ML14119A366

2014/04 Final Written Exam

ML14119A366
Person / Time
Site:	Waterford
Issue date:	04/02/2014
From:	Vincent Gaddy Operations Branch IV
To:	Entergy Operations
References
59-382/OL-14
Download: ML14119A366 (102)

Text

2014 NRC Exam RO Written Exam RO 1 Given:

Plant is at 100% power Steam Generator 2 Steam Flow transmitter to Feedwater Control failed LOW The BOP operator took manual control of FWCS Master Controller #2 and raised the output to 40%, but the reactor tripped on Low Steam Generator Level All other Feedwater Controllers are in AUTOMATIC On the Reactor Trip, Reactor Trip Override (RTO) will ____(1)____. Contingency actions required by the BOP will include ____(2)____.

(1) (2)

A. align FWCS #2 manually closing MFRV #2 and positioning components to their SUFRV #2 to 13 - 21% open RTO position B. align FWCS #2 lowering the output of FWCS Master components to their Controller #2 to reset the RTO RTO position C. not align FWCS #2 manually closing MFRV #2 and positioning components to their SUFRV #2 to 13 - 21% open RTO position D. not align FWCS #2 lowering the output of FWCS Master components to their Controller #2 to reset the RTO RTO position Facility: Waterford 3 Page 1 of 75

2014 NRC Exam RO Written Exam RO 2 Given:

Plant is at 100% power The following annunciators are in alarm:

PRESSURIZER RELIEF LINE TEMP HI PRESSURIZER RELIEF VALVE OPEN Which of the following statements is correct?

A. Quench Tank temperature will equal Tsat for the current Pressurizer pressure.

B. Quench Tank pressure will equal Psat for the current Pressurizer vapor space temperature.

C. The downstream Safety Relief temperature detector will indicate Tsat for the current Pressurizer pressure.

D. The downstream Safety Relief temperature detector will indicate Tsat for the current Quench Tank pressure.

Facility: Waterford 3 Page 2 of 75

2014 NRC Exam RO Written Exam RO 3 Given:

Plant was initially at 100% power A loss of offsite power has occurred B EDG has failed A Small Break Loss of Coolant Accident has occurred Per the Technical Guide for the Loss of Coolant Accident, heat removal from the steam exiting the break in the RCS is ____(1)____ to remove decay heat.

In the beginning stages of the accident (10 - 30 minutes) without operator actions to control RCS pressure, RCS pressure will reach a point of equilibrium based upon _____(2)_____.

(1) (2)

A. adequate Safety Injection Tank pressure B. adequate Atmospheric Dump Valve setpoint C. not adequate Safety Injection Tank pressure D. not adequate Atmospheric Dump Valve setpoint Facility: Waterford 3 Page 3 of 75

2014 NRC Exam RO Written Exam RO 4 OP-902-002, LOCA Recovery Procedure states that core uncovery and superheated conditions may be expected for up to ____(1)____ minutes. The crew is allowed to stay in OP-902-002 in this condition and are not required to exit to OP-902-008, Functional Recovery Procedure, provided _____(2)_____ .

(1) (2)

A. 15 at least one Charging pump is operating with flow > 40 gpm B. 30 at least one Charging pump is operating with flow > 40 gpm C. 15 safety injection flow is within the SI flow curves D. 30 safety injection flow is within the SI flow curves Facility: Waterford 3 Page 4 of 75

2014 NRC Exam RO Written Exam RO 5 The Steam Generator Low Flow trip is required to provide protection against a Reactor Coolant Pump ____(1)____ event because the DNBR _____(2)_____ .

(1) (2)

A. sheared shaft trip uses RCP speed sensors to measure flow B. sheared shaft algorithm is only valid with four RCPs running C. locked rotor trip uses RCP speed sensors to measure flow D. locked rotor algorithm is only valid with four RCPs running Facility: Waterford 3 Page 5 of 75

2014 NRC Exam RO Written Exam RO 6 Given:

The plant is at 100% power A rupture of the charging line has occurred Charging Pumps Header Isolation Valve (CVC 209) is isolated Letdown is isolated Charging flow can not be established through the normal charging pump discharge path and the crew has entered OP-901-112, Charging or Letdown Malfunction The crew will align the Charging pumps to discharge through HPSI header

____(1)____ and restore pressurizer level using the _____(2)_____ .

(1) (2)

A. A cold leg injection valves B. A hot leg injection valves C. B cold leg injection valves D. B hot leg injection valves Facility: Waterford 3 Page 6 of 75

2014 NRC Exam RO Written Exam RO 7 Given:

The plant is in mode 6 A loss of all Shutdown Cooling has occurred The crew has entered OP-901-131, Shutdown Cooling Malfunction RCS level is 15.13 feet CET temperature indicates 130 degrees F The plant has been shutdown for 50 days The calculated RCS time to boil is _____________ hours.

A. 38.9 B. 58.0 C. 41.2 D. 47.0 Facility: Waterford 3 Page 7 of 75

2014 NRC Exam RO Written Exam RO 8 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 high In accordance with OP-901-120, Pressurizer Pressure Control Malfunction, the CRS will direct the ATC to place the ____(1)____ controller in manual to restore pressurizer pressure. The ATC will _____(2)_____ the output of the controller that was placed in manual to restore pressurizer pressure to setpoint.

(1) (2)

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

2014 NRC Exam RO Written Exam RO 9 Given:

Plant operating at 90% power DRTS is out of service A loss of the 1A bus occurs and all 4 RCS low flow trip signals are generated, but NO Reactor Trip Circuit Breakers open. The BOP operator pushes the Reactor Trip push buttons on CP-8 Based on these actions, Reactor Trip Circuit Breakers __(1)__ should directly OPEN. If not, the BOP will manually open the __(2)__ feeder breakers.

(1) (2)

A. 1, 4, 5, and 8 31A and 31B B. 2, 3, 6, and 7 31A and 31B C. 1, 4, 5, and 8 32A and 32B D. 2, 3, 6, and 7 32A and 32B Facility: Waterford 3 Page 9 of 75

2014 NRC Exam RO Written Exam RO 10 With a Steam Generator Tube Rupture 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 A. 50 the environment 50 prevent a loss of subcooled margin B.

minimize the potential release to C. 100 the environment prevent a loss of subcooled margin D. 100 Facility: Waterford 3 Page 10 of 75

2014 NRC Exam RO Written Exam RO 11 Given:

An Excess Steam Demand has occurred for Steam Generator #1 Crew has entered OP-902-004, Excess Steam Demand Recovery Procedure Steam Generator # 1 level is 20% WR and lowering The CRS has directed the BOP to perform actions to stabilize RCS temperature when conditions permit The BOP will take actions to stabilize RCS temperature once ____(1)_____ .

The stabilization of RCS temperature is required to prevent _______(2)______ .

(1) (2)

CET temperature and RCS pressure rising above A.

pressurizer pressure HPSI shutoff head rise CET temperature and Pressurized Thermal Shock B. (PTS) pressurizer pressure rise C. CET temperature or Pressurized Thermal Shock pressurizer pressure (PTS) rise D. CET temperature or RCS pressure rising above pressurizer pressure HPSI shutoff head rise Facility: Waterford 3 Page 11 of 75

2014 NRC Exam RO Written Exam RO 12 Given:

Plant is at 100 percent power FWCS 1 and 2 in AUTOMATIC Which of the following conditions would result in entry to OP-902-006, Loss of Main Feedwater Recovery?

A. Loss of Offsite Power B. S/G #1 Wide Range Level 96 percent C. Both Steam Generators 75% NR D Condenser vacuum 13 in Hg Facility: Waterford 3 Page 12 of 75

2014 NRC Exam RO Written Exam RO 13 Given:

At 1800, a reactor trip occurred due to a Station Blackout At 1810, the crew entered OP-902-005, Station Blackout Recovery At 1815, the CRS directs the ATC operator to reduce battery loads Which of the following describes the clock time limit to accomplish these actions and the reason for those actions?

A. 1845; meet two hour coping time for 125 VDC buses to carry vital loads.

B. 1830; meet two hour coping time for125 VDC buses to carry vital loads.

C. 1845; meet four hour coping time for 125 VDC buses to carry vital loads.

D. 1830; meet four hour coping time for 125 VDC buses to carry vital loads.

Facility: Waterford 3 Page 13 of 75

2014 NRC Exam RO Written Exam RO 14 Given:

A Loss of Offsite power has occurred Crew has entered OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery SUPS MA was lost during the event Auxiliary Component Cooling Water (ACCW) pumps will ____(1)_____ . CC HX A ACC Outlet TCV (ACC-126A) must be manually throttled because ACCW flow is reading ____(2)______ gpm at CP-33.

