Text

Retake Exam - 07/2002 - Draft Written Exam
	ML030360671
Person / Time
Site:	Waterford
Issue date:	05/23/2002
From:	Gody A; NRC Region 4
To:	Venable J; Entergy Operations
References
	50-382/02-302
	Download: ML030360671 (104)
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Waterford 3 Examination Question Examination Bank Examination Question Number 1 QUESTION ID: 5941 - STATUS: Revision LAST USED A

DESCRIPTION: Stuck CEA and TS requirements AUTHOR: dvince1 REVISION 1 REVISION DATE 05/13/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 05/13/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X SIMULATOR SETUP PLANT SYSTEM: CED CATEGORY: PROCEDURE TS PPO

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REVISION: CHANGE: DATE:

TS 3.1.3 OP-901-102 03 02 08/07/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A5-AK3.04 3.4 4.1 W-3-LP-OPS-PPO10 5 QUESTION The plant is doing a downpower to 60% to allow maintenance to be done on Main Feedwater Pump A. The plant is at 80% when the PNPO moves Group P in for ASI control. After moving Group P two steps in, CEA 24 (of Group P) drops into the core to zero inches withdrawn. The CRS enters OP-901-102, CEA or CEDMCS Malfunction, and orders a rapid power reduction. Determine what power level the plant will be required to go to?

A. 70%

B. 65%

C. 60%

D. 50%

ANSWER C. 60%

COMMENTS Given student copy of TS 3.1.3.1 and COLR Figure 3.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-1 New Question History Page 1 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 2 QUESTION ID: 5942 - STATUS: Revision LAST USED A

DESCRIPTION: RCP Malfunction - Seal Failure AUTHOR: dvince1 REVISION 1 REVISION DATE 05/10/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 05/10/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X OPEN REFERENCE SPECIAL

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SIMULATOR SETUP PLANT SYSTEM: PPO CATEGORY: PROCEDURE RCP

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REVISION: CHANGE: DATE:

OP-901-130 02 02 01/25/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A15/17-AA1.22 4 4.2 W-3-LP-OPS-PP010 3 QUESTION The plant is at 100% power. Given the following data for RCP-2B:

Vapor Seal - 30 psig Upper Seal - 294 psig Middle Seal - 1272 psig Which seal has failed?

A. Vapor Seal B. Upper Seal C. Middle Seal D. Lower Seal ANSWER B. Upper Seal COMMENTS Upper Seal has failed by 70%.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-1 New Question History Page 2 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 3 QUESTION ID: 5943 - STATUS: Revision LAST USED A

DESCRIPTION: Natural Circulation criteria and contingency actions AUTHOR: dvince1 REVISION 1 REVISION DATE 05/21/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 05/21/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X OPEN REFERENCE SPECIAL

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X SIMULATOR SETUP PLANT SYSTEM: PPE CATEGORY: PROCEDURE

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OP-902-002 09 00 04/12/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE C/E A13 - AK1.3 3.1 3.4 W-3-LP-OPS-PPE02 19 Page 3 of 104

QUESTION The plant has experienced a LOCA approximately 30 minutes ago. All ESFAS actuations have occurred as required. The following plant conditions exist:

Pressurizer Pressure is 1800 psia and dropping slowly

Pressurizer Level is 5% and dropping slowly

RCS Hot Leg Temperature is 582°F and slowly rising

RCS Cold Leg Temperature is 540°F and slowly rising

Representative CET is 584°F and slowly rising

SG Pressures are 1000 psia

SG Levels are 70% Wide Range and slowly dropping

Containment Pressure is 18.1 psia and constant

All other indications are within required limits.

The CRS has determined that Single Phase Natural Circulation criteria is not being met.

What action should be taken to restore Single Phase Natural Circulation?

A. Carry out the actions of Appendix 11, Void Elimination.

B. Pressurizer pressure needs to be reduced to allow safety injection flow.

C. Steam Generator pressure needs to be reduced to restore Natural Circulation.

D. All charging pumps need to be started to regain pressurizer level.

ANSWER C. Steam Generator pressure needs to be reduced to restore Natural Circulation.

COMMENTS Per step 36 of OP-902-002, if Single Phase Natural Circulation criteria is not met, the contingency action is to verify steam generator feeding and steaming. The Tech Guide states that this means steaming the Steam Generator. Give Steam Tables as reference.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-1 New Question History Page 4 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 4 QUESTION ID: 5944 - STATUS: Revision LAST USED A

DESCRIPTION: Emergency Boration - SDM required AUTHOR: dvince1 REVISION 1 REVISION DATE 05/21/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 05/21/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X OPEN REFERENCE SPECIAL

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X SIMULATOR SETUP PLANT SYSTEM: PPO CATEGORY: PROCEDURE TS

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REVISION: CHANGE: DATE:

OP-901-103 01 01 06/19/2000 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A24-AA2.05 3.3 3.9 W-3-LP-OPS-PPO10 3 QUESTION The plant has just entered Mode 6. The Shift Chemist has determined that boron concentration is below the required Refueling Concentration. The crew has initiated Emergency Boration. After 15 minutes, the CRS asks you to calculate Keff for current plant conditions based upon the following data:

Current RCS Boron Concentration is 2035 ppm

RCS Tave is 135°F

500 EFPD

Required Shutdown Margin Boron Concentration is 2020 ppm

TS Shutdown Margin Requirement is 1.5%

A. 0.98 B. 0.96 C. 0.94 D. 0.92 ANSWER A. 0.98 COMMENTS Give a copy of OP-903-090, Section 7.5 and Attachment 10.5 and Plant Data Book figures 1.4.1 and 1.4.2 as references.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-1 New Question History Page 5 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 5 QUESTION ID: 5945 - STATUS: Revision LAST USED A

DESCRIPTION: CCW and ESFAS AUTHOR: dvince1 REVISION 1 REVISION DATE 05/21/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 05/21/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X OPEN REFERENCE SPECIAL

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SIMULATOR SETUP PLANT SYSTEM: CC CATEGORY: SYSTEM

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REVISION: CHANGE: DATE:

OP-002-003 13 02 08/22/2001 OP-902-009 00 01 12/16/1999 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A26-AK3.02 3.6 3.9 W-3-LP-OPS-CC00 5 Page 6 of 104

QUESTION The following conditions exist:

Plant is at 100% power. CCW system valves are aligned as follows on CP-8:

CC114A, CCW Pump A to AB Suction Crossconnect Open

CC114B, CCW Pump B to AB Suction Crossconnect Open

CC115A, CCW Pump AB to A Suction Crossconnect Open

CC115B, CCW Pump AB to B Suction Crossconnect Open

CC126A, CCW Pump A to AB Discharge Crossconnect Open

CC126B, CCW Pump B to AB Discharge Crossconnect Open

CC200A, CCW Header A to AB Supply Isolation Closed

CC200B, CCW Header B to AB Supply Isolation Open

CC501, CCW Non Safety Supply Hdr Isolation Open

CC562, CCW Non Safety Return Hdr Isolation Open

CC641, CCW to Containment Outside Cntmt Isolation Closed

CC710, Cntmt CCW Return Header Inside Cntmt Isolation Closed

CC713, NNS Return Hdr Outside Containment Isol Closed The Dry Cooling Towers are not bypassed.

Which one of the following could have caused this alignment?

