps will secure but not due to the high radiation. They will secure because of a momentary loss of their discharge path. A high radiation detected in the IWS is the entry conditions for OP-901-414, Effluent Discharge High Radiation.

C. Incorrect. Part 1 is correct. A high radiation detected in the IWS is the entry conditions for OP-901-414, Effluent Discharge High Radiation.

D. CORRECT: High radiation detected on Industrial Waste Sump (IWS) radiation monitor PRM-IRE-6778 will cause the MOV to the OSS to close and the MOV to the waste tank to open. A manual valve must be opened to align flow but the question is asking what happens to the MOVs.

Technical Reference(s): OP-901-414 page 4 Rev. 301 (Attach if not previously provided) SD-SP page 16 Rev. 16.

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO40 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10, 11 55.43 Comments: Wrote a new question with the same K/A. The first question did not have credible distractors.

Revision 2 Facility: Waterford 3 Page 104 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 076 K1.19 Importance Rating 3.6 K/A Statement 076 Service Water, K1.19: Knowledge of the physical connections and/or cause-effect relationships between the SWS and the following systems: SWS emergency heat loads.

Proposed Question: RO 53 Rev: 2 When aligning Auxiliary Component Cooling Water (ACCW) flow to the Essential Chillers the ACCW valves open___(1)____ .

During the transition to ACCW, the ACCW ___(2)____ valves to the Essential Chillers are interlocked to open first.

(1) (2)

A. first, then the CCW valves inlet close B. after the CCW valves outlet close C. after the CCW valves inlet close D. first, then the CCW valves outlet close Revision 2 Facility: Waterford 3 Page 105 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Part 1 is plausible because the applicant could assume that flow is maintained to prevent the Essential Chiller from tripping on low flow. The Essential Chillers have a CCW low flow trip. Part 2 is correct.

B. Incorrect. Part 1 is correct. The ACCW outlet valves to the Essential Chillers will open when the inlet valve is 5 to 10% open to keep the lines full.

C. CORRECT: When aligning the Essential Chillers to ACCW (Wet Mode), the ACCW valves are opened after the CCW valves close to prevent cross-connecting the two systems. The ACCW outlet valves to the Essential Chillers will open when the inlet valve is 5 to 10% open to keep the lines full.

D. Incorrect. Part 1 is plausible because the applicant could assume that flow is maintained to prevent the Essential Chiller from tripping on low flow. The Essential Chillers have a CCW low flow trip. The ACCW outlet valves to the Essential Chillers will open when the inlet valve is 5 to 10% open to keep the lines full.

Technical Reference(s): SD-CC page 29 Rev. 22 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CHW obj. 4 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 4 10 CFR Part 55 Content: 55.41 7 55.43 Comment: Removed To prevent void formation from the stem. It was cueing.

Revision 2 Facility: Waterford 3 Page 106 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 078 K3.01 Importance Rating 3.1 K/A Statement 078 Instrument Air, K3.01: Knowledge of the effect that a loss or malfunction of the IAS will have on the following: Containment air system.

Proposed Question: RO 54 Rev: 2 Given:

Instrument Air has been lost to Containment The crew is performing the actions of OP-901-511, Loss of Instrument Air CEDM COOLING COILS CCW INLET HDR ISOL, CC-646, is failed ____(1)____.

Containment Fan Cooler discharge air flow to the ring header is ___(2)___ .

(1) (2)

A. open unaffected B. closed unaffected C. open bypassed D. closed bypassed Revision 2 Facility: Waterford 3 Page 107 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Part 1 is correct. CCS-102A and CCS-102B, CNTMT COOLING HVAC SAFETY DISCH DPR A(B) will open bypassing discharge flow to the CFC ring header.

B. Incorrect. CC-646, CEDM COOLING CCW INLET HDR ISOL, will fail open on a loss of instrument air. CCS-102A and CCS-102B, CNTMT COOLING HVAC SAFETY DISCH DPR A(B) will open bypassing discharge flow to the CFC ring header C. CORRECT: CC-646, CEDM COOLING CCW INLET HDR ISOL, will fail open on a loss of instrument air allowing full CCW flow to the CEDM coolers. CCS-102A and CCS-102B, CNTMT COOLING HVAC SAFETY DISCH DPR A(B) will open bypassing discharge flow to the CFC ring header.

D. Incorrect. CC-646, CEDM COOLING CCW INLET HDR ISOL, will fail open on a loss of instrument air. Part 2 is correct.

Technical Reference(s): OP-901-511 Attachment 7 Rev. 15 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO50 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 4 10 CFR Part 55 Content: 55.41 10 55.43 Revision 2 Facility: Waterford 3 Page 108 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 103 2.2.44 Importance Rating 4.2 K/A Statement 103 Containment, 2.2.44: Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

Proposed Question: RO 55 Rev: 2 If Containment to ____(1)____ differential pressure reaches 8.5 INWD, Containment Vacuum Relief Valves, CVR-101 and CVR-201, open, and will ______(2)_____ when differential pressure lowers to the reset value.

(1) (2)

A. annulus automatically close B. ambient automatically close C. ambient require manual closure D. annulus require manual closure Revision 2 Facility: Waterford 3 Page 109 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Part 1 is correct. CVR-101 and CVR-201 must be manually closed when the reset value is reached.

B. Incorrect. Containment to Ambient D/P can be read on CP-18 but is not the D/P switch that opens CVR-101 and CVR-201. CVR-101 and CVR-201 must be manually closed when the reset value is reached.

C. Incorrect. Containment to Ambient D/P can be read on CP-18 but is not the D/P switch that opens CVR-101 and CVR-201. Part 2 is correct.

D. CORRECT: CVR-101 and CVR-201 open automatically when annulus pressure is greater than containment pressure by 8.5 INWD (Containment to annulus D/P).

CVR-101 and CVR-201 must be manually closed when the reset value is reached.

Technical Reference(s): SD-CB pages 8 and 9 Rev. 11 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CB00 obj. 2 (As available)

Question Source: Bank # RO55 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2012 RO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge 4 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 9 55.43 Revision 2 Facility: Waterford 3 Page 110 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 001 K5.06 Importance Rating 3.8 K/A Statement 001 Control Rod Drive, K5.06: Knowledge of the following operational implications as they apply to the CRDS: Effects of control rod motion on axial offset.

Proposed Question: RO 56 Rev: 2 Given:

The crew is performing a down power in accordance with OP-901-212, Rapid Plant Power reduction Due to the down power, ASI will be trending in the ____(1)____ direction. To compensate, the ATC will ____(2)____ control rods.

(1) (2)

A. negative insert B. negative withdraw C. positive withdraw D. positive insert Revision 2 Facility: Waterford 3 Page 111 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: As power is lowered, ASI will move in the negative direction (top of the core). To compensate the ATC will insert control rods. Not basic knowledge because the applicant must know that a downpower will cause ASI to move to the top of the core. The top of the core at W3 is a negative ASI which is confusing to some reactor operators.

B. Incorrect. Part 1 is correct. Plausible because the applicant believe that withdrawing control rods will make ASI more positive.

C. Incorrect. As power is lowered, ASI will move in the negative direction (top of the core). Withdrawing control rods would make ASI more positive.

D. Incorrect. As power is lowered, ASI will move in the negative direction (top of the core). Part 2 is correct.

Technical Reference(s): OP-010-005 step 9.10.2.1 Rev. 328 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPN02 obj. 2 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 2 10 CFR Part 55 Content: 55.41 1, 6, 10 55.43 Comments: NRC comment: Changed from a LOD-3 to a LOD-2 Revision 2 Facility: Waterford 3 Page 112 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 002 K6.02 Importance Rating 3.6 K/A Statement 002 Reactor Coolant, K6.02: Knowledge of the effect of a loss or malfunction on the following RCS components: RCP.

Proposed Question: RO 57 Rev: 2 To provide for detection and isolation of a Reactor Coolant leak through the Reactor Coolant Pump 1A seal cooler, the 1A RCP Seal Cooler (CC-679A/CC-6651A) isolation valves will close on a Component Cooling Water (CCW) return temperature of

____(1)____ ºF.

The 1A RCP Seal Cooler (CC-679A/CC-6651A) isolation valves interlock on high Component Cooling Water (CCW) return temperature ____(2)____ be manually overridden.

(1) (2)

A. 145 can B. 145 cannot C. 155 can D. 155 cannot Revision 2 Facility: Waterford 3 Page 113 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. CCW Seal return temperature of 145 ºF is the value at which the valves will remain open and not auto close again 100 seconds after isolation. Part 2 is correct.

B. Incorrect. CCW Seal return temperature of 145 ºF is the value at which the valves will remain open and not auto close again 100 seconds after isolation. This interlock can be overridden by taking the C/S to close and then back to open.

C. CORRECT: If CCW Seal return temperature reaches 155ºF, the CCW inlet and outlet valves to the seal coolers auto close. This interlock can be overridden by taking the C/S to close and then back to open.

D. Incorrect. Part 1 is correct. This interlock can be overridden by taking the C/S to close and then back to open.

Technical Reference(s): OP-901-130 page 5, 11 Rev. 11 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CC00 obj. 12 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8 55.43 Comments: NRC comment: Changed part 2 of the question by asking if the seal cooler isolations can or cannot by overridden on high CCW return temperature. This question tests system knowledge.

Revision 2 Facility: Waterford 3 Page 114 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 015 K4.07 Importance Rating 3.7 K/A Statement 015 Nuclear Instrumentation, K4.07: Knowledge of NIS design feature(s) and/or interlock(s) provide for the following: Permissives.

Proposed Question: RO 58 Rev: 2 Given:

A plant Shutdown is in progress in accordance with OP-010-005, Plant Shutdown At 1X10-4 % power and dropping, the CPC trips are (can be)___(1)___ bypassed and the High Log Power Trips are (can be) __(2)___ enabled.

(1) (2)

A. manually manually B. automatically manually C. automatically automatically D. manually automatically Revision 2 Facility: Waterford 3 Page 115 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Part 1 is correct. The design feature for the permissive on the NI log channel is that the High Log Power Trip is automatically enabled on the 1X10-4 bistable.

B. Incorrect. The CPC trips must be manually bypassed (by procedure) at this power.

The CPC trip bypass is automatically removed on the 1X10-4 bistable. The design feature for the permissive on the NI log channel is that the High Log Power Trip is automatically enabled on the 1X10-4 bistable.

C. Incorrect. The CPC trips must be manually bypassed (by procedure) at this power.

The CPC trip bypass is automatically removed on the 1X10-4 bistable. Part 2 is correct.

D. CORRECT: The design feature for the permissive on the NI log channel is that the High Log Power Trip is automatically enabled on the 1X10-4 bistable. The CPC trips must be manually bypassed (by procedure) at this power.

Technical Reference(s): OP-010-005 step 9.1.42 Rev. 328 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-ENI00 obj. 16 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 3 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 6 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 116 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 017 A4.02 Importance Rating 3.8 K/A Statement 017 In-Core Temperature Monitor, A4.02: Ability to manually operate and/or monitor in the control room: Temperature values used to determine RCS/RCP operation during inadequate core cooling (i.e., if applicable, average of five highest values).

Proposed Question: RO 59 Rev: 2 Given:

A Reactor trip occurred due to a loss of offsite power 20 minutes ago Pressurizer pressure is 2250 PSIA and slowly rising Tcold Loop 1A and 1B are 545°F and stable Thot Loop1 is 568°F and stable Tcold Loop 2A and 2B are 560°F and slowly rising Thot Loop 2 is 565°F and stable Representative CET temperature is 570°F and stable The minimum criteria for verifying single phase natural circulation is____(1)____. The crew should adjust feeding and steaming of Steam Generator __(2)__.

(1) (2)

A. NOT met 1 B. met 1 C. met 2 D. NOT met 2 Revision 2 Facility: Waterford 3 Page 117 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Wrong conclusion concerning natural circ, the minimum criteria is met Wrong SG, To get natural circulation to meet criteria in both loops Steam Generator 2 heat removal must be adjusted.

B. Incorrect. Correct conclusion concerning natural circ, the minimum criteria is met Wrong SG, To get natural circulation to meet criteria in both loops Steam Generator 2 heat removal must be adjusted.

C. CORRECT: Natural circulation is verified in EITHER loop. To get natural circulation to meet criteria in both loops Steam Generator 2 heat removal must be adjusted.

D. Incorrect. Wrong conclusion concerning natural circ, the minimum criteria is met Correct SG.

Technical Reference(s): OP-902-003 step 17 Rev. 10 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE05 obj. 2 (As available)

Question Source: Bank # RO27 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2012 RO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 2, 10 55.43 Comments: Changed the question due to the original question not meeting the K/A. Kept the same K/A.

Revision 2 Facility: Waterford 3 Page 118 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 033 A1.01 Importance Rating 2.7 K/A Statement 033 Spent Fuel Pool Cooling, A1.01: Ability to predict and/or monitor changes in parameters(to prevent exceeding design limits) associated with Spent Fuel Pool Cooling System operating the controls including: Spent fuel pool water level.

Proposed Question: RO 60 Rev: 2 Given:

The RAB watch reports lowering Spent Fuel Pool level The crew enters OP-901-513, Spent Fuel Pool Cooling Malfunction The makeup source to Spent Fuel Pool can be from the ____(1)____. The ATC will verify the Spent Fuel Pool Cooling Pumps trip at __(2)__ MSL.

(1) (2)

A. Condensate Storage Pool only 416 B. Refuel Water Storage Pool or 416 Condensate Storage Pool C. Refuel Water Storage Pool or 439 Condensate Storage Pool D. Condensate Storage Pool only 439 Revision 2 Facility: Waterford 3 Page 119 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. Makeup to the SFP is done frequently on shift. The makeup is always from the non-borated CSP to make-up for evaporated losses. However, the off-normal procedure allows makeup from either source. Part 2 is correct.

B. CORRECT: Makeup can be aligned to either the CSP or the RWSP. The Fuel Pool Cooling Pumps trip at a Spent Fuel Pool level of 416 MSL. The ATC will be required to trip the SFP cooling pumps if it does not happen at this level.

C. Incorrect. Part 1 is correct. Due to Single Point Vulnerability, an additional level switch is required (2/2) to trip the SFP Cooling Pumps. The level switch that was added sends its trip signal at 439 MSL. This will make up half the logic but not trip the SFP Cooling Pumps.

D. Incorrect. Makeup to the SFP is done frequently on shift. The makeup is always from the non-borated CSP to make-up for evaporated losses. However, the off-normal procedure allows makeup from either source. Due to Single Point Vulnerability, an additional level switch is required (2/2) to trip the SFP Cooling Pumps. The level switch that was added sends its trip signal at 439 MSL. This will make up half the logic but not trip the SFP Cooling Pumps Technical Reference(s): OP-901-513 page 4 and 6 Rev. 20 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO50 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 3 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 9, 10 55.43 Comment: NRC comment: Changed the crew will makeup to the in the stem to The makeup source to the Spent Fuel Pool can be from Revision 2 Facility: Waterford 3 Page 120 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 041 A3.02 Importance Rating 3.3 K/A Statement 041 Steam Dump/Turbine Bypass Control, A3.02: Ability to monitor automatic operation of the SDS, including: RCS Pressure, RCS Temperature, and reactor power.