(1) (2) 0 A. start

> 4000 B. start 0

C. require a manual start

> 4000 D. require a manual start Facility: Waterford 3 Page 14 of 75

2014 NRC Exam RO Written Exam RO 15 Given:

Reactor has tripped due to a Grid Disturbance SUPS MA is de-energized The BOP is verifying Station Loads are energized per OP-902-000, Standard Post Trip Actions The minimum Vital AC instrument channel(s) required for electrical train A is

___(1)_____. The vital instrument channel(s) ensures _______(2)______ is available.

(1) (2)

A. not met control power for remote operation of breakers B. not met monitoring and limited control of other safety functions C. met control power for remote operation of breakers D.

monitoring and limited control of other met safety functions Facility: Waterford 3 Page 15 of 75

2014 NRC Exam RO Written Exam RO 16 Given:

An Excess Steam Demand Event has occurred At time 1630, a Containment Spray Actuation Signal has been initiated.

Reactor Coolant Pumps must be secured no later than time ___(1)_____.

Reactor Coolant Pumps (RCPs) are secured to prevent _______(2)______ .

(1) (2)

A. 1640 RCP seal failure B. 1640 damage to the RCP bearings C. 1633 RCP seal failure D. 1633 damage to the RCP bearings Facility: Waterford 3 Page 16 of 75

2014 NRC Exam RO Written Exam RO 17 Given:

Plant is at 100% power WCT A basin level was lowered to 95% due to maintenance STA reports rising temperature on the WCT B basin When the WCT B basin temperature rises above the Technical Specification limit of ____(1)_____ then _____(2)_____ train(s) of the Ultimate Heat Sink will be considered inoperable.

(1) (2)

A. 86 F only one B. 86 F both C. 89 F only one D. 89 F both Facility: Waterford 3 Page 17 of 75

2014 NRC Exam RO Written Exam RO 18 Given:

An extended loss of Offsite power has occurred The crew is performing actions in OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery Instrument and Station Air Compressors are unavailable The crew is performing actions in OP-901-511, Instrument Air Malfunction To maintain ____(1)___ , Essential Air is aligned in accordance with the appropriate _____(2)_____.

(1) (2)

A. containment integrity Emergency Operating procedure B. desired EFW flow Offnormal Operating procedure C. desired EFW flow Emergency Operating procedure D. containment integrity Offnormal Operating procedure Facility: Waterford 3 Page 18 of 75

2014 NRC Exam RO Written Exam RO 19 Given:

Plant is at 100% power All CEAs are fully withdrawn ONE (1) CEA from Reg Group 4 drops into the core RCS pressure reduces to a minimum of 2210 PSIA Proportional heaters are at 100% firing rate Backup heaters are in AUTO and are not energized The crew enters OP-901-102, CEA or CEDMCS Malfunctions The crew will match Tave and Tref using turbine load and ____(1)_____. The pressurizer pressure control system _____(2)_____ functioning properly.

(1) (2)

A. CEA manipulations is not B. RCS boron changes is not C. RCS boron changes is D. CEA manipulations is Facility: Waterford 3 Page 19 of 75

2014 NRC Exam RO Written Exam RO 20 Given:

A Reactor trip and Loss of Offsite Power has occurred Three CEAs are stuck out on the Reactor trip Emergency boration is in progress using BAM pump A After five minutes, the RAB watch reports a large lube oil leak on EDG A and the CRS directs securing EDG A by pulling the overspeed trip mechanism. Which of the following actions should the crew take as a result of the changing plant conditions?

A. Restore Emergency Boration using BAM Pump B.

B. Restore Emergency Boration using the Gravity Feed valves.

C. Commence a plant cooldown to 400°F using ADVs and EFW.

D. Depressurize the RCS to less than 1400 psia and initiate HPSI flow into one cold leg.

Facility: Waterford 3 Page 20 of 75

2014 NRC Exam RO Written Exam RO 21 Given:

The plant is in Mode 5 RCS level is 19.0 feet The last OP-903-090 Shutdown Margin calculated a Keff of 0.965 Charging pump A and AB are in operation to support RCS CRUD cleanup Charging pump B breaker is racked out Startup Channel #2 has just failed high Which describes all required actions to comply with Tech Specs 3.1.2.9?

A. Isolate all Primary Water flow paths to the RCS.

B. Determine RCS boron concentration within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and every 90 minutes thereafter.

C. Determine RCS boron concentration within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, isolate all Primary Makeup Water flow paths to the RCS. Secure an additional charging pump and rack out the pump breaker.

D. Determine RCS boron concentration within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, Isolate all Primary Makeup Water flow paths to the RCS and secure the remaining charging pumps.

Facility: Waterford 3 Page 21 of 75

2014 NRC Exam RO Written Exam RO 22 Given:

A Steam Generator Tube leak on #1 Steam Generator is in progress The crew is performing the actions in OP-901-201, Steam Generator Tube Leakage or High Activity The crew will perform a plant cooldown using the ____(1)_____ .

Steam Generator #1 will be isolated when ____(2)_____ temperature is lowered to 520° F.

(1) (2)

A. Atmospheric Dump cold leg Valves B. Atmospheric Dump hot leg Valves C. Steam Bypass Control hot leg System D. Steam Bypass Control cold leg System Facility: Waterford 3 Page 22 of 75

2014 NRC Exam RO Written Exam RO 23 During a LOCA or Steam Line Break in Containment, the _____(1)______

Radiation Monitor(s) will read erroneously _____(2)______ while Containment temperature is rising.

(1) (2)

A. Containment PIG low B. Containment PIG high C. Containment High Range low D. Containment High Range high Facility: Waterford 3 Page 23 of 75

2014 NRC Exam RO Written Exam RO 24 Per TS 3.7.1.7, Atmospheric Dump Valves, the Atmospheric Dump Valve controller setpoints are required to be operable prior to exceeding ____(1)____

percent power. The basis for this requirement is to mitigate the effects of a

____(2)_____.

(1) (2)

A. 70 Small Break LOCA B. 70 Station Blackout C. 85 Small Break LOCA D. 85 Station Blackout Facility: Waterford 3 Page 24 of 75

2014 NRC Exam RO Written Exam RO 25 Given:

Chemistry reports a high RCS Activity in the RCS The crew has entered OP-901-410, High Activity in the Reactor Coolant System Per OP-901-410, the crew will ___________.

A. Start a backup Charging Pump to maximize letdown flow through the Purification Ion Exchanger B. Place a standby Purification Ion Exchanger in service to remove more activated products C. Bypass the Purification Ion Exchanger to prevent contamination of the Purification Ion Exchanger resin D. Stop backup Charging Pumps to minimize contamination of Purification Ion Exchanger resin Facility: Waterford 3 Page 25 of 75

2014 NRC Exam RO Written Exam RO 26 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 26 of 75

2014 NRC Exam RO Written Exam RO 27 Given:

Emergency Feedwater Pump AB is tagged for maintenance REACTOR TRIP occurred due to a loss of main feedwater On the trip, all offsite and onsite AC power was lost Both steam generator levels indicate 0% WR Both steam generator pressures indicate 15 psia Emergency Feedwater Pump B is now available. Which of the following describes the appropriate method for restoring feedwater?

A. Slowly restore feed to ONE SG.

B. Slowly restore feed to BOTH SGs.

C. Rapidly restore feed to ONE SG.

D. Rapidly restore feed to BOTH SGs.

Facility: Waterford 3 Page 27 of 75

2014 NRC Exam RO Written Exam RO 28 OP-902-005, Station Blackout Recovery, directs the operator to verify closed the CCW non safety header containment isolation valves, CC-641, CC-710, ad CC-713. What is the reason for this?