A. Failure of CCW Surge Tank Level Switch B. Leak in Non Safety Supply Header C. Inadvertent Safety Injection Actuation Signal (SIAS)

D. Inadvertent Containment Spray Actuation Signal (CSAS)

ANSWER D. Inadvertent Containment Spray Actuation Signal (CSAS)

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-1 New Question History Page 7 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 6 QUESTION ID: 5946 - STATUS: Revision LAST USED A

DESCRIPTION: ESDE - adding feedwater to dry SG AUTHOR: dvince1 REVISION 1 REVISION DATE 05/21/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 05/21/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X OPEN REFERENCE SPECIAL

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SIMULATOR SETUP PLANT SYSTEM: PPE CATEGORY: PROCEDURE SG

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REVISION: CHANGE: DATE:

OI-038-000 01 01 08/23/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A40-AK1.07 3.4 4.2 WLP-OPS-PPE08 9 QUESTION The main concern with adding feedwater to an empty Steam Generator is a A. Possible water hammer B. Possible overcooling C. Possible tube rupture D. Possible feedwater ring damage ANSWER C. Possible tube rupture COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 1-1 New Question History Page 8 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 7 QUESTION ID: 5947 - STATUS: Revision LAST USED A

DESCRIPTION: RCS Overcooling - heat removal systems AUTHOR: dvince1 REVISION 1 REVISION DATE 05/21/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 05/21/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X OPEN REFERENCE SPECIAL

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SIMULATOR SETUP PLANT SYSTEM: PPE CATEGORY: SYSTEM

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OP-902-004 09 00 04/12/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE CE/A11-AK2.2 3.2 3.4 WLP-OPS-PPE04 7 QUESTION A Steam Line Break inside containment has occurred on Steam Generator #1. Steam Generator #1 is empty and Pressurizer pressure has begun to rise. CET temperature is stable. Which one of the following would be a required action taken by the crew in response to the pressurizer pressure rise?

A. Throttle High Pressure Safety Injection Flow.

B. Manually initiate Emergency Feedwater Actuation Signal #2.

C. Isolate Steam Generator #1.

D. Commence steaming Steam Generator #2 using Steam Bypass Control Valve #1.

ANSWER B. Manually initiate Emergency Feedwater Actuation Signal #2.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-1 New Question History Page 9 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 8 QUESTION ID: 5948 - STATUS: Revision LAST USED A

DESCRIPTION: Loss of Condenser Vacuum AUTHOR: dvince1 REVISION 1 REVISION DATE 05/22/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 05/22/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X OPEN REFERENCE SPECIAL

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SIMULATOR SETUP PLANT SYSTEM: PPO CATEGORY: PROCEDURE

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REVISION: CHANGE: DATE:

OP-901-220 02 02 02/15/2000 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-4-11 3.4 3.6 WLP-OPS-PPO20 3 QUESTION The plant is at 100% power. Condenser vacuum begins to drop. The crew enters OP-901-220, Loss of Condenser Vacuum. Vacuum is now 24.8 Hg and slowly dropping.

Based on the current vacuum, what action should the crew take?

A. Commence a rapid downpower IAW OP-901-212, Rapid Down Power, concurrent with this off-normal.

B. Commence a normal downpower IAW OP-010-005, Plant Shutdown, concurrent with this off-normal.

C. Trip the reactor and perform OP-902-000, Standard Post Trip Actions, concurrent with this off-normal.

D. Continue to attempt to recover vacuum IAW this off-normal.

ANSWER A. Commence a rapid downpower IAW OP-901-212, Rapid Down Power, concurrent with this off-normal.

COMMENTS Per OP-901-220, step 4.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-1 New Question History Page 10 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 9 QUESTION ID: 5949 - STATUS: Revision LAST USED A

DESCRIPTION: Station Blackout AUTHOR: dvince1 REVISION 1 REVISION DATE 05/22/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 05/22/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X OPEN REFERENCE SPECIAL

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SIMULATOR SETUP PLANT SYSTEM: PPE CATEGORY: PROCEDURE

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REVISION: CHANGE: DATE:

OP-902-005 11 00 04/12/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.1-E55-EK3.02 4.3 4.6 WLP-OPS-PPE05 7 QUESTION A Station Blackout has occurred. The crew has diagnosed to OP-902-005, Station Blackout Recovery. The following plant conditions exist:

Containment pressure is 15.8 psia and slowly rising

Containment Temperature is 118°F and slowly rising

Pressurizer level is 34% and slowly dropping

RCS Temperature is 545°F and slowly rising

RCS Pressure is 2210 psia and slowly dropping

EDG A has tripped on Overspeed.

EDG B is tagged out and not expected to be returned for 30 minutes.

Both batteries are reading 134 VDC Based on these conditions, which of the following actions is INCORRECT?

A. Close MSIVs.

B. Commence a cooldown to 350°F.

C. Place Containment Spray control switches to OFF.

D. Open selected PAC Cabinet doors.

ANSWER B. Commence a cooldown to 350°F.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehensive or Analysis 1-1 New Question History Page 11 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 10 QUESTION ID: 5950 - STATUS: Revision LAST USED A

DESCRIPTION: Loss of SUPS AUTHOR: dvince1 REVISION 1 REVISION DATE 05/22/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 05/22/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X OPEN REFERENCE SPECIAL

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SIMULATOR SETUP PLANT SYSTEM: ID CATEGORY: PROCEDURE PPO SYSTEM

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REVISION: CHANGE: DATE:

OP-901-312 01 07 03/13/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A57-AA2 03 3.7 3.9 W-3-LP-OPS-ID00 7 W-3-LP-OPS-PPO30 3 QUESTION The plant is at 80% power when SUPS MA trips. Which one of the following will occur?

A. The reactor will trip due to opening of Reactor Trip Breakers 1 and 2.

B. Safety Injection Tanks 1A & 2A will inject due to loss of pressure interlocks to their isolation valves.

C. An EFAS signal will be generated that will open the EFW Isolation valves.

D. COLSS will be inoperable due to the failure of CEAC #1.

ANSWER C. An EFAS signal will be generated that will open the EFW Isolation valves.

COMMENTS A is wrong because Breakers 1, 2, 5, & 6 open which does not cause a reactor trip. B is wrong because SIT inject on lowering pressure. D is wrong because CEAC #1 is powered from Train B.

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Waterford 3 Examination Question Examination Bank Examination Question Number 11 QUESTION ID: 5951 - STATUS: Revision LAST USED A

DESCRIPTION: Loads on ACCW during loss of ACCW AUTHOR: dvince1 REVISION 1 REVISION DATE 05/22/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 05/22/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X OPEN REFERENCE SPECIAL

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SIMULATOR SETUP PLANT SYSTEM: ACC CATEGORY: SYSTEM

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REVISION: CHANGE: DATE:

NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A62-AA1.02 3.2 3.3 W-3-LP-OPS-CC00 3 QUESTION Which one of the following components would be directly affected by an inadvertent securing of ACCW Pump A?

A. Essential Chiller A running in Wet Tower mode.

B. Containment Fan Cooler C running in Fast mode.

C. CEDM Fan A running in normal mode.

D. Waste Gas Compressor A running in lead mode.

ANSWER A. Essential Chiller A running in Wet Tower mode.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 1-1 New Question History Page 13 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 12 QUESTION ID: 5952 - STATUS: Revision LAST USED A

DESCRIPTION: Actuation of SBV deluge system AUTHOR: dvince1 REVISION 1 REVISION DATE 05/22/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 05/22/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X OPEN REFERENCE SPECIAL

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SIMULATOR SETUP PLANT SYSTEM: FPP CATEGORY: SYSTEM SBV

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REVISION: CHANGE: DATE:

OP-009-004 11 04 04/24/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A67-AA1.09 3 3.3 W-3-LP-OPS-FP00 10 W-3-LP-OPS-SBV00 4 QUESTION Shield Building Ventilation (SBV) Train A indicates a fire. Which one of the following is TRUE?

A. SBV Train A Deluge System must be manually actuated on the Fire Detection Main Control Panel to allow water flow.

B. FP-601A, Reactor Bldg Fire Mn Hdr A FPM-1 Cntmt Isol, must be open to allow water flow to SBV Train A Deluge System.

C. The local pull station must be operated to allow water flow to SBV Train A Deluge System.

D. SBV Train A Deluge System isolation valve must be opened to allow water flow to SBV Train A.

ANSWER D. SBV Train A Deluge System isolation valve must be opened to allow water flow to the SBV Train A.

COMMENTS Per OP-009-004, Step 8.7.1.