Proposed Question: RO 61 Rev: 2 Given:

Plant is initially at 100% power RCS Tavg is 573 F Reactor Power Cutback system is out of service Reactor trip on Turbine trip is enabled Turbine trip occurs Which of the following describes the Steam Bypass Control system response immediately following the Turbine trip?

A. All valves quick open B. Only valves 1 through 5 quick open C. Only valves 1 through 3 quick open D. No valves quick open Revision 2 Facility: Waterford 3 Page 121 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. All SBCVs do not quick open on a reactor trip. SBC valve #6 quick open is blocked any time there is a reactor trip.

B. CORRECT: SBC valves 1-5 will quick open on a reactor trip with plant power at 100% power. SBC valve #6 quick open is blocked any time there is a reactor trip C. Incorrect. The quick open mode for the SBC system operates in two groups of 3 valves. Only one group of SBCVs quick opening will not handle a trip from 100%

power.

D. Incorrect. RCS Tave less than 561 F would block all SBCVs from quick opening.

The initial conditions in this event has Tave at 573 F.

Technical Reference(s): SD-SBC page 25 Rev. 10 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-SBC00 (As available)

Question Source: Bank # RO 63 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2012 RO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 122 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 045 A2.08 Importance Rating 2.8 K/A Statement 045 Main Turbine Generator, A2.08: Ability to (a) predict the impacts of the following malfunctions or operation on the MT/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Steam dumps are not cycling properly at low load, or stick open at higher load (isolate and use atmospheric reliefs when necessary).

Proposed Question: RO 62 Rev: 2 Given:

Plant is at 100% power One Steam Bypass Control Valve has failed open The crew has entered OP-901-221, Secondary System Transient The BOP will attempt to close the failed open Steam Bypass Control Valve from CP-1 by placing the Valve Mode (Permissive) Select Switch to the ____(1)____ position. If the Steam Bypass fails to close, the crew will reduce reactor power to less than 100% power by ____(2)____.

(1) (2)

A. OFF adjusting main turbine load B. MANUAL adjusting main turbine load C. OFF commencing direct boration to the RCS D. MANUAL commencing direct boration to the RCS Revision 2 Facility: Waterford 3 Page 123 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: To remove the permissive (to open) going to the failed open SBCS valve, the procedure directs the crew to take the permissive select switch to OFF.

OP-901-221 directs the crew to adjust Main Turbine load to reduce Reactor Power less than 100%.

B. Incorrect. Taking the Permissive switch to MANUAL will lock in a permissive to open the SBC Valve. Part 2 is correct.

C. Incorrect. Part 1 is correct. OP-901-221 directs the crew to adjust Main Turbine load to reduce Reactor Power less than 100% and to match Tave and Tref. Direct Boration to the RCS would reduce Reactor Power but will not assist in the excessive cooldown and would not be an immediate effect.

D. Incorrect. Taking the Permissive switch to MANUAL will lock in a permissive to open the SBC Valve. OP-901-221 directs the crew to adjust Main Turbine load to reduce Reactor Power less than 100%. Direct Boration to the RCS would reduce Reactor Power but will not assist in the excessive cooldown and would not be an immediate effect.

Technical Reference(s): OP-901-221 steps 4 and 6 Rev. 4 (Attach if not previously provided) SD-SBC page 24 Revision 10 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO50 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 2 10 CFR Part 55 Content: 55.41 7, 10 55.43 Comments: NRC comment: Changed to a LOD-2 from LOD-3 Revision 2 Facility: Waterford 3 Page 124 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 055 K3.01 Importance Rating 2.5 K/A Statement 055 Condenser Air Removal, K3.01: Knowledge of the effect that a loss or malfunction of the CARS will have on the following: Main condenser.

Proposed Question: RO 63 Rev: 2 Given:

Plant is at 100% power Condenser Vacuum Pump B has tripped To maintain a suction path for Condenser Air Evacuation PIG Rad Monitor (PRM-IRE-0004), the BOP will verify Condenser Vacuum Pump ____(1)____

is running. Condenser Vacuum Pumps are designed to automatically start at a Main Condenser Vacuum of ____(2)____ inches Hg.

(1) (2)

A. A 25 B. A 26 C. C 26 D. C 25 Revision 2 Facility: Waterford 3 Page 125 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Condenser Vacuum Pump B or C must be operating to maintain a suction path for Condenser Air Evacuation PIG Rad Monitor (PRM-IRE-0004). OP-901-220, Loss of Condenser Vacuum, requires the crew to commence a rapid plant down power at a Main Condenser Vacuum of 25 inches Hg.

B. Incorrect. Condenser Vacuum Pump B or C must be operating to maintain a suction path for Condenser Air Evacuation PIG Rad Monitor (PRM-IRE-0004). Part 2 is correct.

C. CORRECT: Condenser Vacuum Pump B or C must be operating to maintain a suction path for Condenser Air Evacuation PIG Rad Monitor (PRM-IRE-0004).

Standby Condenser Vacuum Pumps will auto start at 26 inches Hg on lowering Main Condenser Vacuum.

D. Incorrect. Part 1 is correct. OP-901-220, Loss of Condenser Vacuum, requires the crew to commence a rapid plant down power at a Main Condenser Vacuum of 25 inches Hg.

Technical Reference(s): OP-003-001 page 15 and 20 Rev. 20 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-AE00 obj. 6 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10, 11 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 126 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 071 K1.04 Importance Rating 2.7 K/A Statement 071 Waste Gas Disposal, K1.04: Knowledge of the physical connections and/or cause effect relationships between the Waste Gas Disposal System and the following systems: Station ventilation.

Proposed Question: RO 64 Rev: 2 Given:

The crew is scheduled to perform Section 6.4, Discharging Gas Decay Tank, per OP-007-003, Gaseous Waste Management Discharging ____(1)____ is the preferred method. The crew is required to secure the release if at least one RAB normal __(2)__ fan is not running.

(1) (2)

A. all three Gas Decay exhaust Tanks simultaneously B. all three Gas Decay supply Tanks simultaneously C. one Gas Decay Tank at a supply time D. one Gas Decay Tank at a exhaust time Revision 2 Facility: Waterford 3 Page 127 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: Discharging all GDTs simultaneously is the preferred method (CR 1291) due to the potential leakage of GDT inlet valves. At least one RAB Normal Exhaust Fan shall be operating while discharging. This guidance is in the caution statement before the release is commenced.

B. Incorrect. Part 1 is correct. At least one RAB Normal Exhaust Fan shall be operating while discharging. Integrated knowledge is required here because the applicant will need to know that the supply fan cannot run alone because it would trip if it does not see required exhaust flow.

C. Incorrect. Part 1 is correct. At least one RAB Normal Exhaust Fan shall be operating while discharging. Integrated knowledge is required here because the applicant will need to know that the supply fan cannot run alone because it would trip if it does not see required exhaust flow.

D. Incorrect. Discharging all GDTs simultaneously is the preferred method (CR 1291) due to the potential leakage of GDT inlet valves. Part 2 is correct.

Technical Reference(s): OP-007-003 Caution on page 14 Rev. 307 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-GWM00 obj. 9 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 12 55.43 Comments: Submitted for free review. No changes are required.

Revision 2 Facility: Waterford 3 Page 128 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 075 2.1.30 Importance Rating 4.4 K/A Statement 075 Circulating Water, 2.1.30: Ability to locate and operate components, including local controls.

Proposed Question: RO 65 Rev: 2 Given:

A Shutdown of the Circulating Water System is in progress Circulating Water Pumps C and D are operating The BOP takes the control switch for Circulating Water Pump C to stop. Circulating Water Pump D ____(1)____.

If required, manual operation of Circ Water Pump C or D Discharge Isolation Valves (CW-103C(D)) will be performed ___(2)___ .

(1) (2)

A. can be stopped after in the turbine generator building 100 seconds B. will trip immediately at the intake structure C. will trip immediately in the turbine generator building D. can be stopped after at the intake structure 100 seconds Revision 2 Facility: Waterford 3 Page 129 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect: When securing the first two Circ Water pumps (A and B in this case), a 100 second delay interlock is required before tripping them, the last two pumps secure simultaneously. The Circulating Water Pump discharge (inlet to the condenser) is located in the turbine generator building but is not the valve to be verified closed per OP-003-006.

B. CORRECT: With only two circulating water pumps running, stopping any one pump will cause both pumps to trip simultaneously. Circ Water pump discharge valves are located at the intake structure. The discharge valves should have closed automatically but W3 has OE requiring manual control of these valves.

C. Incorrect. Part 1 is correct. The Circulating Water Pump discharge (inlet to the condenser) is located in the turbine generator building but is not the valve to be verified closed per OP-003-006.

D. Incorrect. With only two circulating water pumps running, stopping any one pump will cause both pumps to trip simultaneously. Part 2 is correct.

Technical Reference(s): OP-003-006 page 65 Rev. 320 (Attach if not previously provided) OP-003-006 page 105 Rev. 320 (including version/revision number) SD-CW page 16 Rev. 17 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CW00 obj. 4 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 3 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 130 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 1 K/A # 2.1.3 Importance Rating 3.7 K/A Statement 2.1.3 Knowledge of shift or short-term relief turnover practices.

Proposed Question: RO 66 Rev: 2 A Reactor Operator has not stood an on-shift watch in the previous four weeks.

Per OI-042-000, Watch Station Processes, the minimum required Station Logs to be reviewed prior to turnover is ________ week(s).

A. one B. two C. three D. four Revision 2 Facility: Waterford 3 Page 131 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect: OI-042-000, Attachment 6.4 first bullet, states prior to turnover, review the Station Log (since the last shift or two weeks minimum). Not a subset because the question is asking what the procedure states.

B. CORRECT: OI-042-000, Attachment 6.4 first bullet, states prior to turnover, review the Station Log (since the last shift or two weeks minimum). In this case, the last shift stood was 4 weeks ago, therefore two weeks of logs must be reviewed.

C. Incorrect. OI-042-000, Attachment 6.4 first bullet, states prior to turnover, review the Station Log (since the last shift or two weeks minimum). Three weeks would be OK but is not the minimum required presented in OI-042-000.

D. Incorrect. Even though the RO has not stood a watch in four weeks, OI-042-000 only requires him/her to review two weeks of logs prior to turnover.

Technical Reference(s): OI-042-000 Attachment 6.4, rev. 45 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPA00 obj. 2 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 132 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 1 K/A # 2.1.19 Importance Rating 3.9 K/A Statement 2.1.19 Ability to use plant computers to evaluate system or component status.

Proposed Question: RO 67 Rev: 2 Per OP-903-001, Technical Specification Surveillance Logs, the Reactor Operator will verify the POWER DEPENDENT INSERTION LIMIT annunciator clear to ensure Group P and ____(1)____ CEAs are within their Transient Insertion Limits.

This annunciator receives its CEA position input from the CEA ___(2)___ .

(1) (2)

A. all regulating groups Reed Switch Position transmitters B. group 6 only Reed Switch Position transmitters C. group 6 only Pulse Counters D. all regulating groups Pulse Counters Revision 2 Facility: Waterford 3 Page 133 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Part 1 is correct. CEA RSPT are the input to CPC and CEAC indications.

The RSPTs are used to meet other TS CEA position requirements but do not input to the PDIL annunciator.

B. Incorrect. All regulating groups are an input to the POWER DEPENDENT INSERTION LIMIT annunciator. CEA RSPT are the input to CPC and CEAC indications. The RSPTs are used to meet other TS CEA position requirements but do not input to the PDIL annunciator.

C. Incorrect. All regulating groups are an input to the POWER DEPENDENT INSERTION LIMIT annunciator. Part 2 is correct.

D. CORRECT. The RO verifies POWER DEPENDENT INSERTION LIMIT annunciator clear every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per TS logs to ensure the Regulating Group and Group P are within their transient insertion limits. The CEA pulse counters (from the PMC) is the input into this annunciator.

Technical Reference(s): OP-903-001 page 25 Rev. 66 (Attach if not previously provided) OP-500-008 Att. 4.78 Rev. 28 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PMC00 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4 55.43 Comments: NRC comment. Changed question, original question did not meet the K/A.

Further review, changed Shutdown Banks in distractor part 1 to group 6 only instead of Shutdown Banks to make the distractors more plausible.

Revision 2 Facility: Waterford 3 Page 134 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 1 K/A # 2.1.44 Importance Rating 3.9 K/A Statement 2.1.44 Knowledge of RO duties in the control room during fuel handling, such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

Proposed Question: RO 68 Rev: 2 Given:

Plant is in a refueling outage Refueling Group is preparing to withdraw the first fuel assembly from the Reactor Vessel The Source Range Neutron Flux Monitors shall be operable and operating with (1) channel(s) operable with continuous visible indication in the control room and (2) channel(s) operable with audible indication in the containment and the control room.

(1) (2)

A. two one B. one one C. two two D. one two Revision 2 Facility: Waterford 3 Page 135 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: The RO will take Tech Spec logs on the Source range neutron flux monitors. They are verified operable by ensuring at least 2 channels operable with continuous visible indication in the control room and 1 channel operable with audible indication in the containment and control room. (TS 3.9.2)

B. Incorrect. Source range neutron flux monitors are verified operable by ensuring at least 2 channels operable with continuous visible indication in the control room.

C. Incorrect. TS 3.9.2 requires only 1 channel operable with audible indication in the containment and control room.

D. Incorrect. Source range neutron flux monitors are verified operable by ensuring at least 2 channels operable with continuous visible indication in the control room and 1 channel operable with audible indication in the containment and control room. (TS 3.9.2)

Technical Reference(s): TS 3.9.2 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-REQ04 obj. 2 (As available)

Question Source: Bank # RO 62 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2012 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2,6 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 136 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 2 K/A # 2.2.43 Importance Rating 3.0 K/A Statement 2.2.43 Knowledge of the process used to track inoperable alarms.

Proposed Question: RO 69 Rev: 2 Per OI-002-000, Annunciator and Control Room Instrumentation Status Control, annunciators that are disabled in conjunction with refuel outage windows ____(1)____

required to be documented in the Watchstation Deficiency Database. These outage annunciators will be identified by placing a __(2)__ dot on the annunciator window.

(1) (2) are not red are yellow are red are not yellow Revision 2 Facility: Waterford 3 Page 137 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: Per OI-002-000, Annunciator and Control Room Instrumentation Status Control, annunciators that are disabled in conjunction with refuel outage windows are not required to be documented in the Watchstation Deficiency Database. These annunciators are identified by placing a red dot on the annunciator window.