A. To prevent running out the CCW pumps B. To prevent thermal shocking the RCP seals C. To prevent thermal shocking the CEDM coolers D. To prevent water hammer in the Containment Building piping Facility: Waterford 3 Page 28 of 75

2014 NRC Exam RO Written Exam RO 29 Given:

A Plant startup is in progress The crew is purging the VCT to establish a Hydrogen blanket in accordance with section 8.19 of OP-002-005, Chemical and Volume Control Procedure The ATC is directed to raise VCT level to 90%

The crew will be required to align the VCT Inlet/Bypass Valve, CVC-169, control switch to the ____(1)_____ position to prevent CVC-169 from diverting to the

____(2)____ on a high level.

(1) (2)

A. VCT Boric Acid Condensate Tanks B. VCT Hold-Up tanks C. Mid Hold-up tanks D. Mid Boric Acid Condensate Tanks Facility: Waterford 3 Page 29 of 75

2014 NRC Exam RO Written Exam RO 30 Given:

Shutdown Cooling (SDC)Train B is in service Component Cooling Water (CCW) to SDC Heat Exchanger B was lost 10 minutes ago Reactor Coolant System temperature is 220 degrees The crew has entered OP-901-131, Shutdown Cooling Malfunction Low Pressure Safety Injection Pump B has been secured Per OP-901-131, Shutdown Cooling Malfunction, the crew must reinitiate

____(1)____ flow to SDC Heat Exchanger B slowly to prevent damage to

_____(2)_____ .

(1) (2)

A. Component Cooling Safety Injection piping Water B. Component Cooling Component Cooling Water Piping Water C. Shutdown Cooling Safety Injection piping D. Shutdown Cooling Component Cooling Water Piping Facility: Waterford 3 Page 30 of 75

2014 NRC Exam RO Written Exam RO 31 Following a large break LOCA with a failure of ESFAS to automatically initiate a SIAS, the Technical Specification Safety Limit for the ____(1)_____ temperature could exceed its melting threshold of _______(2)______ degrees without operator intervention.

(1) (2)

A. cladding 5080 B. cladding 3350 C. fuel centerline 5080 D. fuel centerline 3350 Facility: Waterford 3 Page 31 of 75

2014 NRC Exam RO Written Exam RO 32 Which of the following describes the interlock setpoint associated with SI-401A, RC Loop 2 SHDN Cooling Upstream Isolation?

A. Can only be opened if RCS pressure is < 368 psia and RCS temperature is less than 350° F.

B. Can only be opened if RCS pressure is < 368 psia and can only be closed if LPSI pump A is off.

C. Can only be opened if RCS pressure is < 386 psia and can only be closed if LPSI pump A is off.

D. Can only be opened if RCS pressure is < 386 psia and RCS temperature is less than 350° F.

Facility: Waterford 3 Page 32 of 75

2014 NRC Exam RO Written Exam RO 33 A Steam Generator Tube Rupture has occurred that resulted in an automatic SIAS/CIAS.

Which of the following could result in a Quench Tank Rupture Disc failure and rising containment pressure, due to automatic alignment to the Quench Tank?

A. RCP Control Bleed Off B. RCP Vapor Seal Leak Off C. Reactor Head Vent Header D. Pressurizer Vent Header Facility: Waterford 3 Page 33 of 75

2014 NRC Exam RO Written Exam RO 34 Given:

The crew is performing a fill and drain of the Quench Tank to reduce Quench Tank temperature in accordance with OP-007-001, Boron Management The crew will fill the Quench Tank with ____(1)____ and then drain the Quench Tank to the _____(2)_____ .

(1) (2)

A. Primary Makeup (PMU) Equipment Drain Tank B. Primary Makeup (PMU) Reactor Drain Tank C. Condensate Makeup (CMU) Equipment Drain Tank D. Condensate Makeup (CMU) Reactor Drain Tank Facility: Waterford 3 Page 34 of 75

2014 NRC Exam RO Written Exam RO 35 Given:

At time 0205, the crew manually initiated a SIAS and CIAS due to a Steam Generator Tube Rupture event.

At time 0210, CCW Pump B tripped The crew has diagnosed to OP-902-007, Steam Generator Tube Rupture Recovery Procedure Station loads are powered from the Startup Transformers To prevent damage to Emergency Diesel Generator B, the crew must align CCW flow before time ____(1)____ . If CCW flow cannot be restored to EDG B, the diesel will be secured using the _____(2)_____ .

(1) (2)

A. 0220 emergency Shutdown push buttons on CP-1 B. 0220 overspeed trip plunger C. 0235 overspeed trip plunger D. 0235 emergency Shutdown push buttons on CP-1 Facility: Waterford 3 Page 35 of 75

2014 NRC Exam RO Written Exam RO 36 Given:

The crew has entered OP-901-130, Reactor Coolant Pump Malfunction due to a high bearing temperature on RCP 2B The CRS has directed the BOP operator to lower RCP 2B bearing temperature using DCT fans Per OP-901-130, Reactor Coolant Pump Malfunction, CCW temperature should be maintained above ____(1)_____ °F to prevent _______(2)______ .

(1) (2) degradation of the reactor coolant A. 75 pump seals essential chiller trips on low B. 75 refrigerant pressure degradation of the reactor coolant C. 60 pump seals essential chiller trips on low refrigerant D. 60 pressure Facility: Waterford 3 Page 36 of 75

2014 NRC Exam RO Written Exam RO 37 Given:

Plant is at 100% power A loss of all Pressurizer heaters has occurred The crew has entered OP-901-120, Pressurizer Pressure Control Malfunction Pressurizer Level Setpoint source input has been shifted at CP-31 and a plant shutdown has commenced in accordance with OP-010-005, Plant Shutdown During the shutdown, the crew is required to ____(1)____ . Pressurizer level setpoint will be controlled _____(2)_____ .

(1) (2)

A. maintain pressurizer manually by the operator level constant B. raise pressurizer level automatically from the Reactor Regulating System C. maintain pressurizer automatically from the level constant Reactor Regulating System D. raise pressurizer level manually by the operator Facility: Waterford 3 Page 37 of 75

2014 NRC Exam RO Written Exam RO 38 Which of the following is correct in relation to the DNBR-Low trip?

A. The Reactor Protection Trip setpoint is 1.24 and is automatically bypassed below the 10 E-4 bistable setpoint.

B. The Reactor Protection Trip setpoint is 1.24 and may be bypassed by manually enabling the operating bypass below the 10 E-4 bistable setpoint.

C. The Reactor Protection Trip setpoint is 1.26 and is automatically bypassed below the 10 E-4 bistable setpoint.

D. The Reactor Protection Trip setpoint is 1.26 and may be bypassed by manually enabling the operating bypass below the 10 E-4 bistable setpoint.

Facility: Waterford 3 Page 38 of 75

2014 NRC Exam RO Written Exam RO 39 Given:

Pressurizer pressure is 1650 PSIA and slowly lowering Containment pressure is 16.7 and slowly rising Steam Generator 1 pressure is 700 PSIA and lowering Steam Generator 2 pressure is 680 PSIA and lowering Which of the following ESFAS signal(s) will have been generated?

A. SIAS only B. SIAS and CIAS only C. SIAS, CIAS, and MSIS only D. SIAS, CIAS, MSIS, and CSAS Facility: Waterford 3 Page 39 of 75

2014 NRC Exam RO Written Exam RO 40 Containment Fan Cooler C is powered from which bus?

A. SWGR 31A B. SWGR 31B C. MCC 317A D. MCC 317B Facility: Waterford 3 Page 40 of 75

2014 NRC Exam RO Written Exam RO 41 Given:

Plant is at 100% power Containment Fan Coolers A, B, & D are in operation CEDM Fans A and D are in operation Reactor is manually tripped and SIAS is manually actuated Which of the following describes the response during the event?

A. Containment Fan Coolers A, B, C, & D operate in slow speed. CEDM Fans A and D trip.

B. Only Containment Fan Coolers A, B, & D operate in slow speed. CEDM Fans A and D trip.

C. Containment Fan Coolers A, B, C, & D operate in slow speed. CEDM Fans A and D continue to operate.

D. Only Containment Fan Coolers A, B, & D operate in slow speed. CEDM Fans A and D continue to operate.

Facility: Waterford 3 Page 41 of 75

2014 NRC Exam RO Written Exam RO 42 Given:

A large break LOCA occurred Containment Spray Line A pipe failure occurred in the -35 Wing Area Which of the following conditions describes the operational concern for the Emergency Core Cooling systems following RAS initiation?

The ___(1)___ will not have adequate water inventory for operation of the

___(2)___ pumps.

(1) (2)

A. RWSP LPSI B. RWSP HPSI C. SI sump LPSI D. SI sump HPSI Facility: Waterford 3 Page 42 of 75

2014 NRC Exam RO Written Exam RO 43 Given:

A reactor trip occurred The crew is performing OP-902-000, Standard Post Trip Actions SG #1 and SG #2 pressures are 1060 psia SG #1 and SG #2 NR levels are 5% and steady Main Feedwater is available Tc indicate 555° F and stable The crew is required to raise feedwater flow to maintain SG levels ____(1)____

NR and verify _____(2)_____ being restored back into the bands required by OP-902-000 using the SBCS.