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Waterford 3 Examination Question Examination Bank Examination Question Number 13 QUESTION ID: 5953 - STATUS: Revis ion LAST USED A

DESCRIPTION: Evacuation of the CR and EDG AUTHOR: dvince1 REVISION 1 REVISION DATE 05/22/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 05/22/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X OPEN REFERENCE SPECIAL

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SIMULATOR SETUP PLANT SYSTEM: PPO CATEGORY: PROCEDURE

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REVISION: CHANGE: DATE:

NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A68-AK2.07 3.3 3.4 W-3-LP-OPS-PPO51 21 QUESTION During an evacuation of the Control Room with Fire, FR-2367, Appendix R key switch for EDG B, is operated. What is the purpose of this key switch?

A. Prevents EDG B from tripping.

B. Electrically isolates EDG B from the Control Room.

C. Allows EDG B to be controlled from LCP-43, Remote Shutdown Panel.

D. Starts EDG Train B Mini-sequencer.

ANSWER B. Electrically isolates EDG B from the Control Room.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 1-1 New Question History Page 15 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 14 QUESTION ID: 5954 - STATUS: Revision LAST USED A

DESCRIPTION: Loss of Containment Integrity AUTHOR: dvince1 REVISION 1 REVISION DATE 05/22/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 05/22/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X OPEN REFERENCE SPECIAL

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SIMULATOR SETUP PLANT SYSTEM: PPE CATEGORY: PROCEDURE

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REVISION: CHANGE: DATE:

OP-902-002 09 00 03/30/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A69-AA2.02 3.9 4.4 WLP-OPS-PPE01 6 QUESTION During a LOCA, Containment Spray Pump A trips on overcurrent. The CRS directs overriding and closing the Containment Spray Header Isolation, CS-125A. Why is this done?

A. To prevent airbinding the Containment Spray System.

B. To ensure that Containment Spray flow is maintained via the opposite train.

C. To protect containment integrity.

D. To reduce EDG loading.

ANSWER C. To protect containment integrity.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 1-1 New Question History Page 16 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 15 QUESTION ID: 5955 - STATUS: Revision LAST USED A

DESCRIPTION: Inadequate Core Cooling AUTHOR: dvince1 REVISION 1 REVISION DATE 06/05/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/05/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X OPEN REFERENCE SPECIAL

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X SIMULATOR SETUP PLANT SYSTEM: QSP CATEGORY: SYSTEM

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REVISION: CHANGE: DATE:

OI-038-000 01 01 08/23/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.1-E74-EA1.12 4.1 4.4 W-3-LP-OPS-QSP00 1 Page 17 of 104

QUESTION A LOCA occurred 25 minutes ago. Assume all ESFAS actuations occurred as required and operator immediate actions and contingency actions have been taken. The following conditions exist:

Pressurizer Level - 0%

Pressurizer Pressure - 900 psia

Loop 1 Thot - 500°F

Loop 2 Thot - 531°F

Loop 1 Tcolds - 480°F

Loop 2 Tcolds - 495°F

Representative CET - 528°F

Containment Pressure - 18.1 psia

CP-2 Subcooled Margin Meter - 30°F

RVLMS indicates 80% in the Reactor Vessel Head The CRS is trying to determine Adequate Core Cooling and asks you to verify subcooled margin. You would respond:

A. Subcooled Margin is 30°F.

B. Subcooled Margin is 1°F.

C. Subcooled Margin is 32°F.

D. Subcooled Margin is 4°F.

ANSWER D. Subcooled Margin is approximately 4°F.

COMMENTS Provide copy of Steam Tables and calculator. Per OI-038-000, EOP Expectations/Guidance - below 1000 psia, other indications should be used to determine Subcooled Margin instead of the CP-2 meter. With Natural Circulation conditions (no RCPs due to CSAS at 17.7 psia), Representative CET should be used to determine Subcooled Margin.

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Waterford 3 Examination Question Examination Bank Examination Question Number 16 QUESTION ID: 5956 - STATUS: Revision LAST USED A

DESCRIPTION: RCS Activity TS AUTHOR: dvince1 REVISION 1 REVISION DATE 06/05/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/05/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X OPEN REFERENCE SPECIAL

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SIMULATOR SETUP PLANT SYSTEM: TS CATEGORY: ADMIN

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REVISION: CHANGE: DATE:

TS 3.4.7 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-2-25 2.5 3.7 W-3-LP-OPS-CHM03 14 W-3-LP-OPS-CHM03 15 QUESTION If RCS Specific Activity exceeds Technical Specification limits the plant must be placed in Hot Standby and Tavg reduced to < 500 degrees F. The basis for the limit of < 500 deg F on Tavg is to:

A. Reduce contamination of secondary systems.

B. Stay below lift setpoint of the Main Steam Safeties.

C. Reduce Steam Pressure to prevent possible Tube Rupture.

D. Increase Recirculation Ratio to help clean up activity.

ANSWER B. Stay below lift setpoint of the Main Steam Safeties.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 1-1 New Question History Page 19 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 17 QUESTION ID: 6027 - STATUS: Revision LAST USED A

DESCRIPTION: Continuous CEA Withdrawal and Insertion Limits AUTHOR: dvince1 REVISION 1 REVISION DATE 06/18/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/18/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X SIMULATOR SETUP PLANT SYSTEM: TS CATEGORY: ADMIN

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TS 3.1.3 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A1-AK1.04 3.7 3.9 WLP-OPS-CED00 8 QUESTION The plant is doing a downpower to 50% for Feedwater Pump A maintenance. As the downpower commences, the CRS directs the PNPO to commence ASI control. After 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , power is at 73% with Group P at 120 inches withdrawn and Group 6 at 145 inches withdrawn. The CRS directs CEA Insertion for ASI control so as to NOT exceed The Short Term Steady State Insertion Limit. Based upon this order and current power level, CEA Group P can be inserted to __________ and CEA Group 6 can be inserted to

_______. (Assume power does not change any further for this determination.)

A. 120 inches, 120 inches B. 108 inches, 120 inches C. 60 inches, 108 inches D. 108 inches, 60 inches ANSWER D. Restore CEAs to above 120 inches withdrawn within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or log CEA Insertion hours.

COMMENTS Provide copy of TS 3.1.3.1, TS 3.1.3.6 and COLR Figures 4 and 5.

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Waterford 3 Examination Question Examination Bank Examination Question Number 18 QUESTION ID: 5957 - STATUS: Revision LAST USED A

DESCRIPTION: Dropped Control Rod and Indication AUTHOR: dvince1 REVISION 1 REVISION DATE 06/05/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/05/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X OPEN REFERENCE SPECIAL

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SIMULATOR SETUP PLANT SYSTEM: CEC CATEGORY: THEORY TYR

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REVISION: CHANGE: DATE:

NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A3-AA2.03 3.6 3.8 W-3-LP-OPS-PPO10 1 QUESTION CEA #23 has dropped into the core. The crew has entered OP-901-102, CEA or CEDMCS Malfunction. The first step for dealing with a dropped CEA is to match Tavg and Tref. The reason this is done is because:

A. RCS pressure has increased.

B. Turbine First Stage Pressure has increased.

C. RCS temperature has decreased.

D. Shutdown Margin has decreased.

ANSWER C. RCS temperature has decreased.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 1-2 New Question History Page 21 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 19 QUESTION ID: 5958 - STATUS: Revision LAST USED A

DESCRIPTION: Reactor Trip Recovery AUTHOR: dvince1 REVISION 1 REVISION DATE 06/05/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/05/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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OP-902-009 01 00 04/04/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.1-E7-EK3.01 4 4.6 WLP-OPS-PPE01 15 QUESTION The reactor was at 100% power. Two CEAs fell into the core and the reactor was manually tripped. During Standard Post Trip Actions, the following items were reported:

Feedwater Pump A tripped on loss of lube oil.

Startup Feedwater Regulating Valve B had to be manually placed to 20% open.