B. Incorrect. Per OI-002-000, Annunciator and Control Room Instrumentation Status Control, annunciators that are disabled in conjunction with refuel outage windows are not required to be documented in the Watchstation Deficiency Database. Malfunctioning annunciators are required to be entered. A yellow dot is used for annunciators that are malfunctioning.

C. Incorrect. Per OI-002-000, Annunciator and Control Room Instrumentation Status Control, annunciators that are disabled in conjunction with refuel outage windows are not required to be documented in the Watchstation Deficiency Database. Part 2 is correct D. Incorrect. Part 1 is correct. . A yellow dot is used for annunciators that are malfunctioning.

Technical Reference(s): OI-002-000 step 3.8, 5.1.5.3, 5.1.5.4 Rev. 308 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPA obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments: Changed the K/A and developed a new question because the previous question did not have plausible distractors.

Revision 2 Facility: Waterford 3 Page 138 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 2 K/A # 2.2.35 Importance Rating 3.6 K/A Statement 2.2.35 Ability to determine Technical Specification Mode of Operation.

Proposed Question: RO 70 Rev: 2 Given the following plant conditions:

RCS average temperature: 425 F All control rods: Fully inserted What is the current plant Mode as defined in Technical Specifications for these conditions?

A. MODE 5 B. MODE 4 C. MODE 3 D. MODE 2 Revision 2 Facility: Waterford 3 Page 139 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Mode 5 is defined as Keff<.95 and tavg<200F.

B. Incorrect. Mode 4 is defined as Keff <.99 and Tave between 200F and 350F.

C. CORRECT: Mode 3 is defined as Keff <.99, tavg >350F.

D. Incorrect. Shutdown Bank control rods would have to be withdrawn for Mode 2. W3 enters mode 2 when regulating groups are initially withdrawn or direct dilution has started after initial criticality.

Technical Reference(s): TS Definitions Table 1.2 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-TS00 (As available)

Question Source: Bank # RO66 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2007 RO Makeup Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 Comments: NRC Comment: Changed Mode 1 as a distractor to Mode 5 as a distractor.

More plausible with all rods inserted.

Revision 2 Facility: Waterford 3 Page 140 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 2 K/A # 2.2.39 Importance Rating 3.9 K/A Statement 2.2.39 Knowledge of less than or equal to one hour Technical Specification action statements for systems.

Proposed Question: RO 71 Rev: 2 In accordance with OP-100-014, Technical Specification and Technical Requirements Compliance, the crew is required to enter the appropriate cascading Technical Specifications upon declaring a(an) ___(1)____ inoperable.

The crew will be required to ____(2)____ within one hour.

(1) (2)

A. Emergency Diesel Generator complete OP-903-066, Electrical Breaker Alignment Check B. Component Cooling Water Train complete OP-903-066, Electrical Breaker Alignment Check C. Component Cooling Water Train verify Emergency Feedwater Pump AB operable D. Emergency Diesel Generator verify Emergency Feedwater Pump AB operable Revision 2 Facility: Waterford 3 Page 141 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect: Even though the EDG supplies power to various loads during an emergency, W3 does not cascade due to an EDG being inoperable. Part 2 is correct.

B. CORRECT: OP-100-014, Technical Specification and Technical Requirements Compliance designates systems that required cascading Tech Specs, CCW is one of those systems. The Electrical Breaker Lineup Check is required to be completed w/i 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in accordance with TS 3.8.1.1b.

C. Incorrect. Part 1 is correct. TS 3.8.1.1d (verify EFW Pump AB operable) is required during cascading Tech Specs but must be performed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> D. Incorrect. Even though the EDG supplies power to various loads during an emergency, W3 does not cascade due to an EDG being inoperable. TS 3.8.1.1d (verify EFW Pump AB operable) is required during cascading Tech Specs but must be performed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Technical Reference(s): OP-100-014 page 43 Revision 336 (Attach if not previously provided) TS 3.8.1.1 actions b and d (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CC00 obj. 9 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 3 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Revision 2 Facility: Waterford 3 Page 142 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 3 K/A # 2.3.13 Importance Rating 3.4 K/A Statement 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Proposed Question: RO 72 Rev: 2 Given:

The plant is at 10% Power A containment entry is desired Which of the following areas inside containment are forbidden from being entered?

A. Pressurizer Cubicle below +21 elevation B. +46 elevation at the Quench Tank C. Main Steam Line Crossovers on the +46 elevation D. RCS Cold Leg 1A penetration through the D Ring Wall Revision 2 Facility: Waterford 3 Page 143 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. This is an area known to have high radiation levels, but is not listed in HP-001-213 as being forbidden in MODE 1 (step 5.2.2). Also, not an area listed as needing RP Manager approval to enter (step 5.2.1).

B. Incorrect. This area is in close proximity to the Reactor Cavity but is a sufficient distance away that it is not forbidden (step 5.2.2), or need RP Manager approval to enter (step 5.2.1).

C. Incorrect. This is an exception to the requirement for obtaining RP Manager approval for going above the actual +46 elevation in Containment (step 5.2.1). It is not listed as forbidden (step 5.2.2).

D. CORRECT. Per HP-001-213, Step 5.2.2 and Attachment 7.1, this is a forbidden area in MODE 1. (> 5% RTP).

Technical Reference(s): HP-001-213, Rev. 305 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPA00 (As available)

Question Source: Bank # RO 71 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2011 RO NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 9,12 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 144 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 3 K/A # 2.3.15 Importance Rating 2.9 K/A Statement 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Proposed Question: RO 73 Rev: 2 Per OI-038-000, Emergency Operating Procedures Operations Expectations/Guidance, following a momentary loss of power or voltage dip, some radiation monitors needed for Emergency Plan may require ___________.

A. a restart of the sample pump B. verification of proper setpoint C. reset of their power supply D. local purge operation Revision 2 Facility: Waterford 3 Page 145 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: OI-038-000, step 5.3.4.1, states that some radiation monitors sample pumps needed for Emergency Plan may require restarting following a loss of power or voltage dips. Failure to restart sample pumps could delay the ED classification (W-3 specific issue)

B. Incorrect: OI-038-000, step 5.3.4.1, states that some radiation monitors sample pumps needed for Emergency Plan may require restarting following a loss of power or voltage dips. This distractor is plausible because it is an action that can be performed on a rad monitor per OP-004-001, Radiation Monitors C. Incorrect: OI-038-000, step 5.3.4.1, states that some radiation monitors sample pumps needed for Emergency Plan may require restarting following a loss of power or voltage dips. This distractor is plausible because it is feasible that a voltage dip could trip the local supply breaker.

D. Incorrect: OI-038-000, step 5.3.4.1, states that some radiation monitors sample pumps needed for Emergency Plan may require restarting following a loss of power or voltage dips. This distractor is plausible because it is an action that can be performed on a rad monitor per OP-004-001, Radiation Monitors Technical Reference(s): OI-038-000 step 5.3.4.1 Rev. 13 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE01 obj. 4 (As available)

Question Source: Bank # RO 72 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014 NRC RO Exam Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10, 11 55.43 Revision 2 Facility: Waterford 3 Page 146 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 4 K/A # 2.4.8 Importance Rating 3.8 K/A Statement 2.4.8 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

Proposed Question: RO 74 Rev: 2 Which of the following is prohibited by OP-100-017, Emergency Operating Procedure Implementation Guide?

A. Simultaneous performance of more than one safety function concurrently while in the Functional Recovery Procedure B. Simultaneous performance of an Optimal Recovery Procedure and an Off-Normal Procedure C. Simultaneous performance of more than one Optimal Recovery Procedure D. Simultaneous performance of an Optimal Recovery Procedure and a System Operating Procedure Revision 2 Facility: Waterford 3 Page 147 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. The simultaneous performance of more than one Safety Function concurrently while in the Functional Recovery procedure is allowed per OP-100-016, step 5.16.4.

B. Incorrect. Simultaneous performance of an Optimal Recovery Procedure and an off-normal procedure is allowed.

C. CORRECT: Step 5.11.1 of OP-100-017, Emergency Operating Procedure Implementation Guide, states that simultaneous performance of more than one Optimal Recovery Procedure is prohibited.

D. Incorrect. Simultaneous performance of an Optimal Recovery Procedure and a system operating procedure is allowed.

Technical Reference(s): OP-100-017 step 5.11.1, and 5.16.4 Rev.4 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE01 obj. 4 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 148 of 150

2017 NRC Exam RO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 4 K/A # 2.4.25 Importance Rating 3.3 K/A Statement 2.4.25 Knowledge of fire protection procedures.

Proposed Question: RO 75 Rev: 2 A site Fire Brigade of at least __(1)__ members shall be maintained on site at all times.

The fire brigade composition may be less than the minimum requirement for a period of time not to exceed a maximum of ___(2)___ hour(s).

(1) (2)

A. four one B. four two C. five one D. five two Revision 2 Facility: Waterford 3 Page 149 of 150

2017 NRC Exam RO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. The applicant will select four fire brigade members if he does not include the fire brigade leader. The fire brigade limit of 5 is inclusive of the fire brigade leader. The fire brigade composition may be less than the minimum requirement for a period of time not to exceed a maximum of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

B. Incorrect. The applicant will select four fire brigade members if he does not include the fire brigade leader. The fire brigade limit of 5 is inclusive of the fire brigade leader. Part 2 is correct.

C. Incorrect. Part 1 is correct. The fire brigade composition may be less than the minimum requirement for a period of time not to exceed a maximum of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

D. CORRECT: A site Fire Brigade of at least five members shall be maintained on site at all times. The fire brigade composition may be less than the minimum requirement for a period of time not to exceed a maximum of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Technical Reference(s): FP-001-020 step 3.1 Rev. 311 (Attach if not previously provided) OI-042-000 page 22 Rev. 45 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPA00 obj. 2 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

Revision 2 Facility: Waterford 3 Page 150 of 150

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: April 5, 2017 Facility/Unit: Waterford 3 Region: IV Reactor Type: CE Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with a 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.

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

Applicants Signature Results RO/SRO-Only/Total Examination Values 75 / 25 / 100 Points Applicants Score / / Points Applicants Grade / / Percent

2017 NRC Written Examination Waterford 3 Senior Reactor Operator

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2017 NRC Written Examination Waterford 3 Senior Reactor Operator

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2017 NRC Exam SRO Written Exam SRO1 Given:

A Small Break LOCA has occurred SIAS, CIAS, and MSIS are present The crew is performing actions of OP-902-002, Loss of Coolant Accident Recovery Procedure After the LOCA is isolated, the ATC informs the CRS that the 200°F subcooled line of the RCS Pressure and Temperature Curve (PT curve) is being exceeded.

To restore the RCS to within the limits of the PT curve, the CRS will direct the crew to take actions to lower RCS ____(1)____.

After the RCS is restored to within the limits of the PT curve, the crew will maintain the RCS within the curve by re-energizing the 32A and 32B busses in accordance with OP-902-009, Standard Appendices, Appendix ______(2)______.

(1) (2)

A. temperature 12, Electrical Restoration B. pressure 12, Electrical Restoration C. pressure 25, Restore Pressurizer Heater Control D. temperature 25, Restore Pressurizer Heater Control Facility: Waterford 3 Page 1 of 25

2017 NRC Exam SRO Written Exam SRO 2 Given:

Shutdown Cooling Trains A and B are in service An Inadvertent RAS has occurred The crew will enter ____(1)____. The crew will first ______(2)______.

(1) (2)

A. OP-901-504, Inadvertent ESFAS restart LPSI pumps Actuation only B. OP-901-504, Inadvertent ESFAS reset RAS initiation Actuation only and actuation relays C. OP-901-131, Shutdown Cooling reset RAS initiation Malfunction and OP-901-504, and actuation relays Inadvertent ESFAS Actuation D. OP-901-131, Shutdown Cooling restart LPSI pumps Malfunction and OP-901-504, Inadvertent ESFAS Actuation Facility: Waterford 3 Page 2 of 25

2017 NRC Exam SRO Written Exam SRO 3 Given:

The ATC reports that RCS Tcold is dropping rapidly A MSIS, SIAS, and CIAS has occurred NAO reports steam issuing from the RCA -35 area Following the ESFAS actuations, the BOP reports that both Steam Generator Pressures are 500 psia and dropping.

The crew will go to ____(1)____ Recovery Procedure. The next action the CRS will direct is to ____(2)____.

(1) (2)

A. OP-902-008, Functional close MS-401A and MS-401B, Pump AB TURB STM Supplies B. OP-902-008, Functional stabilize RCS temperature within the PT curves C. OP-902-004, Excess Steam close MS-401A and MS-401B, Demand Pump AB TURB STM Supplies D. OP-902-004, Excess Steam stabilize RCS temperature within Demand the PT curves Facility: Waterford 3 Page 3 of 25

2017 NRC Exam SRO Written Exam SRO 4 Given:

A Station Blackout has occurred The CRS has been informed that restoration of one Emergency Diesel Generator is expected in five hours and the duration for restoration of offsite power is unknown The CRS will enter ____(1)____.

If required, the determination to perform deep load shedding of station batteries must occur within ____(2)____ hour(s) of the onset of the Station Blackout.

(1) (2)

A. OP-902-005, Station Blackout one Recovery Procedure only B. OP-902-005, Station Blackout two Recovery Procedure only C. OP-902-005, Station Blackout two Recovery Procedure and commence FIG-001, Extended Loss of AC Power D. OP-902-005, Station Blackout one Recovery Procedure and commence FIG-001, Extended Loss of AC Power Facility: Waterford 3 Page 4 of 25

2017 NRC Exam SRO Written Exam SRO 5 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 will direct the crew to first ____(1)____.

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

(1) (2)

A. vent the Main Generator IAW OP- 2 902-009, Attachment 33-B, Generator Auxiliary Operations-LOOP B. secure the Air Side Seal Oil 1 Backup Pump IAW OP-902-009, Attachment 33-B, Generator Auxiliary Operations-LOOP C. vent the Main Generator IAW OP- 1 901-313, section E4, Loss of 125 Volt DC Bus TGB-DC D. secure the Air Side Seal Oil 2 Backup Pump IAW OP-901-313, section E4, Loss of 125 Volt DC Bus TGB-DC Facility: Waterford 3 Page 5 of 25

2017 NRC Exam SRO Written Exam SRO 6 Initial plant conditions:

100% power Battery Charger A1 is tagged out Startup Channel 1 is in Primary Given:

ALL ESFAS actuation annunciators for Train A & B are in alarm Startup Channel 1 energizes CEAC 2 de-energizes All ESFAS trip path lights on CP-7A and 7C extinguish The SUPS will be addressed using ____(1)____.

After the given conditions are addressed, the affected SUPS is fully restored and placed in a normal alignment. Then the Normal AC input breaker trips open.