(1) (2)

A. 10-76% RCS temperature only is B. 10-76% RCS temperature and SG pressures are C. 55% - 70% RCS temperature and SG pressures are D. 55% - 70% RCS temperature only is Facility: Waterford 3 Page 43 of 75

2014 NRC Exam RO Written Exam RO 44 Given:

The plant is at 100% power ES-205, ES to #2 Heaters Isolation closed causing all three heater drain pumps to trip The crew has entered OP-901-221, Secondary System Transient Which of the following describes the response during the event?

A. Condensate Polisher D/P will lower, both Main Feedwater Pumps will trip 10 seconds after reaching the suction pressure trip setpoint.

B. Condensate Polisher D/P will lower, one Main Feedwater Pump will trip 10 seconds after reaching the suction pressure trip setpoint.

C. Condensate Polisher D/P will rise, both Main Feedwater Pumps will trip 10 seconds after reaching the suction pressure trip setpoint.

D. Condensate Polisher D/P will rise, one Main Feedwater Pump will trip 10 seconds after reaching the suction pressure trip setpoint.

Facility: Waterford 3 Page 44 of 75

2014 NRC Exam RO Written Exam RO 45 Given:

• A plant power reduction is in progress

• Reactor power is 40% and slowly lowering

• Main Feedwater pumps A & B are providing Feedwater in AUTO mode

• The BOP reports Feedwater Master Controller #1 output has failed LOW

• The BOP reports NO response while attempting to operate the Master Controller #1 in MANUAL Which of the following should be operated in MANUAL mode to restore and maintain Steam Generator level within band?

A. Main Feedwater Regulating valve #1 M/A station only B. Startup Feedwater Regulating valve #1 M/A station only C. Main Feedwater Pump Speed #1 M/A station only D. Both the SUFRV #1 M/A station and Main Feedwater Pump Speed #1 M/A station Facility: Waterford 3 Page 45 of 75

2014 NRC Exam RO Written Exam RO 46 Given:

The reactor has tripped Pressurizer Pressure is 1800 PSIA and lowering SG #1 Level is 51% WR and lowering SG #2 Level is 43% WR and stable SG #1 Pressure is 645 PSIA SG #2 Pressure is 710 PSIA Containment Pressure is 15.2 PSIA and stable The initial response of Emergency Feedwater flows to the Steam Generators is

____(1)____ gpm to Steam Generator #1 and _____(2)_____ gpm to Steam Generator #2.

(1) (2)

A. 200 400 B. 200 200 C. 0 400 D. 0 200 Facility: Waterford 3 Page 46 of 75

2014 NRC Exam RO Written Exam RO 47 Given:

An Excess Steam Demand has occurred SIAS, CIAS, and MSIS are present The crew is performing actions of OP-902-004, Excess Steam Demand Station loads are energized from the Startup transformers The CRS has directed the ATC to stabilize RCS pressure.

To restore pressurizer heaters, the crew will ________.

A. reset the back-up heater banks from CP-2 B. verify the 32A and 32 B feeder breakers closed on the sequencer after .5 seconds and then reset heater banks from CP-2 C. manually close the 32A and 32B feeder breakers after 205 seconds and then reset heater banks from CP-2 D. reset the SIAS, close the 32A and 32B feeder breakers and then reset heater banks from CP-2 Facility: Waterford 3 Page 47 of 75

2014 NRC Exam RO Written Exam RO 48 Given:

The plant has experienced a Station Blackout The crew has entered OP-902-005, Station Blackout The crew has completed the step for reducing battery loads The crew will monitor Spent Fuel Pool level using guidance located in A. OP-500-008, Annunciator response procedure B. OP-002-006, SFP Cooling and Purification C. OP-901-513, SFP Cooling Malfunction D. OP-902-008, Functional Recovery procedure Facility: Waterford 3 Page 48 of 75

2014 NRC Exam RO Written Exam RO 49 Given:

Plant is at 100% power EDG A is synchronized to the grid for a post-maintenance test EDG A output is 2.2 MW If a loss of A-DC occurs, Emergency Diesel Generator A will ____(1)____ and the Emergency Diesel Generator A output breaker will _____(2)_____ .

(1) (2)

A. trip trip open immediately B. trip remain closed C. remain running trip open immediately D. remain running remain closed Facility: Waterford 3 Page 49 of 75

2014 NRC Exam RO Written Exam RO 50 The CROAI Radiation monitors isolate the Control Room Ventilation (HVC) on a high radiation level to prevent Control Room staff from receiving a maximum dose of ___(1)___ for the ___(2)___ of the event.

(1) (2)

A. 5 rem duration B. 5 rem first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> C. 2 rem duration D. 2 rem first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Facility: Waterford 3 Page 50 of 75

2014 NRC Exam RO Written Exam RO 51 Given:

Reactor tripped due to a loss of Main Feedwater Crew entered OP-902-006, Loss of Main Feedwater Recovery Condensate Storage Pool (CSP) level is 35% and lowering with CMU-141, CSP LCV Bypass, open To prevent cavitation of the EFW Pumps, the transfer of EFW Pump suction to

____(1)_____ side(s) of Auxiliary Component Cooling Water (ACCW) must be completed before CSP level lowers to _______(2)______.

(1) (2)

A. both 11%

B. both 25%

C. one 11%

D. one 25%

Facility: Waterford 3 Page 51 of 75

2014 NRC Exam RO Written Exam RO 52 Given:

A Loss Of Coolant Accident (LOCA) is in progress Auxiliary Component Cooling Water (ACCW) Pump A tripped on overcurrent Component Cooling Water temperature is 90°F and rising All Dry Cooling Tower A fans are in SLOW speed operating in AUTO If Component Cooling Water System temperature continues to rise, all Dry Cooling Tower A fans start simultaneously in FAST speed when CCW temperature reaches ____(1)____ and Essential Chillers will swap to the WET tower mode when CCW temperature reaches _____(2)_____ .

(1) (2)

A. 100 °F 95 °F B. 92 °F 102 °F C. 100 °F 102 °F D. 92 °F 95 °F Facility: Waterford 3 Page 52 of 75

2014 NRC Exam RO Written Exam RO 53 Given:

Plant is at 100% power Instrument Air Header pressure is 115 PSIG An air leak occurs, causing Instrument Air Header pressure to drop to 92 PSIG.

The crew enters OP-901-511, Instrument Air Malfunction.

The crew will verify that SA-125, SA Backup Supply for IA Press Cntl valve, is

____(1)____ and IA-123, Instrument Air Dryer Bypass Solenoid valve, is

_____(2)_____ .

(1) (2)

A. open open B. closed open C. open closed D. closed closed Facility: Waterford 3 Page 53 of 75

2014 NRC Exam RO Written Exam RO 54 On a Loss of TGB-DC Bus, the reactor will be manually tripped when Instrument Air header pressure lowers to ____(1)___ due to a loss of power to

_____(2)_____.

(1) (2)

A. 80 IA and SA compressor unloader valves B. 80 Instrument Air Dryers C. 65 IA and SA compressor unloader valves D. 65 Instrument Air Dryers Facility: Waterford 3 Page 54 of 75

2014 NRC Exam RO Written Exam RO 55 Given:

Containment Pressure is 16.9 PSIA RCS Pressure is 1600 PSIA CC-641, CCW RCP Inlet Outside Isol Valve is OPEN BAM-133, Emergency Boration Valve is OPEN SI-343, SI Tanks Drain to RWSP Valve is CLOSED MS-120A, Main Steam Line 1 Normal Drain Valve is OPEN Which ONE of the following valves requires operator action for the current plant conditions?

A. CC-641 B. BAM-133 C. SI-343 D. MS-120A Facility: Waterford 3 Page 55 of 75

2014 NRC Exam RO Written Exam RO 56 Given:

Plant is at 90% power An inadvertent dilution event is in progress The crew entered OP-901-104, Inadvertent Positive Reactivity Addition The ATC reports that Reactor Coolant Tavg-Tref Hi annunciator is in Steam Bypass Control Valves are closed The crew will verify a ____(1)____ signal being sent to CEDMCS. This signal will prevent withdrawal of _____(2)_____ control element assemblies in the Auto Sequential mode.