The 3 to 2 Tie Breaker for Safety Bus A tripped open and EDG A failed to start.

Pressurizer Pressure dropped to 2150 psia and all Pressurizer Backup Heaters had to be manually started.

Assuming all other indications are as required, which Emergency Operating Procedure would the crew end up in?

A. OP-902-001, Reactor Trip Recovery B. OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery C. OP-902-006, Loss of Main Feedwater Recovery D. OP-902-008, Functional Recovery ANSWER A. OP-902-001, Reactor Trip Recovery COMMENTS B is wrong because must lose offsite power or all RCPs to reach it via diagnostics.

C is wrong because still have Feed pump B.

D is wrong because listed actions do not require entry.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-2 New Question History Page 22 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 20 QUESTION ID: 5959 - STATUS : Revision LAST USED A

DESCRIPTION: Pressurizer Steam Space AUTHOR: dvince1 REVISION 1 REVISION DATE 06/05/2002 APPROVAL: APPROVAL DATE:

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NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A8-AK1.02 3.1 3.7 W-3-LP-OPS-TYH04 21 QUESTION A small leak on the top of the pressurizer has occurred. The crew enters OP-901-111, RCS Leakage, and performs a RCS Leakrate. The leakrate calculation determines that unidentified leakage is 1.5 GPM. Previous leakage had been 0.03 GPM. The crew commences a shutdown IAW OP-010-005, Plant Shutdown. During the Shutdown, the Main Spray Valve 1A sticks open and Pressurizer Pressure drops to 2085 psia before the crew can shut the valve. Which of the following is a result of this event?

A. Unidentified leakage will drop due to the pressure change.

B. The reactor will trip due to the low pressure.

C. RVLMS will indicate a partial Reactor Head void due to the low pressure.

D. Pressurizer level will drop due to the pressure change.

ANSWER A. Unidentified leakage will drop due to the pressure change.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-2 New Question History Page 23 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 21 QUESTION ID: 5960 - STATUS: Revis ion LAST USED A

DESCRIPTION: Small Break LOCA and Steam Generators AUTHOR: dvince1 REVISION 1 REVISION DATE 06/05/2002 APPROVAL: APPROVAL DATE:

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NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.1-E9-EK2.03 3 3.3 WLP-OPS-PPE02 14 QUESTION For a Small Break LOCA inside containment, the RCS Heat Removal process can be described as: (Note - assume all ESFAS actuations occurred as required.)

A. Forced Circulation using the Reactor Coolant Pumps B. Single Phased Natural Circulation using the Emergency Feedwater Pumps C. Two Phased Natural Circulation using the Steam Bypass Control System D. Break Heat Removal using the Main Feedwater Pumps ANSWER B. Single Phased Natural Circulation using the Emergency Feedwater Pumps COMMENTS On Small Break LOCAs, Containment Spray Actuation and Main Steam Isolation would occur so Reactor Coolant Pumps, Steam Bypass Control and MFW Pumps would not be available.

Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 1-2 New Question History Page 24 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 22 QUESTION ID: 5961 - STATUS: Revision LAST USED A

DESCRIPTION: Large Break LOCA versus ESDE AUTHOR: dvince1 REVISION 1 REVISION DATE 06/05/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/05/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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OP-902-009 01 00 04/04/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.1-E11-EA2.13 3.7* 3.7* WLP-OPS-PPE02 15 QUESTION Given the following plant conditions:

Reactor is tripped with 2 CEAs stuck out.

Pressurizer Level is 0%.

Pressurizer Pressure is 1485 psia and dropping slowly.

Representative CET temperature is 581°F and rising slowly.

Steam Generator Pressures are 988 psia and steady.

Containment Pressure is 16.9 psia and rising slowly.

Assume all actuations occurred as required.

What event has occurred?

A. Steam Generator Tube Rupture B. Excess Steam Demand inside Containment C. Loss of Coolant Accident D. Loss of Forced Circulation ANSWER C. Loss of Coolant Accident COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-2 New Question History Page 25 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 23 QUESTION ID: 5962 - STATUS: Revision LAST USED A

DESCRIPTION: VCT Level and Makeup AUTHOR: dvince1 REVISION 1 REVISION DATE 06/05/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/05/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: CVC CATEGORY: PROCEDURE PPO

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REVISION: CHANGE: DATE:

OP-901-113 01 01 11/12/1999 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A22-AA1.08 3.4 3.3 W-3-LP-OPS-PPO10 4 QUESTION The plant is at 100% power when the VCT LEVEL LO-LO annunciator is received. The PNPO reports that the VCT Level indication on CP-2 reads 0% and that the PMC VCT Level indication is 40%. Which of the following will immediately occur as a result of this failure?

A. Charging Pump suction will shift to the RWSP.

B. VCT Makeup will start if aligned for Auto.

C. Charging Pumps will trip.

D. Letdown will auto divert to BMS.

ANSWER B. VCT Makeup will start if aligned for Auto.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-2 New Question History Page 26 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 24 QUESTION ID: 5963 - STATUS: Revision LAST USED A

DESCRIPTION: Loss of SDC and LPSI pumps AUTHOR: dvince1 REVISION 1 REVISION DATE 06/05/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/05/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: PPO CATEGORY: PROCEDURE SDC

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REVISION: CHANGE: DATE:

OP-901-131 02 00 01/08/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A25-AK2.02 3.2* 3.2 WLP-OPS-REQ21 6 QUESTION The plant is in Mode 5 with Reduced Inventory with both SDC Trains in service. The dedicated SDC watch reports the following:

LPSI Pump B Flow Lost Alarm

SDC Trouble Alarm

LPSI Pump B Amperage reads 5 amps and steady

LPSI Pump B Flow indicates a steady 1500 GPM What has occurred?

A. LPSI Pump B Minimum Flow Recirc valve has failed open.

B. LPSI Pump B is air bound.

C. LPSI Pump B is at runout condition.

D. LPSI Pump B is cavitating.

ANSWER B. LPSI Pump B is air bound.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-2 New Question History Page 27 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 25 QUESTION ID: 5964 - STATUS: Revision LAST USED A

DESCRIPTION: ATWS - Manual Trip AUTHOR: dvince1 REVISION 1 REVISION DATE 06/05/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/05/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: ATS CATEGORY: SYSTEM PPE

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REVISION: CHANGE: DATE:

OP-902-000 09 00 02/12/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.1-E29-EK3.10 4.1 4.1 WLP-OPS-PPE01 10 W-3-LP-OPS-ATS 3 QUESTION The plant is at 100% power when a Reactor Power Cutback occurs due to an equipment malfunction (card failure). CEA #1 falls into the core following the Reactor Power Cutback. The CRS orders a manual reactor trip but the manual trip buttons do not work.

The PNPO initiates a manual trip using the DRTS pushbuttons. Assuming everything functions as required and all CEAs insert, which of the following statement is TRUE for actions taken for this event?

A. The MG Set Load Contactors will be open, MG Sets are running and the Reactor Trip Breakers will be closed.

B. The MG Set Load Contactors will be closed, MG Sets are running and the Reactor Trip Breakers will be open.

C. The MG Set Load Contactors will be open, MG Sets are tripped and the Reactor Trip Breakers will be closed.

D. The MG Set Load Contactors will be closed, MG Sets are tripped and the Reactor Trip Breakers will be open.

ANSWER A. The MG Set Load Contactors will be open, MG Sets are running and the Reactor Trip Breakers will be closed.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-2 New Question History Page 28 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 26 QUESTION ID: 5965 - STATUS: Revision LAST USED A

DESCRIPTION: ENI Startup Channels and Power Restoration AUTHOR: dvince1 REVISION 1 REVISION DATE 06/05/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/05/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: ENI CATEGORY: SYSTEM

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REVISION: CHANGE: DATE:

OP-004-008 06 01 03/20/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A32-AA1.01 3.1* 3.4* W-3-LP-OPS-ENI00 4 QUESTION The plant is at 90% power following a downpower for work on Heater Drain Pump A.