The SUPS Rectifier or Battery Charger A1 must be restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to prevent

____(2)____.

(1) (2)

A. OP-901-312,Loss of Vital Bus, battery discharge section E1 Loss of SUPS A1 (PDP MA)

B. OP-901-312,Loss of Vital Bus, damage to the rectifier section E1 Loss of SUPS A1 assembly (PDP MA)

C. OP-901-312,Loss of Vital Bus, battery discharge section E3 Loss of SUPS MC D. OP-901-312,Loss of Vital Bus, damage to the rectifier section E3 Loss of SUPS MC assembly Facility: Waterford 3 Page 6 of 25

2017 NRC Exam SRO Written Exam SRO 7 Given:

Reactor startup is in progress in accordance with OP-010-003, Plant Startup CEAs are in Manual Sequential CEA group positions are:

o Shutdown Banks A & B are All Rods Out o Reg Groups 1-3 are All Rods Out o Reg Group 4 is at 100 inches o Reg Groups 5 and 6 are All Rods In o Group P is at 50 inches Count rate data shows 6 doublings have been achieved based on all Log Power channels. The Reactor Engineer reports criticality is expected in the next 50 inch pull based on 1/M Plot.

The CRS will direct ___(1)___ and direct the ATC to ___(2)___.

(1) (2)

A. a reactor trip direct borate until RCS boron concentration is 20 PPM greater than critical boron concentration B. a reactor trip emergency borate IAW OP-901-103, Emergency Boration, until COLR requirements are met C. full insertion of all Reg Group emergency borate IAW OP-901-103, and Group P CEAs using the Emergency Boration, until COLR shim switch requirements are met D. full insertion of all Reg Group direct borate until RCS boron and Group P CEAs using the concentration is 20 PPM greater than shim switch critical boron concentration Facility: Waterford 3 Page 7 of 25

2017 NRC Exam SRO Written Exam SRO 8 Given:

The crew has entered OP-902-008, Safety Function Recovery Procedure A Loss of offsite power has occurred and neither Emergency Diesel Generator (EDG) is available The Temporary Emergency Diesel Generator (TED) is supplying the 3A bus In regards to Attachments 7-A, 7-B, and 7-D, the CRS is required to implement A. only Attachment 7-D, Process Analog Control Cabinet Doors, to open cabinet doors B. only Attachment 7-B, Switchgear B Removable Loads, to strip loads C. Attachment 7-A, Switchgear A Removable Loads and Attachment 7-B, Switchgear B Removable Loads, to strip loads D. Attachment 7-B, Switchgear B Removable Loads, to strip loads and Attachment 7-D, Process Analog Control Cabinet Doors to open cabinet doors Facility: Waterford 3 Page 8 of 25

2017 NRC Exam SRO Written Exam SRO 9 OP-010-006 Attachment 9.23, Loss of Refuel Cavity Water Level Guidelines, states that the most preferred location to place a fuel assembly in transit during a Refuel Cavity leak is the ________.

A. Reactor Vessel B. Upender baskets (place upender horizontal)

C. Fuel Assembly Storage Rack in the Refuel Cavity D. Cavity deep end, with assembly suspended from the Refueling Machine Facility: Waterford 3 Page 9 of 25

2017 NRC Exam SRO Written Exam SRO 10 Given:

The fire brigade leader reports a fire in the Relay Room that requires activation of the Fire Brigade team.

Within 20 minutes of the fire, the CRS will direct the crew to perform actions to electrically lockout the Reactor Coolant Pumps because the location of this fire could affect ____(1)____. This step will be performed in accordance with____(2)____.

(1) (2)

A. the backup overcurrent OP-901-524, Fires in areas protection for the RCPs affecting Safe Shutdown, Section E12 RAB 7A B. the backup overcurrent OP-901-502, Evacuation of protection for the RCPs Control Room and Subsequent Plant Shutdown, Section E0 Control Room Evacuation C. components which provide OP-901-524, Fires in areas cooling to the RCP seals affecting Safe Shutdown, Section E12 RAB 7A D. components which provide OP-901-502, Evacuation of cooling to the RCP seals Control Room and Subsequent Plant Shutdown, Section E0 Control Room Evacuation Facility: Waterford 3 Page 10 of 25

2017 NRC Exam SRO Written Exam SRO 11 Given:

Reactor Power is 100% with Tavg and Tref matched Pressurizer Level Channel X is 40% and slowly lowering Pressurizer Level Channel Y is 60% and slowly rising Channel X is selected for service The crew has entered OP-901-110, Pressurizer Level Control Malfunction The CVCS system configuration will be changed by ______(1)_______.

The crew will implement section _______(2)_______.

(1) (2)

A. both backup charging pumps E1, Pressurizer Level Control Channel starting Malfunction B. letdown flow rising to 126 gpm E1, Pressurizer Level Control Channel Malfunction C. both backup charging pumps E3, Pressurizer Level Controller Malfunction starting D. letdown flow rising to 126 gpm E3, Pressurizer Level Controller Malfunction Facility: Waterford 3 Page 11 of 25

2017 NRC Exam SRO Written Exam SRO 12 Given:

A Tornado Watch is in affect for St. Charles Parish The crew has entered OP-901-521, Severe Weather and Flooding Due to the changing weather conditions, the CRS will verify additional operability requirements are met for the Dry Cooling Tower (DCT) fans by verifying DCT fans

___(1)___ are operable. The Dry Cooling Tower fans are considered operable if their control switches are in the ___(2)___ position(s).

(1) (2)

A. 7 through 15 auto only B. 1 through 9 auto only C. 1 through 9 auto or fast D. 7 through 15 auto or fast Facility: Waterford 3 Page 12 of 25

2017 NRC Exam SRO Written Exam SRO 13 The reactor is operating at 100% power when an inadvertent CSAS occurs. After 5 seconds the reactor trips due to a trip of RCP 1A. The CRS should direct the crew to perform the following:

A. Enter OP-901-504, Inadvertent ESFAS Actuation, place both Containment Spray pumps in stop, and restore CCW to the RCPs concurrently with the performance of OP-902-000, Standard Post Trip Actions. Then transition to OP-902-001, Reactor Trip Recovery.

B. Restore CCW to the RCPs during the performance of OP-902-000, Standard Post Trip Actions. Then transition to OP-902-008, Functional Recovery and terminate Containment Spray.

C. Perform OP-902-000, Standard Post Trip Actions. Then transition to OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery, concurrent with OP-901-504, Inadvertent ESFAS Actuation and place both Containment Spray pumps in stop.

D. Restore CCW to the RCPs during the performance of OP-902-000, Standard Post Trip Actions. Then transition to OP-902-001, Reactor Trip Recovery, and terminate Containment Spray using OP-009-001, Containment Spray.

Facility: Waterford 3 Page 13 of 25

2017 NRC Exam SRO Written Exam SRO 14 Given:

Emergency Diesel Generator (EDG) A is inoperable due to unplanned maintenance 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> into the unplanned EDG A outage, the Temporary Emergency Diesel (TED) Generator is verified available and aligned as a backup for EDG A 8 days (192 hours0.00222 days <br />0.0533 hours <br />3.174603e-4 weeks <br />7.3056e-5 months <br />) from when EDG A first became inoperable, the Temporary Emergency Diesel (TED) Generator becomes unavailable and cannot be restored Per TS 3.8.1.1, from the time the Temporary Emergency Diesel (TED) Generator becomes unavailable, the time limit for restoring Emergency Diesel Generator A to service is ________ hours.

A. 28 B. 48 C. 68 D. 72 Facility: Waterford 3 Page 14 of 25

2017 NRC Exam SRO Written Exam SRO 15 Given:

LOCA occurred 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago Crew is performing OP-902-002, Loss of Coolant Accident Recovery Recirculation Actuation Signal has occurred, and required actions have been taken RCS is 15°F subcooled; CET temperatures are rising very slowly QSPDS RVLMS levels 1-6 indicates void BOP notes that HPSI A and B pumps cold leg flow has dropped off slowly with discharge pressure rising and no oscillations Containment Spray Pumps A and B are running with flow ~ 2000 GPM each train and stable The CRS should ______(1)______. The conditions given indicate _____(2)_____.

(1) (2)

A. perform Appendix 15 Hot and the SI Sump Strainers are starting to Cold Leg Injection clog from debris collection B. secure one HPSI pump and verify the SI Sump Strainers are starting to Attachment 2-E HPSI Flow Curve clog from debris collection is met C. secure one HPSI pump and verify core flow blockage is starting to occur Attachment 2-E HPSI Flow Curve due to boron precipitation is met D. perform Appendix 15 Hot and core flow blockage is starting to occur Cold Leg Injection due to boron precipitation Facility: Waterford 3 Page 15 of 25

2017 NRC Exam SRO Written Exam SRO 16 Given:

Power is 100%

The PMC has failed and the actions of OP-901-501, PMC or Core Operating Limit Supervisory System Malfunction, are being performed As stated in TS surveillance requirement 4.1.3.2, the crew will verify that at least two of the three CEA position indicator channels are operable by verifying for the same CEA, the position indicator channels agree within ____(1)____ inches of each other.

TS 3.1.3.2 Position Indicator Channels-Operating, states, with a maximum of one CEA per CEA group having only one of its CEA position indicator channels operable, operation may continue provided the CEA group(s) with the inoperable position indicator(s) _____(2)_____.

(1) (2)

A. seven is maintained fully withdrawn B. seven CEA position(s) is documented every four hours C. five CEA position(s) is documented every four hours D. five is maintained fully withdrawn Facility: Waterford 3 Page 16 of 25

2017 NRC Exam SRO Written Exam SRO 17 Given:

A Plant Startup from a refueling outage is in progress in accordance with OP-010-003 Prior to establishing Containment Integrity for Mode 4, the crew will demonstrate operability of each Containment Purge Supply and Exhaust Isolation valve by verifying the mechanical stops are ____(1)____. When mode 4 is established, the cumulative hours these valves are opened will be tracked using the attachment in _____(2)_____.

(1) (2)

A. removed OP-903-001, Technical Specification Surveillance Logs B. installed OP-903-001, Technical Specification Surveillance Logs C. installed OP-100-014, Technical Specification and Technical Requirements Compliance D. removed OP-100-014, Technical Specification and Technical Requirements Compliance Facility: Waterford 3 Page 17 of 25

2017 NRC Exam SRO Written Exam SRO 18 Given:

A Spent Fuel Pool leak is in progress The crew has entered OP-901-513, Spent Fuel Pool Cooling Malfunction NAO reports that Spent Fuel Pool level instruments Channel 1 and 2 located on the Q-Deck read 22.2 feet The requirements of TS 3.9.11 WATER LEVEL-SPENT FUEL POOL are ____(1)____.

TS 3.9.11 basis states that in the event of a rupture of an irradiated fuel assembly, sufficient water depth is available such that_____(2)_____.

(1) (2)

A. met sufficient cooling capacity is maintained B. met iodine released is within limits C. not met sufficient cooling capacity is maintained D. not met iodine released is within limits Facility: Waterford 3 Page 18 of 25

2017 NRC Exam SRO Written Exam SRO 19 OI-042-000, Watch Station Processes, states that no more than _____(1)_______

personnel on a shift should be absent at the same time and at least _____(2)______

NAOs on a shift should be a normal member of that shifts crew.

(1) (2)

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

2017 NRC Exam SRO Written Exam SRO 20 Regarding EOP usage, to verify the RCS is not water solid with Pressurizer level indicating 100%, the crew will verify that ____(1)____ . If the RCS is considered water solid, the crew will _____(2)_____.

(1) (2)

A. RCS inventory or temperature remain in the selected Optimal Recovery changes do not produce Procedure and control RCS temperature severe pressure responses and throttle RCS makeup B. RCS inventory or temperature transition to the Functional Recovery changes do not produce Procedure and establish a bubble in the severe pressure responses Pressurizer C. Reactor vessel plenum level is remain in the selected Optimal Recovery less than 100% Procedure and control RCS temperature and throttle RCS makeup D. Reactor vessel plenum level is transition to the Functional Recovery less than 100% Procedure and establish a bubble in the Pressurizer Facility: Waterford 3 Page 20 of 25

2017 NRC Exam SRO Written Exam SRO 21 When clearing the Main Steam Administrative (MS-Admin) tagout, the ____(1)____ must sign off as the tagout holder. The (MS-Admin) tagout must be cleared ____(2)____ all tagouts that use the MS-ADMIN tagout are cleared.

(1) (2)

A. outage manager before B. designated operations after supervisor C. outage manager after D. designated operations before supervisor Facility: Waterford 3 Page 21 of 25

2017 NRC Exam SRO Written Exam SRO 22 Today is April 5, 2017, and the operating crew has determined that a required monthly technical specification surveillance was last performed on March 3, 2017. Technical Specifications require that ____(1)____.

A. the appropriate TS action statement be entered immediately B. the surveillance be performed by April 10, 2017 C. the surveillance be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> D. the plant evaluate risk and perform the surveillance by May 6, 2017 Facility: Waterford 3 Page 22 of 25

2017 NRC Exam SRO Written Exam SRO 23 Which of the following are required actions per TRM 3.3.3.10, Radioactive Liquid Effluent, to release a Boric Acid or Waste Condensate Tank with its associated discharge Radiation Monitor Inoperable?

A. Ensure release rate calculations have been verified by two technically qualified personnel prior to the discharge and the discharge valve lineup is independently verified.

B. Ensure release rate calculations have been verified by two technically qualified personnel prior to the discharge and obtain grab samples every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during discharge.

C. Calculate release flow rate every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the discharge and the discharge valve lineup is independently verified.

D. Calculate release flow rate every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the discharge and obtain grab samples every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during discharge.

Facility: Waterford 3 Page 23 of 25

2017 NRC Exam SRO Written Exam SRO 24 Given:

The CRS is prioritizing safety functions in accordance with OP-902-008, Functional Recovery Procedure A SIAS, CIAS, MSIS and CSAS are present Two CEAs have failed to insert The ATC reports that Reactor Power is 10-5 % and dropping The CRS is evaluating the Reactivity Control Safety Function

____(1)____ safety function acceptance criteria are met. The CRS will implement success path _____(2)_____ for Reactivity control.

(1) (2)

A. Only RC-1 RC-1 B. Only RC-1 RC-2 C. RC-1 and RC-2 RC-2 D. RC-1 and RC-2 RC-1 Facility: Waterford 3 Page 24 of 25

2017 NRC Exam SRO Written Exam SRO 25 Given:

An valid automatic reactor trip signal has failed to trip the reactor The manual reactor trip pushbuttons and Diversified Reactor Trip System (DRTS) also failed to trip the reactor The BOP has tripped the reactor by de-energizing the Motor Generator Sets The Emergency Planning classification for this event is a(n) ____(1)____. The NRC shall be notified no later than _____(2)_____ of declaring the emergency.

(1) (2)

A. Alert one hour B. Alert 15 minutes C. Site Area Emergency one hour D. Site Area Emergency 15 minutes Facility: Waterford 3 Page 25 of 25

Reference Handout for question SRO 25 redacted due to potential SUNSI concerns.