(1) (2)

A. Automatic Withdrawal regulating group Prohibit (AWP)

B. Automatic Withdrawal all Prohibit (AWP)

C. Automatic Motion Inhibit regulating group (AMI)

D. Automatic Motion Inhibit all (AMI)

Facility: Waterford 3 Page 56 of 75

2014 NRC Exam RO Written Exam RO 57 Given:

Plant is steady state at 75% power Tavg is being maintained on program A Letdown malfunction has occurred, requiring letdown flow control valves to be placed in manual The CRS directs Pressurizer level to be restored to program level prior to placing the letdown flow control valves back in auto. What is the target level?

A. 45%

B. 46.5%

C. 49.5%

D. 51.5%

Facility: Waterford 3 Page 57 of 75

2014 NRC Exam RO Written Exam RO 58 Given:

Plant power is 100%

Safety Channel 1 and 2 High Voltage On Select Switches are positioned to Primary (PRI)

Safety Channel A middle detector has just failed low Describe the status of the Startup Channels.

A. Only Startup Channel 1 high voltage is on B. Only Startup Channel 2 high voltage is on C. Both Startup Channels high voltage are on D. Both Startup Channels high voltage is off Facility: Waterford 3 Page 58 of 75

2014 NRC Exam RO Written Exam RO 59 Given:

The in-service Pressurizer pressure control channel has just failed low Which of the following prevents a simultaneous Reactor Protection System (RPS) Trip bistable actuation?

A. Separate circuits are used for protection channel and control channel functions.

B. Each circuit is provided with two separate outputs; one for control channel, one for protection channel.

C. Isolation amplifiers from the output of each circuit ensure that feedback from the control signal will not affect the protection channel.

D. Circuit outputs are multiplexed to be processed separately by the control channel and protection channel circuitry.

Facility: Waterford 3 Page 59 of 75

2014 NRC Exam RO Written Exam RO 60 Core Exit Thermocouples are located ____(1)____ the fuel alignment plate and is the instrumentation used when verifying RCS temperature _____(2)_____ .

(1) (2)

A. below anytime less than four Reactor Coolant Pumps are running B. below during natural circulation conditions C. above during natural circulation conditions D. above anytime less than four Reactor Coolant Pumps are running Facility: Waterford 3 Page 60 of 75

2014 NRC Exam RO Written Exam RO 61 Given:

Plant tripped due to a Large Break LOCA event and TSC directed that both Hydrogen Recombiners were to be placed in service Hydrogen Recombiner A failed and was removed from service Hydrogen Recombiner B is operating with a setting of 25 KW output Hydrogen Analyzers indicate Containment H2 concentration of 4.2% and rising slowly The CRS directs the Hydrogen Recombiner B output raised in accordance with OP-008-006, using Attachment 11.2, to reduce Hydrogen concentration.

Post-LOCA Containment pressure is 17.7 PSIA and Pre-LOCA Containment Temperature was 105 F.

The final setting on the B potentiometer will be ____ KW to establish the required value.

A. 53 B. 55 C. 57 D. 59 Facility: Waterford 3 Page 61 of 75

2014 NRC Exam RO Written Exam RO 62 Given:

Plant is at 100% power Containment Purge is in progress in accordance with OP-002-010, Reactor Auxiliary Building HVAC and Containment Purge CAP-203, Containment Purge Exhaust Inside Containment, has failed closed In relation to the Containment Purge Malfunction and three minutes into the event, Containment Pressure will _____(1)______ because _____(2)______ .

(1) (2)

A. remain the same containment purge inlet dampers close when CAP-203 closes B. remain the same RAB normal Exhaust fan trips on low flow C. continue to rise containment purge outlet dampers are closed D. continue to rise RAB normal Exhaust fan trips on low flow Facility: Waterford 3 Page 62 of 75

2014 NRC Exam RO Written Exam RO 63 Given:

Plant is at 100% power A Gaseous Waste Discharge is in progress when the Waste Gas Flow and Radiation Recorder, GWM-IFRR-0648, fails The recorder cannot be immediately repaired Which of the following describes the impact of the failure, and the action required?

A. Waste Gas Discharge automatic isolation is inoperable; stop the release until the recorder is returned to operable status. The release may resume ONLY when a new release permit is issued.

B. Waste Gas Discharge automatic isolation is inoperable; stop the release until the recorder is returned to operable status. The release may resume under the existing release permit after verifying NO new additions to the WGD Tank(s) being released.

C. Waste Gas Discharge automatic isolation remains operable but flow indication is lost; verify the flow setpoint on GWM-309 remains below the limit specified on the release permit, and continue the release.

D. Waste Gas Discharge automatic isolation remains operable but flow indication is lost; estimate discharge flow rate by determining the change in GDT pressure over time to ensure flow rate remains within limits.

Facility: Waterford 3 Page 63 of 75

2014 NRC Exam RO Written Exam RO 64 Auxiliary Component Cooling Water (ACCW) Pump B is powered from which bus?

A. SWGR 31B B. SWGR 3B C. SWGR 1B D. SWGR 2B Facility: Waterford 3 Page 64 of 75

2014 NRC Exam RO Written Exam RO 65 Per FP-001-020, Fire Emergency/Fire Report, if a fire detector located in the Control Room or _____(1)______ room alarms, the control room will direct the TGB Switchgear Operator to the TGB Switchgear and the Field Operator to the

_____(2)______.

(1) (2)

A. cable vault +35 Relay Room B. cable vault Control Room C. Isolation Panel +35 Relay Room D. Isolation Panel Control Room Facility: Waterford 3 Page 65 of 75

2014 NRC Exam RO Written Exam RO 66 A licensee has NOT stood the required number of proficiency watches prior to the end of the calendar quarter. In addition to conducting a plant tour, which one of the following correctly describes the 10CFR55 provision for the licensee to perform licensed duties during the next quarter?

A. Active status may be continued provided the remaining proficiency watches are stood during the first month of the following calendar quarter.

B. Active status may be continued provided 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of under instruction watches are completed within the first month of the following calendar quarter.

C. The license must become inactive. 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of under instruction watches shall be stood to return the license to active status.

D. The license must become inactive. Seven 8-hour or five 12-hour under instruction watches shall be stood to return the license to active status.

Facility: Waterford 3 Page 66 of 75

2014 NRC Exam RO Written Exam RO 67 Per OI-042-000, Watch Station Process, coordinating activities outside of the Control Room is listed as a responsibility for the ____(1)____ and the

_____(2)_____ .

(1) (2)

A. Shift Manager extra Nuclear Plant operator B. Shift Manager At the Controls (ATC) operator C. Field Support extra Nuclear Plant operator Supervisor D. Field Support At the Controls (ATC) operator Supervisor Facility: Waterford 3 Page 67 of 75

2014 NRC Exam RO Written Exam RO 68 Given:

Plant is in a refueling outage and in DEFUEL mode Which one of the following completes the statement below?

The crew will declare the plant to be in Mode 6 when informed by the Refuel SRO that the first fuel bundle is located in the upender on the......

A. fuel handling building side and is capable of being transported to the containment side B. fuel handling building side and the transfer carriage has been sent to the containment side C. containment building side and the containment upender is vertical D. containment building side and is grappled by the refueling machine Facility: Waterford 3 Page 68 of 75

2014 NRC Exam RO Written Exam RO 69 Given:

The crew is performing actions in OP-010-003, Plant Startup The CRS has directed the ATC to perform a VCT Makeup using the Dilute Makeup Mode per OP-002-005, Chemical and Volume Control Per OI-042-000, Watch Station Process, a ____(1)____ should be performed prior to and immediately following the PMU addition and the evolution should be cross-checked by _____(2)_____ .

(1) (2)

A. shift update verifying the pre-power dependent insertion limit annunciator is clear B. shift update comparing what was placed in the batch counter to the totalizer reading C. notification to the RAB comparing what was placed in the watch batch counter to the totalizer reading D. notification to the RAB verifying the pre-power dependent watch insertion limit annunciator is clear Facility: Waterford 3 Page 69 of 75

2014 NRC Exam RO Written Exam RO 70 Given:

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

(1) (2)

A. the work package OP-100-010, Att. 7.1, TS/TRM Entry Guidelines B. OP-100-010, Att. 7.1, OP-100-010, Att. 7.2, EOS TS/TRM Entry Checklist Guidelines C. the work package OP-100-010, Att. 7.2, EOS Checklist D. OP-100-010, Att. 7.1, OP-100-010, Att. 7.1, TS/TRM TS/TRM Entry Entry Guidelines Guidelines Facility: Waterford 3 Page 70 of 75

2014 NRC Exam RO Written Exam RO 71 Which ONE of the following radiation monitors (1) is specified as the primary monitor with the designed sensitivity to measure small Primary to Secondary leakage AND which radiation monitor (2) is specified as qualified for use if the primary monitor fails?