Startup Channel A was removed for maintenance and the Startup HV Control Selector Switch is aligned to the OFF position. Maintenance has been completed and the NPO goes to realign the Startup Channel to service. The NPO inadvertently turns the Startup HV Control Selector Switch to ON and walks away. What is a possible effect of this action?

A. Audio Count Rate amplifier automatically turns off.

B. The associated Boron Dilution Monitor fails low.

C. CPC A trip on DNBR and LPD occurs.

D. Startup Channel A detector is damaged.

ANSWER D. Startup Channel A detector is damaged.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-2 New Question History Page 29 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 27 QUESTION ID: 5966 - STATUS: Revision LAST USED A

DESCRIPTION: SG Tube Leak AUTHOR: dvince1 REVISION 1 REVISION DATE 06/05/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/05/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: PPO CATEGORY: PROCEDURE

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REVISION: CHANGE: DATE:

OP-901-202 03 00 04/11/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-3-11 2.7 3.2 WLP-OPS-PPO20 4 QUESTION The plant has experienced a Steam Generator Tube Leak. OP-901-202, Steam Generator Tube Leakage or High Activity, has been entered. The plant is currently shutdown and carrying out the actions of OP-901-202. RCS Pressure is higher than the isolated Steam Generator pressure. The isolated SG Narrow Range level is 79% and rising. If the SG Level is not brought under control, what could occur?

A. Water hammer of the Main Steam piping.

B. Opening of Main Steam Safeties.

C. Dilution of the RCS boron concentration.

D. Contamination of the Main Condenser.

ANSWER B. Opening of Main Steam Safeties.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comp rehensive or Analysis 1-2 New Question History Page 30 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 28 QUESTION ID: 5967 - STATUS: Revision LAST USED A

DESCRIPTION: SGTR and Natural Circulation AUTHOR: dvince1 REVISION 1 REVISION DATE 06/05/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/05/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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OP-902-007 10 0 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.1-E38-EA2.09 4.2 4.2 WLP-OPS-PPE07 4 QUESTION Following a SGTR with a concurrent Loss of Offsite Power, which ONE of the following would indicate Natural Circulation criteria is met?

A. All available charging pumps running with 88 gpm of flow.

B. Loop delta T is 40 degrees F.

C. High Pressure Safety Injection flow is 200 gpm per loop.

D. Thot is 545 degrees F and slowly rising.

ANSWER B. Loop delta T is 40 degrees F.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-2 New Question History Page 31 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 29 QUESTION ID: 5968 - STATUS: Revision LAST USED A

DESCRIPTION: Loss of Main Feedwater - interlocks AUTHOR: dvince1 REVISION 1 REVISION DATE 06/10/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/10/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: RXC CATEGORY: SYSTEM

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REVISION: CHANGE: DATE:

OP-004-015 08 00 05/31/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE CE/EO6 EK2.1 3.3 3.7 WLP-OPS-RXC00 1 QUESTION For Feedwater Pump A, which ONE of the following would cause a Reactor Power Cutback?

A. Feedwater pump speed controller fails to 0% output.

B. 2 of 2 Speed Sensor Pickup probes (SSPU) fail Off.

C. 2 of 2 Control Oil Pressure read less than 60 psig.

D. Duplex Oil Filter reaches 20 psid.

ANSWER C. 2 of 2 Control Oil Pressure read less than 60 psig.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 1-2 New Question History Page 32 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 30 QUESTION ID: 5969 - STATUS: Revision LAST USED A

DESCRIPTION: Loss of DC Power - battery chargers AUTHOR: dvince1 REVISION 1 REVISION DATE 06/10/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/10/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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TS 3.8.2.1 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A58-AK1.01 2.8 3.1* W-3-LP-OPS-PPO30 5 QUESTION Battery Charger 3B1 is tagged out for maintenance. Battery Charger 3B2 trips on overcurrent. It takes the shift crew 30 minutes to restore Battery Charger 3B1 to service.

Battery 3B-S voltage reaches 108 volts before Battery Charger 3B1 is restored. The Battery Charger is restored to service and Battery 3B-S voltage is reading 132 volts.

Which ONE of the following statements is true following restoration?

A. Restore Battery Charger 3B2 to OPERABLE status within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

B. Perform Surveillance Requirement 4.8.2.1a.1 within 7 days.

C. No action is required per TS 3.8.2.1.

D. Verify parameters listed in Table 4.8-2 meet the Category B limits within 7 days.

ANSWER D. Verify parameters listed in Table 4.8-2 meet the Category B limits within 7 days.

COMMENTS Give copy of TS 3.8.2.1.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-2 New Question History Page 33 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 31 QUESTION ID: 5970 - STATUS: Revision LAST USED A

DESCRIPTION: Waste Gas Release and E-Plan AUTHOR: dvince1 REVISION 1 REVISION DATE 06/10/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/10/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: GWM CATEGORY: PROCEDURE PPO

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REVISION: CHANGE: DATE:

OP-901-413 00 01 08/14/2000 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A60-AK3.01 2.9 4.2 W-3-LP-OPS-PPO40 3 QUESTION A Gaseous Waste Release is in progress from Gas Decay Tank A. A Waste Gas Activity Hi alarm comes in on CP-4. Which ONE of the following is TRUE in relation to this event?

A. GWM-309, Waste Gas Discharge Flow Control Valve, must be shut by the NPO.

B. The Shift Manager will evaluate need to activate the Emergency Plan.

C. GWM-305A, Gas Decay Tank A Discharge Isolation, will automatically close.

D. The CRS should enter OP-901-414, Effluent Discharge High Radiation.

ANSWER B. The Shift Manager will evaluate need to activate the Emergency Plan.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 1-2 New Question History Page 34 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 32 QUESTION ID: 5971 - STATUS: Revision LAST US ED A

DESCRIPTION: ARM Annunciator Response Actions AUTHOR: dvince1 REVISION 1 REVISION DATE 06/10/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/10/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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REVISION: CHANGE: DATE:

OP-901-402 02 00 08/18/2000 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A61-AK3.02 3.4 3.6 W-3-LP-OPS-PPO40 1 WLP-OPS-RMS 3 QUESTION The plant is at 100% power. The Rad Monitoring Sys Activity Hi-Hi annunciator alarms.

The RM-11 shows the Charging Pump Rooms Area Rad Monitor (ARM-IRE-5023) and the HVAC Duct PIG A (PRM-IRE-6710A) are in alarm. All other plant indications are normal and stable. Given this information, which Off Normal procedure would the crew enter?

A. OP-901-402, High Airborne Activity in the Reactor Auxiliary Building B. OP-901-413, Waste Gas Discharge High Radiation C. OP-901-111, Reactor Coolant System Leakage D. OP-901-112, Charging or Letdown Malfunction ANSWER A. OP-901-402, High Airborne Activity in the Reactor Auxiliary Building COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-2 New Question History Page 35 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 33 QUESTION ID: 5972 - STATUS: Revision LAST USED A

DESCRIPTION: OP-902-008 Exit AUTHOR: dvince1 REVISION 1 REVISION DATE 06/10/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/10/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: PPE CATEGORY: PROCEDURE

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REVISION: CHANGE: DATE:

OP-902-008 12 00 04/12/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE CE/E09-EK3.2 3.0 3.5 WLP-OPS-PPE08 5 QUESTION The plant has experienced a Loss of Coolant Accident Inside Containment concurrent with and Excess Steam Demand Event. All ESFAS actuations have occurred as required.

All acceptance criteria for the implemented success path for each Safety Function is being satisfied. The crew is now evaluating exiting OP-902-008. Given the current plant conditions, which ONE of the following is NOT a procedure that the crew would exit to from OP-902-008?

A. OP-010-005, Plant Shutdown B. OP-902-009, Appendix 1, Diagnostic Flow Chart C. OP-902-002, Loss of Coolant Accident D. A procedure developed by the TSC.