2017 NRC Written Examination Waterford 3 Reactor Operator and Senior Reactor Operator

1. C 26. C

2. A 27. A

3. A 28. C

4. B 29. A

5. C 30. D

6. D 31. B

7. C 32. D

8. C 33. A

9. D 34. D

10. B 35. A

11. A 36. B

12. B 37. C

13. B 38. D

14. D 39. B

15. D 40. D

16. B 41. C

17. A 42. B

18. A 43. C

19. D 44. A

20. B 45. B

21. B 46. C

22. C 47. C

23. A 48. A

24. D 49. C

25. B 50. D Page 1 of 2

2017 NRC Written Examination Waterford 3 Reactor Operator and Senior Reactor Operator

51. D S1. C

52. D S2. D

53. C S3. C

54. C S4. D

55. D S5. A

56. A S6. C

57. C S7. B

58. D S8. D

59. C S9. A

60. B S10. C

61. B S11. A

62. A S12. D

63. C S13. A

64. A S14. B

65. B S15. D

66. B S16. D

67. D S17. B

68. A S18. D

69. A S19. A

70. C S20. A

71. B S21. B

72. D S22. B

73. A S23. A

74. C S24. C

75. D S25. C Page 2 of 2

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000009 EA2.14 Importance Rating 4.4 K/A Statement 009 Small Break LOCA, EA2.14: Ability to determine or interpret the following as they apply to the Small Break LOCA: Actions to be taken if PTS limits are violated Proposed Question: SRO 1 (Q76) Rev: 2 Given:

A Small Break LOCA has occurred SIAS, CIAS, and MSIS are present The crew is performing actions of OP-902-002, Loss of Coolant Accident Recovery Procedure After the LOCA is isolated, the ATC informs the CRS that the 200°F subcooled line of the RCS Pressure and Temperature Curve (PT curve) is being exceeded.

To restore the RCS to within the limits of the PT curve, the CRS will direct the crew to take actions to lower RCS ____(1)____.

After the RCS is restored to within the limits of the PT curve, the crew will maintain the RCS within the curve by re-energizing the 32A and 32B busses in accordance with OP-902-009, Standard Appendices, Appendix ______(2)______.

(1) (2)

A. temperature 12, Electrical Restoration B. pressure 12, Electrical Restoration C. pressure 25, Restore Pressurizer Heater Control D. temperature 25, Restore Pressurizer Heater Control Revision 2 Facility: Waterford 3 Page 1 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. The applicant is required to know exceeding the upper limit of the PT curve means that the RCS is over sub-cooled. OP-902-002 step 30 requires the crew to stop the cooldown and lower pressure. Appendix 12 has various sections for restoring electrical power, but guidance to close in the 32 feeder breakers with a SIAS is located in Appendix 25 B. Incorrect. Part 1 is correct. Appendix 12 has various sections for restoring electrical power, but guidance to close in the 32 feeder breakers with a SIAS is located in Appendix 25.

C. CORRECT: If the upper limit of the PT curve is exceeded, the concern is PTS. To restore the RCS to within limits, the crew will need to lower RCS pressure. OP-902-002 step 30 directs the crew to Appendix 25, Restore Pressurizer Heater Control guidance for energizing the 32A(B) busses and restoring pressurizer heaters.

D. Incorrect. The applicant is required to know exceeding the upper limit of the PT curve means that the RCS is over sub-cooled. OP-902-002 step 30 requires the crew to stop the cooldown and lower RCS pressure. Part 2 is correct.

Technical Reference(s): OP-902-002 step 30 Rev. 20 (Attach if not previously provided) OP-902-009 Att. 2 and 25 Rev. 315 (including version/revision number) TGOP-902-002 Step 30 Rev. 19 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE02 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 55.43 5 Comments: NRC Comment: Changed part 2 of the question to state After the RCS is restored to within the limits of the PT curve, the crew will maintain the RCS within the curve by. This will create a smooth transition between the crew being out of the curve to maintaining the RCS within the curve.

Revision 2 Facility: Waterford 3 Page 2 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000025 2.4.9 Importance Rating 4.2 K/A Statement 025 Loss of RHR System, 2.4.9: Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

Proposed Question: SRO 2 (Q77) Rev: 2 Given:

Shutdown Cooling Trains A and B are in service An Inadvertent RAS has occurred The crew will enter ____(1)____. The crew will first ______(2)______.

(1) (2)

A. OP-901-504, Inadvertent ESFAS restart LPSI pumps Actuation only B. OP-901-504, Inadvertent ESFAS reset RAS initiation Actuation only and actuation relays C. OP-901-131, Shutdown Cooling reset RAS initiation Malfunction and OP-901-504, and actuation relays Inadvertent ESFAS Actuation D. OP-901-131, Shutdown Cooling restart LPSI pumps Malfunction and OP-901-504, Inadvertent ESFAS Actuation Revision 2 Facility: Waterford 3 Page 3 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. The guidance to restart LPSI pumps is located in OP-901-504. OP-901-504 directs the crew to perform OP-901-131 concurrently. Part 2 is correct.

B. The guidance to restart LPSI pumps is located in OP-901-504. OP-901-504 directs the crew to perform OP-901-131 concurrently. LPSI pumps can be restarted 1 second after an RAS signal. OP-901-504 directs the crew to reset RAS initiation and actuation relays after starting LPSI pumps so that SI-602A(B) can be closed.

C. Incorrect. Part 1 is correct. LPSI pumps can be restarted 1 second after an RAS signal. OP-901-504 directs the crew to reset RAS initiation and actuation relays after starting LPSI pumps so that SI-602A(B) can be closed.

D. CORRECT: A loss of Shutdown Cooling flow has occurred due to both LPSI pumps tripping on an Inadvertent RAS. The guidance to restart LPSI pumps is located in OP-901-504. OP-901-504 directs the crew to perform OP-901-131 concurrently. LPSI pumps can be restarted 1 second after an RAS signal.

Technical Reference(s): OP-901-131 section E2 Rev. 304 (Attach if not previously provided) OP-901-504 section E3 Rev. 10 (including version/revision number) SD-SI page 27 Rev. 15 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO50 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 2 10 CFR Part 55 Content: 55.41 55.43 5 Comments: Due to NRC comment. Added only to the end of distractor B. Changed LOD-3 to LOD-2.

Revision 2 Facility: Waterford 3 Page 4 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000040 AA2.01 Importance Rating 4.7 K/A Statement 040 Steam Line Rupture, AA2.01: Ability to determine and interpret the following as they apply to the Steam Line Rupture: Occurrence and location of a steam line rupture from pressure and flow indications Proposed Question: SRO 3 (Q78) Rev: 2 Given:

The ATC reports that RCS Tcold is dropping rapidly A MSIS, SIAS, and CIAS has occurred NAO reports steam issuing from the RCA -35 area Following the ESFAS actuations, the BOP reports that both Steam Generator Pressures are 500 psia and dropping.

The crew will go to ____(1)____ Recovery Procedure. The next action the CRS will direct is to ____(2)____.

(1) (2)

A. OP-902-008, Functional close MS-401A and MS-401B, Pump AB TURB STM Supplies B. OP-902-008, Functional stabilize RCS temperature within the PT curves C. OP-902-004, Excess Steam close MS-401A and MS-401B, Demand Pump AB TURB STM Supplies D. OP-902-004, Excess Steam stabilize RCS temperature within Demand the PT curves Revision 2 Facility: Waterford 3 Page 5 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. The MSIS did not isolate the leak. The applicant could determine that two events are going on or parameters do not support an optimal recovery procedure entry; either case would put the crew into OP-902-008. The applicant determines both S/Gs are not inoperable and the leak is on the common line due to steam issuing in the RCA. Part 2 is correct.

B. Incorrect. The MSIS did not isolate the leak to any S/G. The applicant could determine that two events are going on or parameters do not support an optimal recovery procedure entry; either case would put the crew into OP-902-008. The applicant can determine that both S/G are not inoperable and the leak is on the common line due to steam issuing in the RCA.

Stabilize RCS temperature within the PT curves is a step that must be performed but will not be performed next because both S/G pressures are still dropping.

C. CORRECT: The MSIS should have isolated the steam leak or contained the steam leak to one SG, unless the leak is in the common line going to EFW Pump AB. With SG pressures still dropping and equal to each other, OP-902-004 directs the crew to close MS-401A and B to attempt to isolate the leak. The SRO must determine that even though he will not be meeting the SFSC for one operable SG in OP-902-004, the optimal is the correct one to enter because the reason for not meeting the safety function (RCS heat removal) is known and an immediate response can be performed to satisfy the safety function (OP-100-017 step 5.6.2).

D. Incorrect. Part 1 is correct. Stabilize RCS temperature within the PT curves must be performed but will not be performed next because both S/G pressures are still dropping.

Technical Reference(s): OP-902-004 step 15 and step 18 Rev. 16 (Attach if not previously provided) OP-100-017 step 5.6.2 Rev. 5 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE04 obj. 7 and 8 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 4 10 CFR Part 55 Content: 55.41 55.43 5 Comments: Free review question. Changed the stem to give indications that an ESD is occurring.

This meets the part of the K/A for determining the occurrence of an ESD. Added NAO reports that steam issuing from the RCA so that it can be determined that the steam leak is not occurring upstream of the MSIVs and can be isolated.

Revision 2 Facility: Waterford 3 Page 6 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000055 2.4.6 Importance Rating 4.7 K/A Statement 055 Station Blackout, 2.4.6: Knowledge of EOP mitigation strategies.

Proposed Question: SRO 4 (Q79) Rev: 2 Given:

A Station Blackout has occurred The CRS has been informed that restoration of one Emergency Diesel Generator is expected in five hours and the duration for restoration of offsite power is unknown The CRS will enter ____(1)____.

If required, the determination to perform deep load shedding of station batteries must occur within ____(2)____ hour(s) of the onset of the Station Blackout.

(1) (2)

A. OP-902-005, Station Blackout one Recovery Procedure only B. OP-902-005, Station Blackout two Recovery Procedure only C. OP-902-005, Station Blackout two Recovery Procedure and commence FIG-001, Extended Loss of AC Power D. OP-902-005, Station Blackout one Recovery Procedure and commence FIG-001, Extended Loss of AC Power Revision 2 Facility: Waterford 3 Page 7 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Entry into OP-902-005 only would be correct if the Loss of all AC power was determined to be less than four hours. Part 2 is correct.

B. Incorrect. Entry into OP-902-005 only would be correct if the Loss of all AC power was determined to be less than four hours. Part 2 is plausible because two hours is less than the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> coping time for W3 on the station batteries with the loss of all AC power.

C. Incorrect. Part 1 is correct. Part 2 is plausible because two hours is less than the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> coping time for W3 on the station batteries with the loss of all AC power.

D. CORRECT: When the Loss of all AC power may exceed the License Basis SBO duration of four hours, the ELAP must be declared within one hour of the onset of the SBO to meet ELAP time requirements. The caution prior to step 17 of OP-902-005 states that the ELAP must be declared within one hour of the onset of a SBO to ensure that the Station Battery deep load shed time requirements are met. Once an ELAP is declared, the crew will commence FIG-001, Extended Loss of AC Power. This is a new SBO step for W3 and is a result of the latest revision to the EOPs.

Technical Reference(s): OP-902-005 Step 17 Rev. 20 (Attach if not previously provided) TG-OP-902-005 step 17 Rev. 309 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE05 obj. 6 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 3 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 1, 5 Comments:

1. Free review question. Changed the distractor hours to declare an ELAP to less than the coping time of station batteries.

2. NRC Comment: Changed part two of the question to include if required.

Removed the reference for Extended Loss of AC Power from the stem.

3. Add the procedure number to part 1. FIG-001 Revision 2 Facility: Waterford 3 Page 8 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 000058 AA2.03 Importance Rating 3.9 K/A Statement 058 Loss of DC Power, AA2.03: Ability to determine and interpret the following as they apply to the Loss of DC Power: DC loads lost; impact on ability to operate and monitor plant systems Proposed Question: SRO 5 (Q80) Rev: 2 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 will direct the crew to first ____(1)____.

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

(1) (2)

A. vent the Main Generator IAW OP- 2 902-009, Attachment 33-B, Generator Auxiliary Operations-LOOP B. secure the Air Side Seal Oil 1 Backup Pump IAW OP-902-009, Attachment 33-B, Generator Auxiliary Operations-LOOP C. vent the Main Generator IAW OP- 1 901-313, section E4, Loss of 125 Volt DC Bus TGB-DC D. secure the Air Side Seal Oil 2 Backup Pump IAW OP-901-313, section E4, Loss of 125 Volt DC Bus TGB-DC Revision 2 Facility: Waterford 3 Page 9 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: OP-902-003 directs the crew to perform OP-902-009, Attachment 33-B, Generator Auxiliary Operations-LOOP. This attachment will provide the guidance to vent the main generator in preparation for securing the DC seal oil pump. The TGB-DC is preserved to maintain important loads such as the remote operation of the 2 bus feeder breakers.

B. Incorrect. OP-902-009 directs the crew to secure the Air Side Seal Oil Backup Pump but not until the a controlled vent of the Main Generator has been performed. The feeder breakers for the 1 bus is powered from Safety related DC (A-DC and B-DC) for backup overcurrent protection for the RCPs.

C. Incorrect. OP-901-313 is plausible because a section exists for a loss of TGB-DC but it provides no guidance to vent the main generator because AC power is assumed to be available. The feeder breakers for the 1 bus is powered from Safety related DC (A-DC and B-DC) for backup overcurrent protection for the RCPs. This Appendix in the EOP references many procedures but OP-901-313 is not one of them.

D. Incorrect. OP-901-313 is plausible because a section exists for a loss of TGB-DC but it provides no guidance to secure the Air Side Seal Oil Pump. It has a step to verify the AC Air Side Seal Oil Pump is running. Part 2 is correct. This Appendix in the EOP references many procedures but OP-901-313 is not one of them.

Technical Reference(s): OP-902-009 Attachment 33-B Rev. 315 (Attach if not previously provided) TG-OP-902-009 page 86 Rev. 311 (including version/revision number) OP-901-313 section E4 Rev. 305 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE01 obj. 6 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 55.43 5 Comments: NRC comment: Removed Vent the Main Generator IAW in the stem and added it to the distractors. Added which step would be performed first in the stem and added secure the DC pump to distractors and D.

Revision 2 Facility: Waterford 3 Page 10 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 1 K/A # 0057 2.2.22 Importance Rating 4.7 K/A Statement 057 Loss of Vital AC Electrical Instrument Bus, 2.2.22: Knowledge of limiting conditions for operations and safety limits.

Proposed Question: SRO 6 (Q81) Rev: 2 Initial plant conditions:

100% power Battery Charger A1 is tagged out Startup Channel 1 is in Primary Given:

ALL ESFAS actuation annunciators for Train A & B are in alarm Startup Channel 1 energizes CEAC 2 de-energizes All ESFAS trip path lights on CP-7A and 7C extinguish The SUPS will be addressed using ____(1)____.

After the given conditions are addressed, the affected SUPS is fully restored and placed in a normal alignment. Then the Normal AC input breaker trips open.