(1) (2)

A MS Line N-16 Monitor Steam Generator 1 and 2 Blowdown PRM-RE5501-1 (2) PRM-IRE-0100X B MS Line N-16 Monitor AE Discharge Monitor PRM-RE5501-1 (2) PRM-IRE-0004 C AE Discharge Monitor Steam Generator 1 and 2 Blowdown PRM-IRE-0004 PRM-IRE-0100X D AE Discharge Monitor MS Line N-16 Monitor PRM-IRE-0004 PRM-RE5501-1 (2)

Facility: Waterford 3 Page 71 of 75

2014 NRC Exam RO Written Exam RO 72 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 72 of 75

2014 NRC Exam RO Written Exam RO 73 Per OP-100-017, Emergency Operation Procedure Implementation Guide:

Simultaneous performance of more than one Emergency Operating (EOP)

Recovery Procedure is ____(1)____ . Simultaneous performance of an Off-Normal Operating Procedure and an Emergency Operating Recovery Procedure is allowed _____(2)_____ .

(1) (2)

A. allowed at the discretion of the CRS B. allowed only if the Emergency Operating Recovery Procedure directs its use C. not allowed at the discretion of the CRS D. not allowed only if the Emergency Operating Recovery Procedure directs its use Facility: Waterford 3 Page 73 of 75

2014 NRC Exam RO Written Exam RO 74 Given:

An Excess Steam Demand is in progress The crew is performing required actions in OP-902-004, Excess Steam Demand Chemistry is unable to obtain an RCS Boron sample Reactor power is dropping Emergency Boration may be terminated if which of the following conditions are met?

A. Pressurizer level is approaching the upper end of the control band and HPSI Throttle Criteria is being met.

B. Pressurizer level is approaching the upper end of the control band and a Shutdown Margin calculation is performed as soon as plant conditions permit.

C. Reactor Vessel Level Monitoring indicates the core is covered and HPSI Throttle Criteria is being met.

D. Reactor Vessel Level Monitoring indicates the core is covered and a Shutdown Margin calculation is performed as soon as plant conditions permit.

Facility: Waterford 3 Page 74 of 75

2014 NRC Exam RO Written Exam RO 75 Per OP-100-017, Emergency Operating Procedure Implementation Guide, which of the following criteria (if any) would allow the crew to remain in a selected Optimal recovery procedure if the safety function status checklist is not being met?

A. The crew must exit to the functional recovery procedure any time the safety function status checklist is not met.

B. Two events are in progress and a shift brief is performed which must include the Shift Manager.

C. A single event is in progress and transitioning to the functional recovery procedure will provide no additional guidance to correct the failed safety function.

D. The reason for not meeting the safety function is known and TSC concurrence must be obtained.

Facility: Waterford 3 Page 75 of 75

2014 NRC Exam SRO Written Exam SRO 1 Given:

• Plant is at 15% power

• The crew is making preparations to synch the Main Generator to the grid

• Main Feedwater Pump A is operating

• Startup Transformer B trips on the Sudden Pressure Relay resulting in a reactor trip

• Pressurizer pressure is 1950 PSIA and rising

• Pressurizer level is 15% and stable

• One backup Charging Pump has started

• RCS Temperature is 541 F and rising

• EDG B is running loaded

• NAO reports no precipitation Which of the following describes the correct procedure entry and required action?

A. OP-902-001, Reactor Trip Recovery and perform Appendix 20, Operation of DCT Sump Pumps within 30 minutes B. OP-902-001, Reactor Trip Recovery and start an additional Charging Pump C. OP-902-003, Loss of Offsite Power/ Loss of Forced Circulation Recovery and perform Appendix 20, Operation of DCT Sump Pumps within 30 minutes D. OP-902-003, Loss of Offsite Power/ Loss of Forced Circulation Recovery and start an additional Charging Pump Facility: Waterford 3 Page 1 of 25

2014 NRC Exam SRO Written Exam SRO 2 Given:

The plant is at 100% power The AB bus is aligned to the B Train HPSI Pumps A and B are aligned for service LPSI Pump A is tagged out Technical Specification 3.5.2.a has been entered HPSI Pump B breaker develops a malfunction that causes the breaker to be unable to close. Regarding ECCS equipment available to mitigate a SBLOCA, which of the following is true in accordance with Technical Specifications?

A. TS 3.5.2.b is applicable and may be exited once the AB HPSI pump is aligned to replace the B HPSI pump.

B. TS 3.5.2.b is applicable and may ONLY be exited when one ECCS pump is restored.

C. TS 3.0.3 is applicable and may be exited once the AB HPSI pump is aligned to replace the B HPSI pump.

D. TS 3.0.3 is applicable and may ONLY be exited when one ECCS pump is restored.

Facility: Waterford 3 Page 2 of 25

2014 NRC Exam SRO Written Exam SRO 3 Given:

A LOCA has occurred The crew is performing the actions of OP-902-002, LOCA Recovery Procedure Pressurizer level indicates 10% and rising Steam Generator #1 level is 51% NR and rising Steam Generator #2 level is 50% NR and rising Both Steam Generator levels are being controlled with EFW in manual CET temperature is 430 degrees F RCS pressure is 524 psia QSPDS Reactor Vessel level 5 indicates NOT VOIDED Containment temperature is 210 degrees F Which of the following must the CRS direct prior to the crew throttling HPSI flow?

A. Raise vessel plenum level until Vessel Plenum level indicates 100%.

B. Raise Steam Generator levels to greater than 55% NR.

C. Raise subcooling to 28° F.

D. Raise pressurizer level to greater than 23%.

Facility: Waterford 3 Page 3 of 25

2014 NRC Exam SRO Written Exam SRO 4 Given:

• Plant is operating at 100% with the following Annunciators in alarm:

o CCW Surge Tank Level LO-LO on Panel M & N o CCW FLOW LO red alarms for all Reactor Coolant Pumps o Controlled Bleedoff Temperature Hi alarms for all Reactor Coolant Pumps

• CCW Surge Tank A level is 0%.

• CCW Surge Tank B level lowered to 15% but is being restored via the CCW Makeup Pumps The crew has entered OP-901-510, CCW System Malfunction. To mitigate this event, the CRS will complete subsection ____(1)____. The crew will be required to _____(2)_____.

(1) (2)

A. E3 High System Temperature isolate the leak and then and transition to E1 System restore flow to the AB loop Leakage B. E3 High System Temperature restore flow to the AB loop and transition to E1 System and then isolate the leak Leakage C. E1 System Leakage only restore flow to the AB loop and then isolate the leak D. E1 System Leakage only isolate the leak and then restore flow to the AB loop Facility: Waterford 3 Page 4 of 25

2014 NRC Exam SRO Written Exam SRO 5 Given:

Plant at 100% power and steady state N-16 Radiation Monitor for Steam Generator 2 reads 65 GPD PSLR reads 85 GPD Chemistry reports primary to secondary leakage in Steam Generator 2 is consistent with PSLR Technical Specification 3.4.5.2, Operational Leakage, is _____(1)______.

The Nuclear Energy Institute recommended a limit of 150 GPD for primary to secondary leakage; however, the limit in Technical Specification 3.4.5.2 is more restrictive ____(2)____.

(1) (2)

A. not met to ensure the magnitude of leakage does not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems B. met to ensure the magnitude of leakage does not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems C. not met because the proximity of the east ADV to the east control room air intake could result in unacceptable radiological consequences D. met because the proximity of the east ADV to the east control room air intake could result in unacceptable radiological consequences Facility: Waterford 3 Page 5 of 25

2014 NRC Exam SRO Written Exam SRO 6 Given:

Plant is in Mode 1 The Shift Manager receives a call from the grid operator informing him that Waterfords post-trip grid voltage would be 222 kV.

Current Line A and B grid voltages do NOT meet the requirements of OP-903-066, Electrical Breaker Alignment Check Based on this information, the crew should ____(1)____ because ____(2)_____.