ANSWER A. OP-010-005, Plant Shutdown COMMENTS OP-010-005 requires operating RCP and MFW - all ESFAS actuations would have MSIS (No MFW possible) and CSAS (No RCPs).

Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 1-2 New Question History Page 36 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 34 QUESTION ID: 5973 - STATUS: Revision LAST USED A

DESCRIPTION: Pzr Level Control Malfunction and Changing Power AUTHOR: dvince1 REVISION 1 REVISION DATE 06/11/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/11/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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REVISION: CHANGE: DATE:

OP-901-110 03 01 09/02/1998 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A28-AK3.04 2.9* 3 W-3-LP-OPS-PPO10 3 QUESTION The plant is at 100% power when a Pressurizer Level Setpoint Malfunction occurs. The crew has entered OP-901-110, Pressurizer Level Malfunction. What would be the minimum level of operation for Pressurizer Level if the plant had to drop power to 95%?

A. 44%

B. 41%

C. 38%

D. 31%

ANSWER B. 41%

COMMENTS Give copy of OP-901-110, Attachment 1, Pzr level vs. Tave Curve, and Plant Data Book Section 2.2.1, RCS Temperature Control Bands vs. Power.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-3 New Question History Page 37 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 35 QUESTION ID: 3318 -B STATUS: Draft LAST USED DESCRIPTION: IA pressure for RX trip (similiar to RO NRC EXAM 1994)

AUTHOR: bcoble REVISION 0 REVISION DATE 03/24/1999 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/18/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: IA CATEGORY: Procedure PPO

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REVISION: CHANGE: DATE:

OP-901-511 04 03 07/03/2000 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 4.2-A65-AA2.06 3.6* 4.2 W-3-LP-OPS-AIR00 5 W-3-LP-OPS-PPO50 4 QUESTION Given the following:

The plant is at 100 % power when the following alarms are received:

INST AIR PRESS BACKUP VLV OPEN

INST AIR DRYERS BYPASSED

INSTRUMENT AIR RECEIVER PRESSURE HI/LO

The PMC mimic AIR indicates excessive IA usage and rising.

On CP-1, IA pressure is reading 60 psig and dropping.

The crew is in OP-901-511, Instrument Air Malfunction.

What action should be taken?

A. Commence a rapid plant shutdown IAW OP-901-212, Rapid Plant Downpower.

B. Commence a normal plant shutdown IAW OP-010-005, Plant Shutdown.

C. Trip the main turbine and perform OP-901-101, Reactor Power Cutback, concurrently with this procedure.

D. Trip the reactor and perform OP-902-000, Standard Post Trip Actions, concurrently with this procedure.

ANSWER D. Trip the reactor and perform OP-902-000, Standard Post Trip Actions, concurrently with this procedure.

COMMENTS Rewrote question to make it more comprehension/analysis type. Dave Vincent 6/19/2002 Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-3 Modified Bank Question History Page 38 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 36 QUESTION ID: 5974 - STATUS: Revision LAST USED A

DESCRIPTION: RCS Leakage and Annunciator AUTHOR: dvince1 REVISION 1 REVISION DATE 06/11/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/11/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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REVISION: CHANGE: DATE:

OP-500-012 18 00 06/25/2001 OP-901-111 01 05 06/14/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE CE/A16-AK1.3 3.2 3.5 W-3-LP-OPS-PPO10 1 QUESTION The plant is at 85% power for Heater Drain Pump maintenance. A Containment Water Leakage Hi alarm is received. The Containment Weir indicates 5 GPM and steady.

Charging and Letdown mismatch shows a rising trend? All other indications are normal.

Which ONE of the following is the cause of this?

A. Leak into the CCW AB Header from the RCS causing CCW reliefs to lift B. Leak from Containment Fan Coolers C. Leak from the RCS D. Leak from the Reactor Drain Tank ANSWER C. Leak from the RCS COMMENTS Note - Reference material OP-500-012, revision do not match because of Procedure Revision Policy that only revises the affected attachment of the Annunciator Response and not all attachments.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 1-3 New Question History Page 39 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 37 QUESTION ID: 1257 - STATUS: Approved LAST USED A

DESCRIPTION: CEA Pulse Counter response to Reactor Trip.

AUTHOR: kkirkpa REVISION 1 REVISION DATE 06/26/1997 APPROVAL: mlangan APPROVAL DATE: 07/17/1997 REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/11/2002 TYPE: MULTIPLE CHOICE TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

REFERENCE:

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SIMULATOR SETUP PLANT SYSTEM: CED CATEGORY: SYSTEM

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NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.1-001-K4.01 3.5 3.8 W-3-LP-OPS-CED00 17 QUESTION All CEAs are initially at 150. CHOOSE the correct CEA Pulse Counter indication following a reactor trip in which all CEAs fully insert.

A. Green LEL lights on CEDMCs Panel illuminate B. Rod Bottom light on the Core Mimic illuminate C. Selected Individual CEA Display indicates 150 D. Selected CEA Group Display indicates 0 ANSWER D. Selected CEA Group Display indicates 0 COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-1 Bank Question History Page 40 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 38 QUESTION ID: 6029 - STATUS: Revision LAST USED A

DESCRIPTION: Post Trip Xenon AUTHOR: dvince1 REVISION 1 REVISION DATE 06/23/2002 APPROVAL: APPROVAL DATE:

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NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.1-001-K5.85 3.5 3.7 W-3-LP-OPS-TYR06 7 QUESTION The reactor has just tripped from 100% power at 13 EFPD. How long will it take for xenon to reach its pre-trip value?

A. 70 to 80 hours9.259259e-4 days 0.0222 hours 1.322751e-4 weeks 3.044e-5 months B. 40 to 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months C. 20 to 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months D. 6 to 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months ANSWER C. 20 to 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months COMMENTS Rewrite of question #3891.

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Waterford 3 Examination Question Examination Bank Examination Question Number 39 QUESTION ID: 5975 - STATUS: Revision LAST USED A

DESCRIPTION: RCP and Containment Isolation Valves AUTHOR: dvince1 REVISION 1 REVISION DATE 06/11/2002 APPROVAL: APPROVAL DATE:

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OP-901-411 01 02 07/30/2001 OP-500-008 15 00 03/27/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.4-003-K6.04 2.8 3.1 W-3-LP-OPS-RCP00 6 QUESTION A small RCS leak occurs in RCP 1A seal cooler. CCW AB Rad Monitor activity is rising. Which one of the following would be an action taken for this event?

A. Open the RCP 1A CCW Isolation valve on CP-2.

B. Open CC-710, CCW to Containment Isolation.

C. Isolate the NNS Component Cooling Water Header.

D. Trip the Reactor and secure all reactor coolant pumps.

ANSWER A. Open the RCP 1A CCW Isolation valve on CP-2.

COMMENTS Note - Reference material OP-500-008, revision does not match because of Procedure Revision Policy that only revises the affected attachment of the Annunciator Response and not all attachments.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-1 New Question History Page 42 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 40 QUESTION ID: 5976 - STATUS: Revision LAST USED A

DESCRIPTION: CVCS and effects on RCS Temp & Pressure AUTHOR: dvince1 REVISION 1 REVISION DATE 06/11/2002 APPROVAL: APPROVAL DATE:

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OP-002-005 18 00 04/12/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.1-004-K3.06 3.4 3.6 wlp-ops-cvc00 6 W-3-LP-OPS-PSC04 28 QUESTION The plant is at 100% power. The CVCS Ion Exchanger Bypass Switch, CVC-140, is selected to the Ion Exchanger position for testing. The Letdown Heat Exchanger Temperature Control Valve, CC-636, controller fails closed. Letdown Heat Exchanger outlet temperature rises to 180°F. Assuming no operator action, which one of the following would occur as a result of this event?

A. CVC-140 will automatically bypass.

B. RCS temperature will lower.

C. Pressurizer level will rise.

D. Volume Control Tank will divert.

ANSWER B. RCS temperature will lower.