The SUPS Rectifier or Battery Charger A1 must be restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to prevent

____(2)____.

(1) (2)

A. OP-901-312,Loss of Vital Bus, battery discharge section E1 Loss of SUPS A1 (PDP MA)

B. OP-901-312,Loss of Vital Bus, damage to the rectifier section E1 Loss of SUPS A1 assembly (PDP MA)

C. OP-901-312,Loss of Vital Bus, battery discharge section E3 Loss of SUPS MC D. OP-901-312,Loss of Vital Bus, damage to the rectifier section E3 Loss of SUPS MC assembly Revision 2 Facility: Waterford 3 Page 11 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Part 1 is incorrect because given plant conditions indicate a loss of SUPS MC and not A1 (PDP MA) (key indications are reactor trip breakers, Startup Channel 1 and CEAC 2).

Part 2 is correct.

B. Incorrect. Part 1 - see A above. Part 2 is incorrect because the only effect on the inverter is loss of rectifier output (due to normal AC input breaker tripping). Normal operating procedures have cautions about pre-charging the inverter before closing the DC input source to prevent damage to capacitors.

C. CORRECT: Given plant conditions indicate a loss of SUPS MC and not A1 (PDP MA) (key indications are Startup Channel 1 and CEAC 2). With the SUPS fully restored and returned to a normal alignment, a loss of the normal AC source would make the rectifier inoperable and the emergency DC source would supply loads. Per TRM 3.8.3.1 bases either the rectifier or the battery charger (A1) must be restored to prevent discharge of the battery. Knowledge of the TRM basis makes this question SRO only.

D. Incorrect. Part 1 is correct. Part 2 incorrect - see B above.

Technical Reference(s): OP-901-312 pgs 3-6, 12-17 Rev. 312 (Attach if not previously provided) TRM 3.8.3.1 (amd. 135) and Bases (amd. 91)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-ID00 obj. 2 & 5 (As available)

Question Source: Bank #

Modified Bank # SRO14/SRO5 (Note changes or attach parent)

New Question History: Last NRC Exam 2010 SRO Exam/2011 SRO Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 55.43 2, 5 Comments:

Original question was free reviewed. Rejected K/A and re-wrote based on draft comments.

For Rev. 3, deleted form the given conditions, Reactor Trip breakers 3, 4, 7, and 8 OPEN. Separated part 1 and part 2 as recommended.

Revision 2 Facility: Waterford 3 Page 12 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 000024 AA2.05 Importance Rating 3.9 K/A Statement 024 Emergency Boration, AA2.05: Amount of boron to add to achieve required shutdown margin.

Proposed Question: SRO 7 (Q82) Rev: 2 Given:

Reactor startup is in progress in accordance with OP-010-003, Plant Startup CEAs are in Manual Sequential CEA group positions are:

o Shutdown Banks A & B are All Rods Out o Reg Groups 1-3 are All Rods Out o Reg Group 4 is at 100 inches o Reg Groups 5 and 6 are All Rods In o Group P is at 50 inches Count rate data shows 6 doublings have been achieved based on all Log Power channels. The Reactor Engineer reports criticality is expected in the next 50 inch pull based on 1/M Plot.

The CRS will direct ___(1)___ and direct the ATC to ___(2)___.

(1) (2)

A. a reactor trip direct borate until RCS boron concentration is 20 PPM greater than critical boron concentration B. a reactor trip emergency borate IAW OP-901-103, Emergency Boration, until COLR requirements are met C. full insertion of all Reg Group emergency borate IAW OP-901-103, and Group P CEAs using the Emergency Boration, until COLR shim switch requirements are met D. full insertion of all Reg Group direct borate until RCS boron and Group P CEAs using the concentration is 20 PPM greater than shim switch critical boron concentration Revision 2 Facility: Waterford 3 Page 13 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect.. Part 1 is correct. Part 2 - OP-010-003, step 9.4.41.4.1 directs adjusting boron concentration IAW OP-002-005, Chemical & Volume Control, (most likely direct boration).

Direct boration or any other normal method of boration in OP-002-005 will improve Shutdown Margin but it would be the wrong method in this case.

B. CORRECT: Given conditions indicate that the reactor will go critical below the Power Dependent Insertion Limit (PDIL) of Reg Group 5 at 60 inches. The applicant must know the PDIL. OP-010-003, Plant Startup, step 9.4.36, directs the operator to trip the reactor and emergency borate IAW OP-901-103. OP-901-103, step 6.1 directs borating until Shutdown Margin (TS 3.1.1.2 / COLR) is satisfied. The applicant has two decision points deep in the Plant Startup procedure and must proceed using the correct off-normal procedure. This makes the question SRO only.

C. Incorrect. Part 1 - full insertion of all Reg Group and Group P CEAs will shutdown the reactor, but OP-010-003, step 9.4.36, directs a reactor trip. Part 2 is correct.

D. Incorrect. Part 1 - OP-010-003, Plant Startup, step 9.4.41 directs the operator to insert all Reg Group and Group P CEAs fully into the core if the reactor becomes critical below the -

0.5% reactivity position and Part 2 - adjust boron concentration +/-20 PPM of critical boron concentration IAW OP-002-005 (direct boration). This makes both parts plausible.

Technical Reference(s): OP-010-003 steps 9.4.36 & 9.4.41 Rev 342 (Attach if not previously provided) OP-901-103 step 6.1 Rev. 3 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO10 obj. 3 (As available)

WLP-OPS-PPN01 obj. 3 Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 55.43 5 Comments: Re-wrote question with the same K/a based on draft comments.

For revision 2, changed the stem and part 2 such that the sentence flows (i.e. remove direct direct)

Revision 2 Facility: Waterford 3 Page 14 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # CE/E09 2.2.37 Importance Rating 4.6 K/A Statement CE/E09 Functional Recovery, 2.2.37: Ability to determine operability and/or availability of safety related equipment.

Proposed Question: SRO 8 (Q83) Rev: 2 Given:

The crew has entered OP-902-008, Safety Function Recovery Procedure A Loss of offsite power has occurred and neither Emergency Diesel Generator (EDG) is available The Temporary Emergency Diesel Generator (TED) is supplying the 3A bus In regards to Attachments 7-A, 7-B, and 7-D, the CRS is required to implement A. only Attachment 7-D, Process Analog Control Cabinet Doors, to open cabinet doors B. only Attachment 7-B, Switchgear B Removable Loads, to strip loads C. Attachment 7-A, Switchgear A Removable Loads and Attachment 7-B, Switchgear B Removable Loads, to strip loads D. Attachment 7-B, Switchgear B Removable Loads, to strip loads and Attachment 7-D, Process Analog Control Cabinet Doors to open cabinet doors Revision 2 Facility: Waterford 3 Page 15 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. The note before step 8 states, if a TEDG is available and ready to load within 30 minutes of SBO onset, then load stripping via the associated Attachment 7-A or 7-B should not be necessary. Load stripping via Attachment 7-B is required.

B. Incorrect. The note before step 7 states if a TEDG is the source of AC power, the verify equipment ventilation must still be performed.

C. Incorrect. The note before step 8 states, if a TEDG is available and ready to load within 30 minutes of SBO onset, then load stripping via the associated Attachment 7-A or 7-B should not be necessary. Load stripping via Attachment 7-A is not required.

D. CORRECT: The note before step 7 states if a TEDG is the source of AC power, the verify equipment ventilation must still be performed. The note before step 8 states, if a TEDG is available and ready to load within 30 minutes of SBO onset, then load stripping via the associated Attachment 7-A or 7-B should not be necessary.

Technical Reference(s): OP-902-008, FRP Entry, steps 7 & 8 Rev 26 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE08 obj. 4 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 3 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments: Developed a new question for the same K/A.

Revision 2 Facility: Waterford 3 Page 16 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 000036 2.3.12 Importance Rating 3.7 K/A Statement 036 Fuel Handling Accident, 2.3.12 Knowledge of radiological safety principles pertaining to licensed-operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high rad areas, aligning filters, etc.

Proposed Question: SRO 9 (Q84) Rev: 2 OP-010-006 Attachment 9.23, Loss of Refuel Cavity Water Level Guidelines, states that the most preferred location to place a fuel assembly in transit during a Refuel Cavity leak is the ________.

A. Reactor Vessel B. Upender baskets (place upender horizontal)

C. Fuel Assembly Storage Rack in the Refuel Cavity D. Cavity deep end, with assembly suspended from the Refueling Machine Revision 2 Facility: Waterford 3 Page 17 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: OP-010-006 Attachment 9.23, Loss of Refuel Cavity Water Level Guidelines, states that the most preferred location to place a fuel assembly in transit during a Refuel Cavity leak is the Reactor Vessel.

B. Incorrect. OP-010-006 Attachment 9.23, Loss of Refuel Cavity Water Level Guidelines, states that the most preferred location to place a fuel assembly in transit during a Refuel Cavity leak is the Reactor Vessel. Upender baskets (place upender horizontal) is on the list but is not the most preferred.

C. Incorrect. OP-010-006 Attachment 9.23, Loss of Refuel Cavity Water Level Guidelines, states that the most preferred location to place a fuel assembly in transit during a Refuel Cavity leak is the Reactor Vessel. Fuel Assembly Storage Rack in the Refuel Cavity is on the list but is not the most preferred.

D. Incorrect. OP-010-006 Attachment 9.23, Loss of Refuel Cavity Water Level Guidelines, states that the most preferred location to place a fuel assembly in transit during a Refuel Cavity leak is the Reactor Vessel. Cavity deep end, with assembly suspended from the Refueling Machine is on the list but is not the most preferred.

Technical Reference(s): OP-010-006 Attachment 9.23 Rev. 329 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-REQ04 obj. 5 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 55.43 5,7 Comments: NRC comment: Changed the question and kept the same K/A. The first question was not SRO only Revision 2 Facility: Waterford 3 Page 18 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 1 Group # 2 K/A # 00067 AA2.17 Importance Rating 4.3 K/A Statement 067 Plant Fire on Site, AA2.17: Ability to determine and interpret the following as they apply to plant fire on site: systems that may be affected by the fire.

Proposed Question: SRO 10 (Q85) Rev: 2 Given:

The fire brigade leader reports a fire in the Relay Room that requires activation of the Fire Brigade team.

Within 20 minutes of the fire, the CRS will direct the crew to perform actions to electrically lockout the Reactor Coolant Pumps because the location of this fire could affect ____(1)____. This step will be performed in accordance with____(2)____.

(1) (2)

A. the backup overcurrent OP-901-524, Fires in areas protection for the RCPs affecting Safe Shutdown, Section E12 RAB 7A B. the backup overcurrent OP-901-502, Evacuation of protection for the RCPs Control Room and Subsequent Plant Shutdown, Section E0 Control Room Evacuation C. components which provide OP-901-524, Fires in areas cooling to the RCP seals affecting Safe Shutdown, Section E12 RAB 7A D. components which provide OP-901-502, Evacuation of cooling to the RCP seals Control Room and Subsequent Plant Shutdown, Section E0 Control Room Evacuation Revision 2 Facility: Waterford 3 Page 19 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. Plausible because there is a TS action to de-energize the RCPs if the primary and backup overcurrent protection is inoperable (TS 3.8.4.1). Part 2 is correct.

B. Incorrect: Plausible because there is a TS action to de-energize the RCPs if the primary and backup overcurrent protection is inoperable (TS 3.8.4.1). OP-901-502 would be entered and a Control Room Evacuation performed if the fire was in the cable spreading room which is adjacent to the relay room. Operators get these two rooms confused with each other.

C. CORRECT: For a fire in the relay room, the crew will enter OP-901-524, Fires in areas affecting Safe Shutdown. This procedures directs the crew to trip the RX, secure RCPs and electrically lockout the RCPs per Attachment 2 within 20 minutes of the fire. The question meets the requirement for SRO only because part 1 is not system knowledge because it is a note in the OP-901-524 procedure and is important because damage to the seals could occur if the steps are not completed within the 20 minute time requirement. This question cannot be answered by solely knowing AOP entry conditions.

D. Incorrect. Part 1 is correct. OP-901-502 would be entered and a Control Room Evacuation performed if the fire was in the cable spreading room which is adjacent to the relay room.

Technical Reference(s): OP-901-524 pages 7,8, and 106 Rev. 15 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO50 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 55.43 5 Comments: NRC comment: Added more information to the explanation on why the distractors are plausible. Added the sub-sections to the AOPs.

Revision 2 Facility: Waterford 3 Page 20 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 004 A2.15 Importance Rating 3.7 K/A Statement 004 Chemical and Volume Control, A2.15: Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High or low PZR level Proposed Question: SRO 11 (Q86) Rev: 2 Given:

Reactor Power is 100% with Tavg and Tref matched Pressurizer Level Channel X is 40% and slowly lowering Pressurizer Level Channel Y is 60% and slowly rising Channel X is selected for service The crew has entered OP-901-110, Pressurizer Level Control Malfunction The CVCS system configuration will be changed by ______(1)_______.

The crew will implement section _______(2)_______.

(1) (2)

A. both backup charging pumps E1, Pressurizer Level Control Channel starting Malfunction B. letdown flow rising to 126 gpm E1, Pressurizer Level Control Channel Malfunction C. both backup charging pumps E3, Pressurizer Level Controller Malfunction starting D. letdown flow rising to 126 gpm E3, Pressurizer Level Controller Malfunction Revision 2 Facility: Waterford 3 Page 21 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: The level setpoint for 100% is normally ~ 56%. With Selected pressurizer level indicating 40% both backup charging pumps would have received start signals and letdown should be at minimum (~28 gpm). Pressurizer level is diverging between channels. This is indicative of a failing channel, therefor E1 is correct section to implement.

B. Incorrect. If Channel Y was the selected channel, then letdown flow rising to 126 gpm would be the correct answer. Part 2 is correct.

C. Incorrect. Part 1 is correct. Pressurizer level is diverging between channels. This is indicative of a failing channel. If Pressurizer level channels were tracking together it would be indicative of a Pressurizer controller or setpoint malfunction.

D. Incorrect. If Channel Y was the selected channel, then letdown flow rising to 126 gpm would be the correct answer. Pressurizer level is diverging between channels.

This is indicative of a failing channel. If Pressurizer level channels were tracking together it would be indicative of a Pressurizer controller or setpoint malfunction.

Technical Reference(s): OP-901-110 pages 4-7 Rev. 9 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO10 obj. 3 (As available)

Question Source: Bank # SRO1 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2010 NRC SRO Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 4 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

Revision 2 Facility: Waterford 3 Page 22 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 008 2.2.40 Importance Rating 4.7 K/A Statement 008 Component Cooling Water, 2.2.40: Ability to apply Technical specifications for a system.

Proposed Question: SRO 12 (Q87) Rev: 2 Given:

A Tornado Watch is in affect for St. Charles Parish The crew has entered OP-901-521, Severe Weather and Flooding Due to the changing weather conditions, the CRS will verify additional operability requirements are met for the Dry Cooling Tower (DCT) fans by verifying DCT fans

___(1)___ are operable. The Dry Cooling Tower fans are considered operable if their control switches are in the ___(2)___ position(s).