(1) (2)

A. declare both AC off-site sufficient power may not exist to circuits inoperable and enter supply safety related equipment both Tech Spec 3.8.1.1 and needed for the mitigation of a TRM 3.8.1.1 design basis accident B. declare both AC off-site post trip excessive current from this circuits inoperable and enter reduced voltage will actuate the both Tech Spec 3.8.1.1 and SUT protective relays TRM 3.8.1.1 C. enter only TRM 3.8.1.1 sufficient power may not exist to supply safety related equipment needed for the mitigation of a design basis accident D. enter only TRM 3.8.1.1 post trip excessive current from this reduced voltage will actuate the SUT protective relays Facility: Waterford 3 Page 6 of 25

2014 NRC Exam SRO Written Exam SRO 7 Given:

Plant is stable at 100% power RCS Temperature loop1 Hot Leg (RC-ITI-0111X) has failed low The crew has entered OP-901-110, Pressurizer Level Control Malfunction As a result of the failed temperature instrument, Letdown flow will ____(1)____.

The CRS will implement subsection _____(2)_____ of OP-901-110.

(1) (2)

A. rise E1 Pressurizer Level Control Channel Malfunction B. lower E1 Pressurizer Level Control Channel Malfunction C. rise E2 Pressurizer Level Setpoint Malfunction D. lower E2 Pressurizer Level Setpoint Malfunction Facility: Waterford 3 Page 7 of 25

2014 NRC Exam SRO Written Exam SRO 8 Given:

• Plant is operating at 100%

• The crew is discharging Gas Decay Tanks

• The following annunciators is received:

• Waste Gas Disch Rad High Dryer/Mon Trouble (Cabinet G, E-10)

• The ATC operator informs the CRS that the discharge activity exceeds the Gaseous Release Permit set point The CRS will direct the crew to verify the ____(1)____ high alarm set point set in accordance with the release permit. The annunciator response procedure will refer the CRS to ____(2)_____ and close GWM-309, Waste Gas Discharge Flow Control.

(1) (2)

A. Plant Stack PIG Monitor A or B OP-007-003, Gaseous Waste (PRM-IRE-0100.1 or 0100.2) Management B. Plant Stack PIG Monitor A or B OP-901-413, Waste Gas (PRM-IRE-0100.1 or 0100.2) Discharge High Radiation C. Gaseous Waste Management OP-901-413, Waste Gas Monitor (PRM-IRE-0648) Discharge High Radiation D. Gaseous Waste Management OP-007-003, Gaseous Waste Monitor (PRM-IRE-0648) Management Facility: Waterford 3 Page 8 of 25

2014 NRC Exam SRO Written Exam SRO 9 Given:

• The site is under attack from armed adversaries. The crew has entered OP-901-523, Security Events

• The site has been notified by Security that the Control Room is the target of the attack.

The CRS will enter OP-901-502, subsection ____(1)____. OP-901-523, Security Events, states that the NRC Headquarters Operation Center shall be notified within _____(2)_____ minutes of discovery of the security based event.

(1) (2)

A. E1 Control Room Evacuation with 60 Fire B. E1 Control Room Evacuation with 15 Fire C. E2 Control Room Evacuation 15 D. E2 Control Room Evacuation 60 Facility: Waterford 3 Page 9 of 25

2014 NRC Exam SRO Written Exam SRO 10 Given:

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

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

Representative CET temperature and RCS pressure start to rise.

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

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

(1) (2)

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

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

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

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

Functional Recovery Facility: Waterford 3 Page 10 of 25

2014 NRC Exam SRO Written Exam SRO 11 Given:

A SGTR event is in progress with S/G #2 faulted The crew has completed the rapid cooldown of the RCS RCS THOT is 518 °F RCS TCOLD is 504 °F RCS pressure is 1450 PSIA S/G #2 pressure is 650 PSIA Reactor Coolant Pumps 1B and 2B are operating OP-902-007, Steam Generator Tube Rupture Recovery directs the reduction of RCS pressure.

Based on plant conditions, the CRS should direct the ATC to reduce RCS pressure, with a MINIMUM pressure of A. 700 PSIA B. 940 PSIA C. 1100 PSIA D. 1200 PSIA Facility: Waterford 3 Page 11 of 25

2014 NRC Exam SRO Written Exam SRO 12 Given:

RCS temperature is 340°F RCS pressure is 380 PSIA SDC Train A is in service SDC Train B is in standby The following annunciators are received:

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

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

LOOP 1 SDC RELIEF VLV ACTIVE (Cabinet N, A-17)

LOOP 2 SDC RELIEF VLV ACTIVE (Cabinet M, A-7)

The CRS will direct the BOP to FIRST ____(1)____ in accordance with the guidance in

_____(2)_____.

(1) (2)

A. secure HPSI Pumps OP-901-131, Shutdown Cooling Malfunction B. secure LPSI Pump B OP-901-131, Shutdown Cooling Malfunction C. secure LPSI Pump B OP-901-504, Inadvertent ESFAS Actuation D. secure HPSI Pumps OP-901-504, Inadvertent ESFAS Actuation Facility: Waterford 3 Page 12 of 25

2014 NRC Exam SRO Written Exam SRO 13 The following plant conditions exist:

The plant is in Mode 1 Channel B Wide Range Pressure transmitter (RC-IPI-0102B) has failed low Appropriate bistables have been bypassed on Channel B Subsequently, Channel C Lo Pressurizer Pressure bistable has failed in the actuated state.

If the CRS directs bypassing the Channel C Lo Pressurizer Pressure bistable, then:

A. Channel B Lo Pressurizer pressure remains bypassed and Channel C Lo Pressurizer pressure remains bypassed. No additional actions are required.

B. Channel B Lo Pressurizer pressure remains bypassed, Channel C does not bypass. Channel C must be placed in trip to comply with Tech Spec 3.3.1.

C. A Reactor Trip and SIAS occurs. OP-901-504, Inadvertent ESFAS Actuation directs that Instrument Air will be restored to containment by opening IA-909, CNTMT ISOLATION INSTRUMENT AIR.

D. A Reactor Trip and SIAS occurs. OP-901-504, Inadvertent ESFAS Actuation directs that emergency boration may only be secured after Shutdown Margin is verified through Chemistry analysis.

Facility: Waterford 3 Page 13 of 25

2014 NRC Exam SRO Written Exam SRO 14 Given:

A failure has occurred that has resulted in a loss of DC control power to LPSI Pump B breaker only.

The control room received a LPSI PUMP B TRIP/TROUBLE annunciator.

Subsequently, a Large Break LOCA occurs Containment pressure is 22.8 PSIA and steady RCS pressure is 175 PSIA and lowering Low Pressure Safety Injection (LPSI) Pump A tripped on overcurrent In response to this event, the SRO should ____(1)___ and ____(2)____ to address the Inventory Control safety function.

(1) (2)

A. continue in OP-902-002, Loss realign CS Pump A to of Coolant Accident Recovery replace LPSI Pump A B. continue in OP-902-002, Loss locally close LPSI Pump B of Coolant Accident Recovery breaker using the pistol grip C. go to OP-902-008, Functional realign CS Pump A to Recovery replace LPSI Pump A D. go to OP-902-008, Functional locally close LPSI Pump B Recovery breaker using the pistol grip Facility: Waterford 3 Page 14 of 25

2014 NRC Exam SRO Written Exam SRO 15 Given:

Plant is at 100% power A loss of the 3B Safety bus has occurred All indications for this condition are normal with the following exceptions:

Auxiliary Cooling Water Pump (ACCW) B tripped at the 17 second load block All Emergency Diesel Generator (EDG) B Sequencer load block lights have extinguished EDG B Sequencer LOCKOUT light is LIT The ____(1)____ de-energized. The CRS will direct the crew to _____(2)_____.

(1) (2)

A. Train B loads only after secure EDG B IAW OP-009-block 17 are 002, Emergency Diesel Generator B. Train B loads only after rack down ACCW Pump B block 17 are breaker IAW OP-901-311, Loss of Train B Safety Bus C. Entire 3B safety bus is rack down ACCW Pump B breaker IAW OP-901-311, Loss of Train B Safety Bus D. Entire 3B safety bus is secure EDG B IAW OP-009-002, Emergency Diesel Generator Facility: Waterford 3 Page 15 of 25

2014 NRC Exam SRO Written Exam SRO 16 The following plant conditions exist:

The plant is MODE 6 and dry fuel operations are in progress Fuel Handling Building Normal Ventilation Train A is in service.