COMMENTS RCS temperature lowers as the IX resin breaks down and releases boron with temperature increase.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-1 New Question History Page 43 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 41 QUESTION ID: 3458 - STATUS: Approved LAST USED A

DESCRIPTION: CVC-101 Auto Closures.

AUTHOR: NRC REVISION 0 REVISION DATE 01/06/1995 APPROVAL: tbrown APPROVAL DATE: 01/11/1995 REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/11/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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OP-002-005 18 00 04/12/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.2-004-A2.07 3.4 3.7 W-3-LP-OPS-CVC00 3 QUESTION WHICH ONE (1) of the following sets of signals will AUTOMATICALLY close the Letdown Stop valve (CVC-101)?

A. CIAS or HIGH letdown heat exchanger outlet temperatures.

B. CIAS or HIGH regenerative heat exchanger outlet temperature.

C. SIAS or HIGH letdown heat exchanger outlet temperatures.

D. SIAS or HIGH regenerative heat exchanger outlet temperature.

ANSWER D. SIAS or HIGH regenerative heat exchanger outlet temperature.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-1 Bank Question History Page 44 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 42 QUESTION ID: 5977 - STATUS: Revision LAST USED A

DESCRIPTION: ESFAS - bus power supplies AUTHOR: dvince1 REVISION 1 REVISION DATE 06/11/2002 APPROVAL: APPROVAL DATE:

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OP-009-007 05 01 02/08/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.2-013-K2.01 3.6* 3.8 WLP-OPS-PPS00 2 QUESTION The plant is at 100% power. Maintenance is being performed on PPS Channel A and all PPS Channel A bistables are bypassed. The technician inadvertently de-energizes PPS Channel A completely. Which one of the following is TRUE as a result of this action?

A. The bistable bypasses are no longer in effect.

B. The reactor will trip.

C. Safety Injection Actuation will occur.

D. Excore Nuclear Instrumentation Safety Channel A will de-energize.

ANSWER D. Excore Nuclear Instrumentation Safety Channel A will de-energize.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-1 New Question History Page 45 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 43 QUESTION ID: 5978 - STATUS: Revision LAST USED A

DESCRIPTION: Inadvertent RAS AUTHOR: dvince1 REVISION 1 REVISION DATE 06/11/2002 APPROVAL: APPROVAL DATE:

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OP-901-504 02 01 06/03/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.2-013-A2.06 3.7* 4 W-3-LP-OPS-PPO50 3 WLP-OPS-SI00 3 QUESTION If the plant is at 100% power and an inadvertent Recirculation Actuation Signal (RAS) occurred, which of the following would be a potential concern? Assume no surveillances in progress.

A. Loss of Low Pressure Safety Injection Pumps due to trip signal.

B. Loss of Safety Injection suction due to SI-106A & B, ESF Pump Suction RWSP Valves, closing.

C. Loss of Safeguards Pumps recirculation protection due to SI-120A & B, SI Pumps Recirc Isol Valves, closing.

D. Potential Containment Isolation concern due to SI-602A & B, ESF Pumps Suction SI Sump Valves, opening.

ANSWER D. Potential Containment Isolation concern due to SI-602A & B, ESF Pumps Suction SI Sump Valves, opening.

COMMENTS Note - A is wrong because the trip signal is in for only 1 second and the pumps can be restarted. B&C are wrong because SI-106s and SI-120s do not get a close signal. D is correct because SI-602s are part of the Containment Isolation requirement.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-1 New Question History Page 46 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 44 QUESTION ID: 5979 - STATUS: Revision LAST USED A

DESCRIPTION: ENI and criticality AUTHOR: dvince1 REVISION 1 REVISION DATE 06/11/2002 APPROVAL: APPROVAL DATE:

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OP-010-003 01 02 04/03/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.7-015-K5.05 4.1 4.4 WLP-OPS-PPN01 3 QUESTION A reactor startup is in progress. The plant had shutdown after 50 EFPD to repair a RCP seal. The PNPO is withdrawing Regulating Group 6 to 50 inches withdrawn. After the withdrawal is completed, the PNPO determines that 3 doublings have occurred by looking at Startup Channels. As the next CEA movement is begun, when should the PNPO be expecting criticality to occur?

A. When the Reactor Engineer determines it using the 1/M plot.

B. When the 5th doubling occurs.

C. At all times.

D. When the CEAs are withdrawn to the critical rod height position.

ANSWER C. At all times.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-1 New Question History Page 47 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 45 QUESTION ID: 5980 - STATUS: Revision LAST USED A

DESCRIPTION: ENI and Boron Dilution Monitors AUTHOR: dvince1 REVISION 1 REVISION DATE 06/11/2002 APPROVAL: APPROVAL DATE:

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OP-903-001 25 00 05/30/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.7-015-A3.03 3.9 3.9 W-3-LP-OPS-ENI00 4 QUESTION The plant has been shutdown for 8 days going into a refueling outage. The following alarms are received on CP-4, Cabinet G - RCS Boron Chnl 1 Dilution Hi and RCS Boron Chnl 2 Dilution Hi. The PNPO reports the following plant conditions:

Reactor power is 10 x E-7% and stable.

RCS Temperature is 150 degrees F and stable

RCS Boron Dilution Monitor #1 process is reading 2 x 102 CPS

RCS Boron Dilution Monitor #1 setpoint is reading 3 x 102 CPS

RCS Boron Dilution Monitor #2 process is reading 3.8 x 102 CPS

RCS Boron Dilution Monitor #2 setpoint is reading 5.6 x 102 CPS Based on this information, the crew should:

A. Declare the RCS Boron Dilution Monitors inoperable.

B. Commence Emergency Boration.

C. Switch the ENI Startup High Voltage Control Switches to Primary.

D. Adjust the RCS Boron Dilution Monitors setpoints to less than or equal to 2 times process.

ANSWER D. Adjust the RCS Boron Dilution Monitors setpoints to less than or equal to 2 times process.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-1 New Question History Page 48 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 46 QUESTION ID: 5981 - STATUS: Revision LAST USED A

DESCRIPTION: CETs and Superheat AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

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OP-902-009 00 01 12/16/1999 OP-902-002 09 00 04/12/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.7-017-K5.03 3.7 4.1 WLP-OPS-MCD03 2 Page 49 of 104

QUESTION A Loss of Coolant Accident has occurred concurrent with a loss of power to the 3A Safety Bus. Plant conditions are as follows:

RCS Pressure - 1318 PSIA and slowly dropping

Representative CET - 581°F and slowly dropping

RCS Tcold - 568°F and slowly dropping

Pressurizer Level - 0%

RVLMS - 40% Plenum Level

RWSP - 89% and slowly dropping

Steam Generator Level #1 - 58% WR and slowly dropping

Steam Generator Level #2 - 59% WR and slowly dropping

EFW flow to both Steam Generators - 0 gpm

Charging Pump B running

HPSI flow - 55 GPM per loop

LPSI flow - 0 GPM per loop

Containment Pressure - 18.5 psia and stable

Containment temperature - 238°F and stable Assuming that all ESFAS actuations occurred as required, state which Safety Function criteria is NOT met A. RCS Inventory Control B. RCS Pressure Control C. Core Heat Removal D. RCS Heat Removal ANSWER C. Core Heat Removal COMMENTS Give copy of SFSC for OP-902-002 (pages 51-60), OP-902-009, Appendix 2A, 2B, and 2C, and copy of steam tables.

Note - D is the wrong choice because per Operations Expectations, SG Levels are met until EFW fails to work in automatic and start feeding at 55% WR.

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Waterford 3 Examination Question Examination Bank Examination Question Number 47 QUESTION ID: 5982 - STATUS: Revision LAST USED A

DESCRIPTION: CFC Fans and Power AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

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OP-500-002 14 00 03/20/2002 OP-008-003 05 01 02/27/1997 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.5-022-K2.01 3.0* 3.1 WLP-OPS-CCS00 4 QUESTION Containment Fan Coolers A, B, and C are running in Fast. An annunciator on Panel B, TRN A Cntmt Cooler Vlv Power Lost, goes into alarm. The RAB watch reports that CCS-EBKR-60A-17, Containment Cooling Train A CCW Valves, is in the trip-free position. The SNPO reports that Containment Fan Cooler A CCW Isolation Valves are indicating no power. What is the amount of Component Cooling Water to Containment Fan Cooler A?