(1) (2)

A. 7 through 15 auto only B. 1 through 9 auto only C. 1 through 9 auto or fast D. 7 through 15 auto or fast Revision 2 Facility: Waterford 3 Page 23 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Part 1 is correct. The basis for TS 3.7.4 action c states that the DCT fan operability is maintained by operating in fast or auto mode. The fan being in fast and inoperable is plausible because the sequencer at which the fan starts/stops on rising and lowering temperature is inoperable when the C/S is in FAST. This sequencer is not part of the fan operability.

B. Incorrect. TS 3.7.4 action c states with a tornado watch in effect, all 9 DCT fans under the missile protected portion of the DCT shall be operable. The 9 DCT fans under the missile shield are DCT fans 7-15. The basis for this TS action states that the DCT fan operability is maintained by operating in fast or auto mode. The fan being in fast and inoperable is plausible because the sequencer at which the fan starts/stops on rising and lowering temperature is inoperable when the C/S is in FAST. This sequencer is not part of the fan operability.

C. Incorrect. TS 3.7.4 action c states with a tornado watch in effect, all 9 DCT fans under the missile protected portion of the DCT shall be operable. The 9 DCT fans under the missile shield are DCT fans 7-15. Part 2 is correct.

D. CORRECT: TS 3.7.4 action c states with a tornado watch in effect, all 9 DCT fans under the missile protected portion of the DCT shall be operable. The 9 DCT fans under the missile shield are DCT fans 7-15. The basis for TS 3.7.4 action c states that the DCT fan operability is maintained by operating in fast or auto mode.

Technical Reference(s): OP-901-521 section E2 step 3 Rev. 323 (Attach if not previously provided) TS 3.7.4 and basis (including version/revision number) SD-CC page 19 Rev. 22 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-CC00 obj. 10 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 55.43 2 Comments: NRC comment: Added to the explanation why it is plausible that the fans are inoperable when in Fast Mode.

Revision 2 Facility: Waterford 3 Page 24 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 013 A2.06 Importance Rating 4.0 K/A Statement 013 Engineered Safety Features Actuation, A2.06: Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Inadvertent ESFAS actuation.

Proposed Question: SRO 13 (Q88) Rev: 2 The reactor is operating at 100% power when an inadvertent CSAS occurs. After 5 seconds the reactor trips due to a trip of RCP 1A. The CRS should direct the crew to perform the following:

A. Enter OP-901-504, Inadvertent ESFAS Actuation, place both Containment Spray pumps in stop, and restore CCW to the RCPs concurrently with the performance of OP-902-000, Standard Post Trip Actions. Then transition to OP-902-001, Reactor Trip Recovery.

B. Restore CCW to the RCPs during the performance of OP-902-000, Standard Post Trip Actions. Then transition to OP-902-008, Functional Recovery and terminate Containment Spray.

C. Perform OP-902-000, Standard Post Trip Actions. Then transition to OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery, concurrent with OP-901-504, Inadvertent ESFAS Actuation and place both Containment Spray pumps in stop.

D. Restore CCW to the RCPs during the performance of OP-902-000, Standard Post Trip Actions. Then transition to OP-902-001, Reactor Trip Recovery, and terminate Containment Spray using OP-009-001, Containment Spray.

Revision 2 Facility: Waterford 3 Page 25 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: SRO needs to know that OP-901-504 must be implemented concurrently with SPTAs. With a short time period of 5 seconds, the crew should take action to restore CCW to the RCPs within the next 2 min and 55 seconds and stop CS pumps during SPTAs.

B. Incorrect. Plausible if the applicant believes that a safety function is threatened or believes that functional recovery provides the only additional guidance for terminating containment spray. Incorrect because SPTAs should be implemented concurrently with OP-901-504.

C. Incorrect. Plausible if the applicant believes that SPTAs are to be performed independently of OP-901-504. Incorrect because they should be implemented concurrently - the crew should not wait until transition to a major event EOP to terminate Containment Spray.

D. Incorrect. Plausible if the applicant does not believe that OP-901-504 is to be implemented concurrently with the EOPs and that the normal operating procedure should be used to shutdown containment spray. Incorrect because SPTAs should be implemented concurrently with OP-901-504.

Technical Reference(s): OP-901-504 pgs. 7, 16 & 17 Rev. 10 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO50 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 3 10 CFR Part 55 Content: 55.41 55.43 5 Comments: Revised to make SRO-only Revision 2 Facility: Waterford 3 Page 26 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 064 2.2.25 Importance Rating 4.2 K/A Statement 064 Emergency Diesel Generator, 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operation and safety limits.

Proposed Question: SRO 14 (Q89) Rev: 2 Given:

Emergency Diesel Generator (EDG) A is inoperable due to unplanned maintenance 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> into the unplanned EDG A outage, the Temporary Emergency Diesel (TED) Generator is verified available and aligned as a backup for EDG A 8 days (192 hours0.00222 days <br />0.0533 hours <br />3.174603e-4 weeks <br />7.3056e-5 months <br />) from when EDG A first became inoperable, the Temporary Emergency Diesel (TED) Generator becomes unavailable and cannot be restored Per TS 3.8.1.1, from the time the Temporary Emergency Diesel (TED) Generator becomes unavailable, the time limit for restoring Emergency Diesel Generator A to service is ________ hours.

A. 28 B. 48 C. 68 D. 72 Revision 2 Facility: Waterford 3 Page 27 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> would be the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> AOT subtracted by the 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> that it took to get the TEDG available.

B. CORRECT: Technical Specification 3.8.1.1 basis states if the EDG becomes inoperable for pre-planned maintenance, the allowed outage time can be extended from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 10 days, if a TEDG is available and aligned. The same basis states,if the TEDG becomes unavailable during the 10 day AOT and cannot be restored, the EDG AOT reverts back to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, not to exceed 10 days. Therefore, 192 hour0.00222 days <br />0.0533 hours <br />3.174603e-4 weeks <br />7.3056e-5 months <br />s=8 days, 2 days (48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) are available such that 10 days is not exceeded.

C. Incorrect. 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> would be 10 days from the time the TEDG was placed in service.

D. Incorrect. If the TEDG becomes unavailable during the 10 day AOT and cannot be restored, the EDG AOT reverts back to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, not to exceed 10 days. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> would exceed the 10 day AOT.

Technical Reference(s): TS 3.8.1.1 basis (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-EDG00 obj. 7 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 4 10 CFR Part 55 Content: 55.41 55.43 2 Comments:

Free review question, no changes required.

Revision 2 Facility: Waterford 3 Page 28 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 1 K/A # 006 A2.04 Importance Rating 3.8 K/A Statement 006 ECCS A2.04: Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: improper discharge pressure.

Proposed Question: SRO 15 (Q90) Rev: 2 Given:

LOCA occurred 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago Crew is performing OP-902-002, Loss of Coolant Accident Recovery Recirculation Actuation Signal has occurred, and required actions have been taken RCS is 15°F subcooled; CET temperatures are rising very slowly QSPDS RVLMS levels 1-6 indicates void BOP notes that HPSI A and B pumps cold leg flow has dropped off slowly with discharge pressure rising and no oscillations Containment Spray Pumps A and B are running with flow ~ 2000 GPM each train and stable The CRS should ______(1)______. The conditions given indicate _____(2)_____.

(1) (2)

A. perform Appendix 15 Hot and the SI Sump Strainers are starting to Cold Leg Injection clog from debris collection B. secure one HPSI pump and verify the SI Sump Strainers are starting to Attachment 2-E HPSI Flow Curve clog from debris collection is met C. secure one HPSI pump and verify core flow blockage is starting to occur Attachment 2-E HPSI Flow Curve due to boron precipitation is met D. perform Appendix 15 Hot and core flow blockage is starting to occur Cold Leg Injection due to boron precipitation Revision 2 Facility: Waterford 3 Page 29 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Part 1 is correct. The indications given indicate a problem developing on the discharge side of the High Pressure Safety Injection Pumps, not the suction side (SI Sump Strainers) Plausible because flow is lowering. The applicant can determine there is no blockage because the CS pump flows are steady and its suction is also from the SI sump.

Step 49 (Loss of ECCS pump suction) directs securing a HPSI pump if flow is low and oscillating.

B. Incorrect. Both parts are incorrect. The indications given indicate a problem developing on the discharge side of the High Pressure Safety Injection Pumps, not the suction side (SI Sump Strainers). Plausible because flow is lowering (but it is not oscillating). Step 49 (Loss of ECCS pump suction) directs securing a HPSI pump if flow is low and oscillating. Also, the new revision to the EOPs added an attachment (2-L) to be used to verify HPSI flow within the curves Post-RAS. Attachment 2-E would be the wrong attachment to use.

C. Incorrect. Step 49 (Loss of ECCS pump suction) directs securing a HPSI pump if flow is low and oscillating. The new revision to the EOPs added Attachment (2-L) which is used to verify HPSI flow within the curves Post-RAS. Attachment 2-E would be the wrong attachment to use.

D. CORRECT: The indications given indicate a problem developing on the discharge side of the High Pressure Safety Injection Pumps. At 2-3 hours post LOCA the crew should align hot and cold leg injection to avoid concentrating boric acid in the reactor vessel and possible boron precipitation in the core that could restrict coolant flow.

Technical Reference(s): OP-902-002 steps 49 and 53 Rev. 20 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE02 obj. 19 (As available)

Question Source: Bank # SRO11 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2012 SRO Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 4 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

Revision 2 Facility: Waterford 3 Page 30 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 014 2.4.11 Importance Rating 4.2 K/A Statement 014 Rod Position Indication, 2.4.11 Knowledge of abnormal condition procedures.

Proposed Question: SRO 16 (Q91) Rev: 2 Given:

Power is 100%

The PMC has failed and the actions of OP-901-501, PMC or Core Operating Limit Supervisory System Malfunction, are being performed As stated in TS surveillance requirement 4.1.3.2, the crew will verify that at least two of the three CEA position indicator channels are operable by verifying for the same CEA, the position indicator channels agree within ____(1)____ inches of each other.

TS 3.1.3.2 Position Indicator Channels-Operating, states, with a maximum of one CEA per CEA group having only one of its CEA position indicator channels operable, operation may continue provided the CEA group(s) with the inoperable position indicator(s) _____(2)_____.

(1) (2)

A. seven is maintained fully withdrawn B. seven CEA position(s) is documented every four hours C. five CEA position(s) is documented every four hours D. five is maintained fully withdrawn Revision 2 Facility: Waterford 3 Page 31 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Seven inches is the deviation limit between a CEA and the other CEAs within the same group (TS 3.1.3.1 action d). Part 2 is correct.

B. Incorrect. Seven inches is the deviation limit between a CEA and the other CEAs within the same group (TS 3.1.3.1 action d). CEA position must be documented every fours on a loss of PMC (due to the loss of the PDIL annunciator). The stem is asking what TS 3.1.3.2 states, so this distractor is wrong.

C. Incorrect. Part 1 is correct. CEA position must be documented every fours on a loss of PMC (due to the loss of the PDIL annunciator). The stem is asking what TS 3.1.3.2 states, so this distractor is wrong D. CORRECT: TS surveillance requirement 4.1.3.2 requires CEA position indications for the same CEA to be within 5 inches of each other. TS 3.1.3.2 action c states operations may continue if the CEA with only one position indicator operable is maintained fully withdrawn. SRO only because the required knowledge is below the line in parts 1 and 2.

Technical Reference(s): OP-901-501, Section E1, steps 8 & 10, Rev. 15 (Attach if not previously provided) TS 3.1.3.2 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPO50 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 3 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

Revision 2 Facility: Waterford 3 Page 32 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 029 A2.03 Importance Rating 3.1 K/A Statement 029 Containment Purge System, A2.03: Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Startup operations and the associated required valve lineups.

Proposed Question: SRO 17 (Q92) Rev: 2 Given:

A Plant Startup from a refueling outage is in progress in accordance with OP-010-003 Prior to establishing Containment Integrity for Mode 4, the crew will demonstrate operability of each Containment Purge Supply and Exhaust Isolation valve by verifying the mechanical stops are ____(1)____. When mode 4 is established, the cumulative hours these valves are opened will be tracked using the attachment in _____(2)_____.

(1) (2)

A. removed OP-903-001, Technical Specification Surveillance Logs B. installed OP-903-001, Technical Specification Surveillance Logs C. installed OP-100-014, Technical Specification and Technical Requirements Compliance D. removed OP-100-014, Technical Specification and Technical Requirements Compliance Revision 2 Facility: Waterford 3 Page 33 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. The Containment Purge Supply and Exhaust Isolation valve mechanical stops are removed during refuel outages but must be re-installed prior to establishing containment integrity. Part 2 is correct.

B. CORRECT: Prior to establishing Containment Integrity for Mode 4, OP-010-003 states to demonstrate operability of each Containment Purge Supply and Exhaust Isolation valve by verifying the mechanical stops limit valve opening to < 52º open position. The cumulative purge hours are tracked using an attachment in OP-903-001. These hours are tracked to ensure compliance with Tech Specs. SRO only because the applicant must demonstrate knowledge of TS surveillances 4.6.1.7.1 and 4.6.1.7.3.

C. Incorrect. Part 1 is correct. The purpose of OP-100-014 is to ensure compliance with TS and TRMs. Logging the containment purge hours are Tech Spec required but are not located here.

D. Incorrect. The Containment Purge Supply and Exhaust Isolation valve mechanical stops are removed during refuel outages but must be re-installed prior to establishing containment integrity. The purpose of OP-100-014 is to ensure compliance with TS and TRMs. Logging the containment purge hours are Tech Spec required but are not located here.

Technical Reference(s): OP-903-001 Attachment 11.6 Rev. 66 (Attach if not previously provided) OP-010-003 step 9.1.31 Rev. 342 (including version/revision number) TS 3.6.1.7 Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPN01 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 3 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2,5 Comments: Added TS 3.6.1.7 to the reference section.

Revision 2 Facility: Waterford 3 Page 34 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 2 Group # 2 K/A # 033 2.2.42 Importance Rating 4.6 K/A Statement 033 Spent Fuel Pool Cooling, 2.2.42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications.

Proposed Question: SRO 18 (Q93) Rev: 2 Given:

A Spent Fuel Pool leak is in progress The crew has entered OP-901-513, Spent Fuel Pool Cooling Malfunction NAO reports that Spent Fuel Pool level instruments Channel 1 and 2 located on the Q-Deck read 22.2 feet The requirements of TS 3.9.11 WATER LEVEL-SPENT FUEL POOL are ____(1)____.

TS 3.9.11 basis states that in the event of a rupture of an irradiated fuel assembly, sufficient water depth is available such that_____(2)_____.