Two minutes ago the crew received a report of a dropped dry fuel cask in the Fuel Handling Building A Fuel Handling Accident (FHA) Signal has not yet been generated Crew has implemented OP-901-405, Fuel Handling Incident.

Based on these conditions, the crew should expect the (1) to detect any initial airborne activity rise and should start the (2) following the FHA signal.

(1) (2)

A. Fuel Handling Building PIG Fuel Handling Building HV Room Exhaust Fan A A Radiation Monitor B. Fuel Handling Building PIG FHB WRGM sample pump A Radiation Monitor C. Fuel Handling Building Fuel Handling Building HV Room Exhaust Fan A WRGM D. Fuel Handling Building FHB WRGM sample pump WRGM Facility: Waterford 3 Page 16 of 25

2014 NRC Exam SRO Written Exam SRO 17 Given:

Plant is at 100% power Control Rod testing is in progress in accordance with OP-903-005, Control Element Assembly Operability Check CEA #28 in Shutdown Bank A is being tested.

The initial position for CEA #28 is fully withdrawn at 149.5 inches.

During the surveillance testing for CEA #28, entry into TS 3.1.3.5, Shutdown CEA Insertion Limit ____(1)____ be required. The basis for the Shutdown CEA insertion limit is to _____(2)_____.

(1) (2)

A. will prevent axial Xenon redistribution B. will maintain minimum shutdown margin C. will not maintain minimum shutdown margin D. will not prevent axial Xenon redistribution Facility: Waterford 3 Page 17 of 25

2014 NRC Exam SRO Written Exam SRO 18 Given:

Plant is at 100% power Reactor Power Cutback is in service A Turbine Trip occurred due to an overspeed condition The following annunciator is illuminated associated with the Main Turbine:

o Turbine Trip Overspeed/DEH Power Lost The CRS will direct the crew to ________.

A. verify a reactor power cutback and perform OP-901-101, Reactor Power Cutback only B. verify a reactor power cutback and perform OP-901-101, Reactor Power Cutback and OP-901-210, Turbine Trip concurrently C. trip the reactor and perform OP-902-000, Standard Post Trip Actions and OP-901-210, Turbine Trip concurrently D. trip the reactor and perform OP-902-000, Standard Post Trip Actions only Facility: Waterford 3 Page 18 of 25

2014 NRC Exam SRO Written Exam SRO 19 Given:

Reactor is shutdown with all CEAs fully inserted RCS Boron concentration is 2100 ppm Keff is 0.945 RCS temperature is 195°F Which of the following correctly describes the minimum required shift staffing in accordance with Tech Spec 6.2.2?

A. 1 SM, 1 SRO, 2 ROs, 1 STA and 2 NAOs B. 1 SM, 1 RO, and 1 NAO C. 1 SM, 1 RO, 1 STA and 1 NAO D. 1 SM, 1 SRO, 2 ROs and 2 NAOs Facility: Waterford 3 Page 19 of 25

2014 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 ____(1)____ . If the RCS is considered water solid, the crew will _____(2)_____.

(1) (2)

A. RCS inventory or remain in the selected Optimal temperature changes do not Recovery Procedure and control RCS produce severe pressure temperature and throttle HPSI flow responses B. RCS inventory or transition to the Functional Recovery temperature changes do not Procedure and establish a bubble in produce severe pressure the Pressurizer responses C. Reactor vessel plenum level remain in the selected Optimal is less than 100% Recovery Procedure and control RCS temperature and throttle HPSI flow D. Reactor vessel plenum level transition to the Functional Recovery is less than 100% Procedure and establish a bubble in the Pressurizer Facility: Waterford 3 Page 20 of 25

2014 NRC Exam SRO Written Exam SRO 21 If plant conditions require the removal of a danger tag, the ____(1)____ may perform Alternate Release Authorization. One procedural condition required for this authorization is that the Tagout/Work Order Holder____(2)____.

(1) (2)

A. Duty Plant Manager will be notified immediately upon return to the site and prior to starting work B. SM or designee will be notified immediately upon return to the site and prior to starting work C. Duty Plant Manager is contacted per-telecom if not on site D. SM or designee is contacted per-telecom if not on site Facility: Waterford 3 Page 21 of 25

2014 NRC Exam SRO Written Exam SRO 22 The plant is at 100%. The rubber seal has been reported torn on Door 153, a CVAS boundary door, and the door has been declared inoperable. Door 161, the other door in that airlock, is operable. Which of the following is true concerning requirements to establish CVAS Boundary operability?

A. Perform OP-903-124, CVAS Pressure Boundary Testing, with Door 153 held open and Door 161 closed.

B. Perform OP-903-124, CVAS Pressure Boundary Testing, both Door 153 and Door 161 closed.

C. No testing is required until Door 153 has been restored to operable status.

D. No testing is required; only one door is required to be operable in each CVAS air lock.

Facility: Waterford 3 Page 22 of 25

2014 NRC Exam SRO Written Exam SRO 23 The stated limit in EP-002-030, Emergency Radiation Exposure Guidelines and Controls, for Emergency Team Members chosen to perform Life Saving activities is ___(1)____ REM TEDE. These limits may be exceeded only _____(2)_____.

(1) (2)

A. 25 if the NRC is consulted prior to authorizing the exposure B. 30 if the NRC is consulted prior to authorizing the exposure C. 30 by volunteers fully aware of the risks involved D. 25 by volunteers fully aware of the risks involved Facility: Waterford 3 Page 23 of 25

2014 NRC Exam SRO Written Exam SRO 24 Given:

Waste Condensate Tank B is being discharged to the Circ Water system EFFLUENT RAD MONT SYS ACT HI-HI annunciator is in alarm on CP-36 WASTE LIQUID RAD MONITOR TROUBLE annunciator is in alarm on CP-4 LWM-IFRR-0647, Liquid Waste Flow Recorder, indicates rising activity level The automatic isolations did not automatically close as designed The ATC operator has closed LWM-441 and LWM-442 Based on these conditions, for Waste Condensate Tank B to be approved for discharge before the Liquid Waste Radiation Monitor is repaired, which of the following is a required action per TRM 3.3.3.10, Radioactive Liquid Effluent?

A. Complete a valve lineup to ensure that Waste Condensate Tank A is isolated from the discharge.

B. Initiate a Department Action Statement Notice requiring samples every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during discharge.

C. Initiate a Technical Specification Addendum Log to 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.

D. Ensure release rate calculations have been verified by two technically qualified personnel prior to the discharge.

Facility: Waterford 3 Page 24 of 25

2014 NRC Exam SRO Written Exam SRO 25 Per EP-002-100, Technical Support Center Activation, Operation and Deactivation, the lowest level of event classification that requires activation of the Technical Support Center (TSC) is an ____(1)____ . It is the responsibility of the

_____(2)_____ to direct the activities of the TSC including overall management of the onsite Emergency Response Organization.

(1) (2)

A. Unusual Event TSC Manager B. Unusual Event Emergency Plant Manager C. Alert TSC Manager D. Alert Emergency Plant Manager Facility: Waterford 3 Page 25 of 25

2014 NRC Written Examination Waterford 3 Reactor Operator and Senior Reactor Operator

1. B 26. B

2. 0 27. A

3. 0 28. 8

4. D 29. B

5. A 30. 8

6. A 31. c

7. 0 32. c

8. D - 33. A

9. 0 34. B

10. A 35. c

11. 8 36. B

12. 0 37. A

13. 0 38. D

14. B 39. B

15. D 40. c

16. c 41. A

17. 0 42. D

18. D 43. c

19. c 44. 0

20. B 45. A

21. c 46. c

22. c 47. c

23. D 48. ~

24. A 49. 8

25. A 50. .A Page 1 of 2

2014 NRC Written Examination Waterford 3 Reactor Operator and Senior Reactor Operator

51. c S1. 8

52. c 52. A

53. A S3. D

54. c 54. c

55. D S5. c

56. A SB. A

57. c S7. c

58. B sa. c

59. A S9. 8

60. c S10. A

61. B S1 1. c

62. A S12. D

63. D S13. c

64. B 814. c

65. *a. S15 . c

66. c S16. 8

67. c S17. 8

68. A S18. B

69. B 819. 8

70. 8 S20. A

71. D S21. 8

72. A 522. A

73. c S23. D

74. A S24. D

75. c S25. D Page 2 of 2