(1) (2)

A. met sufficient cooling capacity is maintained B. met iodine released is within limits C. not met sufficient cooling capacity is maintained D. not met iodine released is within limits Revision 2 Facility: Waterford 3 Page 35 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: D Explanation: (Optional)

A. Incorrect. Tech Spec 3.9.11 requires at least 23 feet of water above the fuel. The given information says level is less than required. Plausible because a certain mass of water is required to provide sufficient cooling capacity, but this is not the reason for the 23 feet of water stated in the bases.

B. Incorrect. Tech Spec 3.9.11 requires at least 23 feet of water above the fuel. The given information says level is less than required. Part 2 is correct.

C. Incorrect. Part 1 is correct. Plausible because a certain mass of water is required to provide sufficient cooling capacity, but this is not the reason for the 23 feet of water stated in the bases.

D. CORRECT: Tech Spec 3.9.11 requires at least 23 feet of water maintained over irradiated fuel. This meets the K/A for recognizing system parameters that are entry-level conditions for Tech Specs. Part two makes this question SRO-only because it requires knowledge of the TS bases.

Technical Reference(s): TS 3.9.11 and bases (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE01 obj. 4 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 Comments:

Re-wrote question based on NRC comments. Used a different randomly selected K/A.

Revision 2 Facility: Waterford 3 Page 36 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 1 K/A # 2.1.4 Importance Rating 3.8 K/A Statement 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no solo operation, maintenance of active license status, 10CFR55, etc.

Proposed Question: SRO 19 (Q94) Rev: 2 OI-042-000, Watch Station Processes, states that no more than _____(1)_______

personnel on a shift should be absent at the same time and at least _____(2)______

NAOs on a shift should be a normal member of that shifts crew.

(1) (2)

A. four two B. five two C. four three D. five three Revision 2 Facility: Waterford 3 Page 37 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: OI-042-000 step 5.1.4.2 (Shift Composition Guidelines) states that no more that four personnel on a shift should be absent at the same time and at least two NAOs on a shift should be a normal member of that shifts crew.

B. Incorrect. OI-042-000 step 5.1.4.2 (Shift Composition Guidelines) states that no more that four personnel on a shift should be absent at the same time and at least two NAOs on a shift should be a normal member of that shifts crew.

C. Incorrect. OI-042-000 step 5.1.4.2 (Shift Composition Guidelines) states that no more that four personnel on a shift should be absent at the same time and at least two NAOs on a shift should be a normal member of that shifts crew.

D. Incorrect. OI-042-000 step 5.1.4.2 (Shift Composition Guidelines) states that no more that four personnel on a shift should be absent at the same time and at least two NAOs on a shift should be a normal member of that shifts crew.

Technical Reference(s): OI-O42-000 step 5.1.4.2 Rev. 46 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPA00 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 1,2 Comments: NRC Comment: Developed a new question with the same K/A. The original question was determined not be SRO knowledge only.

Revision 2 Facility: Waterford 3 Page 38 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 1 K/A # 2.1.45 Importance Rating 4.3 K/A Statement 2.1.45 Ability to identify and interpret diverse indications to validate the response of another indication.

Proposed Question: SRO 20 (Q95) Rev: 2 Regarding EOP usage, to verify the RCS is not water solid with Pressurizer level indicating 100%, the crew will verify that ____(1)____ . If the RCS is considered water solid, the crew will _____(2)_____.

(1) (2)

A. RCS inventory or temperature remain in the selected Optimal Recovery changes do not produce Procedure and control RCS temperature severe pressure responses and throttle RCS makeup B. RCS inventory or temperature transition to the Functional Recovery changes do not produce Procedure and establish a bubble in the severe pressure responses Pressurizer C. Reactor vessel plenum level is remain in the selected Optimal Recovery less than 100% Procedure and control RCS temperature and throttle RCS makeup D. Reactor vessel plenum level is transition to the Functional Recovery less than 100% Procedure and establish a bubble in the Pressurizer Revision 2 Facility: Waterford 3 Page 39 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: Optimal Recovery procedures (902-002, 004 and 007) and OI-038-000 (Operations Expectations procedure) includes guidance for verifying the RCS is not water solid. RCS inventory or temperature changes not producing severe pressure responses is listed as a diverse indication that the RCS is not water solid. Controlling RCS temperature and throttling HPSI flow is the contingency action for the RCS is water solid.

Therefore the crew can remain in the selected ORP and transitioning to OP-902-008 is not required.

B. Incorrect. Part 1 is correct. Controlling RCS temperature and throttling HPSI flow is the contingency action for the RCS is water solid. Therefore, transitioning to OP-902-008 is not required.

C. Incorrect. The crew is required to verify RV head level is less than 100% to check RCS is not water solid, not plenum level. Plausible because the applicant would have to know RVLMS gives both head and plenum level on QSPDS. RCS inventory or temperature changes not producing severe pressure responses is listed as a diverse indication that the RCS is not water solid. Part 2 is correct.

D. Incorrect. The crew is required to verify RV head level is less than 100% to check RCS is not water solid, not plenum level. Plausible because the applicant would have to know RVLMS gives both head and plenum level on QSPDS. Controlling RCS temperature and throttling HPSI flow is the contingency action for the RCS is water solid. Therefore, transitioning to OP-902-008 is not required.

Technical Reference(s): OP-902-004 step 31 revision 16 (Attach if not previously provided) TGOP-902-004 step 31 Rev. 307 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE04 obj. 7 (As available)

Question Source: Bank # SRO20 Modified Bank # (Note changes or attach parent)

New Question History: Last NRC Exam 2014 NRC Exam Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 4 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

Revision 2 Facility: Waterford 3 Page 40 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 2 K/A # 2.2.13 Importance Rating 4.3 K/A Statement 2.2.13 Knowledge of tagging and clearance procedures.

Proposed Question: SRO 21 (Q96) Rev: 2 When clearing the Main Steam Administrative (MS-Admin) tagout, the ____(1)____ must sign off as the tagout holder. The (MS-Admin) tagout must be cleared ____(2)____ all tagouts that use the MS-ADMIN tagout are cleared.

(1) (2)

A. outage manager before B. designated operations after supervisor C. outage manager after D. designated operations before supervisor Revision 2 Facility: Waterford 3 Page 41 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. The outage management responsibility per EN-OP-102 is to communicate to site personnel when MS-ADMIN tagout is hung, cleared or changes made. The MS-ADMIN tagout cannot be cleared until all tagouts using it are cleared.

B. CORRECT: The designated operations supervisor signs on and must sign off the MS-ADMIN tagout before it can be cleared. The MS-ADMIN tagout can be cleared once all tagouts using it are cleared.

C. Incorrect. The outage management responsibility per EN-OP-102 is to communicate to site personnel when MS-ADMIN tagout is hung, cleared or changes made. Part 2 is correct.

D. Incorrect. Part 1 is correct. The MS-ADMIN tagout cannot be cleared until all tagouts using it are cleared.

Technical Reference(s): EN-OP-102 step 5.22 [6] Rev. 18 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: FLP-OPS-ESOMS obj. 4 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 2 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

Revision 2 Facility: Waterford 3 Page 42 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 2 K/A # 2.2.12 Importance Rating 4.1 K/A Statement 2.2.12 Knowledge of surveillance procedures Proposed Question: SRO 22 (Q97) Rev: 2 Today is April 5, 2017, and the operating crew has determined that a required monthly technical specification surveillance was last performed on March 3, 2017. Technical Specifications require that ____(1)____.

A. the appropriate TS action statement be entered immediately B. the surveillance be performed by April 10, 2017 C. the surveillance be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> D. the plant evaluate risk and perform the surveillance by May 6, 2017 Revision 2 Facility: Waterford 3 Page 43 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: B Explanation: (Optional)

A. Incorrect. TS allows for a 25% extension on a missed surveillance. Immediate TS entry is not required.

B. CORRECT: TS defines a month as it pertains to surveillances to be 31 days (Table 1.1). TS 4.02 states that a surveillance must be performed within the specified interval not to exceed an extension of 25% of that interval. The extension for this surveillance is 31 days (.25)=7.75 days. April 10 will be the seventh day of the extension, so the surveillance must be done by then. SRO only because the applicant must demonstrated knowledge of section 1.0 and 4.0 of TS.

C. Incorrect. The surveillance does not have to be completed with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. TS allows for a 25%

extension on a missed surveillance. Not a sub step of B because the root states the CRS must.

D. Incorrect. May 6th is 30 days from the surveillance time interval and is outside of the 25%

allowed extension .

Technical Reference(s): TS section 4.0 (Attach if not previously provided) TS table 1.1 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-TS00 obj. 3 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 3 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments: NRC comment: First question was not SRO only. Changed the question using the same K/A.

Revision 2 Facility: Waterford 3 Page 44 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 3 K/A # 2.3.11 Importance Rating 4.3 K/A Statement 2.3.11 Ability to control radiation releases Proposed Question: SRO 23 (Q98) Rev: 2 Which of the following are required actions per TRM 3.3.3.10, Radioactive Liquid Effluent, to release a Boric Acid or Waste Condensate Tank with its associated discharge Radiation Monitor Inoperable?

A. Ensure release rate calculations have been verified by two technically qualified personnel prior to the discharge and the discharge valve lineup is independently verified.

B. Ensure release rate calculations have been verified by two technically qualified personnel prior to the discharge and obtain grab samples every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during discharge.

C. Calculate release flow rate every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the discharge and the discharge valve lineup is independently verified.

D. Calculate release flow rate every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the discharge and obtain grab samples every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during discharge.

Revision 2 Facility: Waterford 3 Page 45 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: A Explanation: (Optional)

A. CORRECT: These actions are required per TRM 3.3.3.10 action 1b for an inoperable BM or LWM Radiation Monitor.

B. Incorrect. Part 1 is correct. Independent samples are required prior to the discharge, not during the discharge (action 1a)

C. Incorrect. Part 1 is for an inoperable flow instrument (action 2). Part 2 is correct.

D. Incorrect. Part 1 is for an inoperable flow instrument (action 2). Independent samples are required prior to the discharge but not every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the discharge (action 1a).

Technical Reference(s): TRM 3.3.3.10 (Attach if not previously provided)

(including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-BM00 obj. 9 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 3 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 Comments:

NRC comment: Changed the level of difficulty from 4 to 3.

Revision 2 Facility: Waterford 3 Page 46 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 4 K/A # 2.4.21 Importance Rating 4.6 K/A Statement 2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant integrity, containment conditions, radioactivity release control, etc.

Proposed Question: SRO 24 (Q99) Rev: 2 Given:

The CRS is prioritizing safety functions in accordance with OP-902-008, Functional Recovery Procedure A SIAS, CIAS, MSIS and CSAS are present Two CEAs have failed to insert The ATC reports that Reactor Power is 10-5 % and dropping The CRS is evaluating the Reactivity Control Safety Function

____(1)____ safety function acceptance criteria are met. The CRS will implement success path _____(2)_____ for Reactivity control.

(1) (2)

A. Only RC-1 RC-1 B. Only RC-1 RC-2 C. RC-1 and RC-2 RC-2 D. RC-1 and RC-2 RC-1 Revision 2 Facility: Waterford 3 Page 47 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. RC-1(Condition 2) is met due to power <10-4% and dropping. RC-2(Condition 1) is met because emergency boration is in progress due to the SIAS. Even though RC-1 criteria is met, RC-2 is implemented because RC-1 has no guidance for emergency boration and termination.

B. Incorrect. RC-1(Condition 2) is met due to power <10-4% and dropping. RC-2(Condition 1) is met because emergency boration is in progress due to the SIAS. Part 2 is correct.

C. CORRECT: RC-1(Condition 2) is met due to power <10-4% and dropping. RC-2(Condition 1) is met because emergency boration is in progress due to the SIAS. Even though RC-1 criteria is met, RC-2 is implemented because RC-1 has no guidance for emergency boration and termination. This question is TIER 3 because the logic is from OI-038-000, EOP Operations/Expectations Guidance and this logic is the same when prioritizing safety functions with more than one CEA stuck for any type of event.

D. Incorrect. Part 1 is correct. Even though RC-1 criteria is met, RC-2 is implemented because RC-1 has no guidance for emergency boration and termination.

Technical Reference(s): OI-038-000 step 5.4.55 Rev. 14 (Attach if not previously provided) OP-902-008 RC-1 and RC-2 SFSC Rev. 26 (including version/revision number)

Proposed references to be provided to applicants during examination: None Learning Objective: WLP-OPS-PPE01 obj. 4 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 4 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

Revision 2 Facility: Waterford 3 Page 48 of 50

2017 NRC Exam SRO Written Exam Worksheet Examination Outline Cross-

Reference:

Level RO SRO Tier # 3 Group # 4 K/A # 2.4.30 Importance Rating 4.1 K/A Statement 2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

Proposed Question: SRO 25 (Q100) Rev: 2 Given:

An valid automatic reactor trip signal has failed to trip the reactor The manual reactor trip pushbuttons and Diversified Reactor Trip System (DRTS) also failed to trip the reactor The BOP has tripped the reactor by de-energizing the Motor Generator Sets The Emergency Planning classification for this event is a(n) ____(1)____. The NRC shall be notified no later than _____(2)_____ of declaring the emergency.

(1) (2)

A. Alert one hour B. Alert 15 minutes C. Site Area Emergency one hour D. Site Area Emergency 15 minutes Revision 2 Facility: Waterford 3 Page 49 of 50

2017 NRC Exam SRO Written Exam Worksheet Proposed Answer: C Explanation: (Optional)

A. Incorrect. The required information for making this classification is located in the basis document for SS3. If the applicant does not know that the 32 feeder breakers are not part of the reactor console he/she would answer alert. Part 2 is correct B. Incorrect. The required information for making this classification is located in the basis document for SS3. If the applicant does not know that the 32 feeder breakers are not part of the reactor console he/she would answer alert. 15 minutes is the time limit for notifying Operation Hotline Members and Waterford 1 and 2 for an event classification C. CORRECT: The basis for SS3 states that tripping the reactor using the 32 feeder breakers is a Site Area Emergency (not part of the reactor control console). The NRC shall be notified within one hour of the classification. This question is TIER 3 because the emergency classification criteria is the same for any automatic trip failure. Only one page of the E-plan will be given because the applicant is being tested on his/her knowledge of information located in the basis document for SS3 (not his ability to locate SS3).

D. Incorrect. Part 1 is correct. 15 minutes is the time limit for notifying Operation Hotline Members and Waterford 1 and 2 for an event classification.

Technical Reference(s): EP-001-001 pages 22 & 152 Rev 32 (Attach if not previously provided) EP-002-010 step 5.2.1.5 Rev 314 (including version/revision number)

Proposed references to be provided to applicants during examination: EP-001-001 page 22 Rev 32 Learning Objective: WLP-OPS-EP02 objs. 9 and 17 (As available)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X Question History: Last NRC Exam None Question Cognitive Level: Memory or Fundamental Knowledge 3 Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

Revision 2 Facility: Waterford 3 Page 50 of 50