A. 700 GPM B. 0 GPM C. 1400 GPM D. 1000 GPM ANSWER A. 700 GPM COMMENTS Per CWD 1134 these valves are energized to close. The CFC Flow Control Valve controls the amount of flow to the CFCs. So with the isolation valves failed open, CFC flow is 700 GPM (normal for Fast). B is wrong because there will still be flow, C is wrong because this is the amount for Slow speed. D is wrong because there is no 1000 GPM flow for these valves. Note - Reference material OP-500-008, revision does not match because of Procedure Revision Policy that only revises the affected attachment of the Annunciator Response and not all attachments.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-1 New Question History Page 51 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 48 QUESTION ID: 5983 - STATUS: Revision LAST USED A

DESCRIPTION: CEDM Fans and Interlocks AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

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OP-008-004 05 03 04/04/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.5-022-K4.04 2.8 3.1 WLP-OPS-CCS00 5 QUESTION One of the automatic functions associated with the Control Element Drive Mechanism Fans is ___________________________.

A. Starting when the Reactor Trip Breakers are closed in.

B. Stopping when a Containment Isolation Actuation Signal occurs.

C. Starting when the EDG Sequencer times out its load block.

D. Stopping when a Safety Injection Actuation Signal occurs.

ANSWER D. Stopping when a Safety Injection Actuation Signal occurs.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-1 New Question History Page 52 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 49 QUESTION ID: 5984 - STATUS: Revision LAST USED A

DESCRIPTION: Condensate and MFW AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

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OP-902-008 12 00 04/12/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.4-056-K1.03 2.6* 2.6 WLP-OPS-CD00 7 WLP-OPS-PPE08 9 QUESTION A Station Blackout concurrent with a loss of Emergency Feedwater Pump AB has occurred. Steam Generator levels are approaching 55% WR when the 6.9KV Bus 1A is re-energized. The CRS directs restoring SG Inventory. Given current plant conditions, how will this be accomplished?

A. Restore available feedwater path and use Auxiliary Feedwater Pump.

B. Depressurize one Steam Generator to less than 500 psia and use Condensate Pump A.

C. Verify Main Feedwater Pump A DC Oil Pump running and use Main Feedwater Pump A.

D. Initiate Emergency Feedwater Actuation Signal #1 and use Emergency Feedwater Pump A.

ANSWER B. Depressurize one Steam Generator to less than 500 psia and use Condensate Pump A.

COMMENTS Per OP-902-008, HR-2, step 40 (page 190). A is wrong because AFW pump is powered by the 1B bus. C is wrong because the MFWP cannot be restarted without the 2A bus. D is wrong because EFW A is powered by the 3A bus.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-1 New Question History Page 53 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 50 QUESTION ID: 5985 - STATUS: Revision LAST USED A

DESCRIPTION: CD Pump A Valve and CWD AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

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NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-1-24 2.8 3.1 W-3-LP-OPS-CWD00 5 QUESTION Using CWD 1372, determine which ONE of the following is FALSE concerning the Condensate Pump A Discharge Valve.

A. The limit switch contact b% is open until the valve is greater than 20% open.

B. The annunciator panel referenced for this CWD is Panel F.

C. This valve can only be opened and closed locally.

D. The valve number is CD-144A.

ANSWER A. The limit switch contact b% is open until the valve is greater than 20% open.

COMMENTS Provide CWD 1372 as a reference.

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Waterford 3 Examination Question Examination Bank Examination Question Number 51 QUESTION ID: 5986 - STATUS: Revision LAST USED A

DESCRIPTION: MFW Pump Trips AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

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OP-003-033 00 02 01/08/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.4-059-K4.16 3.1* 3.2* W-3-LP-OPS-FWP00 6 QUESTION The plant has downpowered to 45% for repairs to Heater Drain Pumps. Condensate Pump C has been secured for tagging. The crew is briefing securing Main Feedwater Pump A. Condensate Pump B trips. What is the status of the Main Feedwater Pumps?

(Assume Feedwater Suction Pressure is adequate.)

A. Both Main Feedwater Pumps are tripped.

B. Main Feedwater Pump B is tripped.

C. Main Feedwater Pump A is tripped.

D. Both Main Feedwater Pumps are running.

ANSWER D. Both Main Feedwater Pumps are running.

COMMENTS This trip is only active when <39% Power.

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Waterford 3 Examination Question Examination Bank Examination Question Number 52 QUESTION ID: 5987 - STATUS: Revision LAST USED A

DESCRIPTION: FW Pumps and Power Levels AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

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OP-010-003 01 02 04/03/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.4-059-A1.03 2.7* 2.9* WLP-OPS-PPN01 3 QUESTION The plant is starting up and has now reached 1% power. Based on this power level, which ONE of the following would be the next action taken by the crew?

A. Complete Critical Data Logsheet.

B. Manually remove High Log Power Level Trip Bypasses.

C. Start a Main Feedwater Pump.

D. Place COLSS in service.

ANSWER C. Start a Main Feedwater Pump.

COMMENTS Note - critical data taken at 5 E-4%, High Log Power Level Trip is bypassed at 0.257%,

and COLSS is placed in service at 15%.

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Waterford 3 Examination Question Examination Bank Examination Question Number 53 QUESTION ID: 5988 - STATUS: Revision LAST USED A

DESCRIPTION: EFW and inventory AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

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OP-902-006 09 00 04/12/2001 OP-902-009 01 00 12/16/1999 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.4-061-K1.07 3.6 3.8 WLP-OPS-EFW00 5 QUESTION The crew has diagnosed to OP-902-006, Loss of Main Feedwater Recovery. All Emergency Feedwater Pumps actuated as required. Steam Generator levels are being maintained 50-70% Narrow Range using EFW in manual. While performing Safety Function Status Checks, the STA notes that the Condensate Storage Pool is 14% level.

What action should the crew take for this information?

A. Start the Auxiliary Feedwater Pump to supply feedwater.

B. Ensure EFW in automatic and allow level to control at 68-71% Wide Range.

C. Align one train of ACCW to the suction of the EFW pumps.

D. Verify Condensate Storage Pool automatic makeup is functioning correctly.

ANSWER C. Align one train of ACCW to the suction of the EFW pumps.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-1 New Question History Page 57 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 54 QUESTION ID: 5989 - STATUS: Revision LAST USED A

DESCRIPTION: Loss of EFW Pumps & TS AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

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NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.4-061-K6.02 2.6 2.7 WLP-OPS-EFW00 9 QUESTION The plant is at 100% power. Emergency Feedwater Pump A is tagged out for maintenance. An overcurrent relay on Emergency Feedwater Pump B trips causing the pump to be inoperable. Based on this, which action should be taken?

A. Enter TS 3.7.1.2d B. Enter TS 3.7.1.2e C. Enter TS 3.7.1.2f D. Enter TS 3.0.3 ANSWER A. Enter TS 3.7.1.2d COMMENTS Provide copy of TS 3.7.1.2 Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-1 New Question History Page 58 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 55 QUESTION ID: 5990 - STATUS: Revision LAST USED A

DESCRIPTION: LWM and Waste Gas Vent Header AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

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SIMULATOR SETUP PLANT SYSTEM: GWM CATEGORY: SYSTEM LWM

REFERENCE:

REVISION: CHANGE: DATE:

NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.9-068-K1.02 2.5 2.6 W-3-LP-OPS-LWM00 3 QUESTION The Liquid Waste Management System interfaces with the Gaseous Waste Management System via the A. Gas Surge Header B. Gas Analyzer C. Vent Gas Collection Header D. Gas Surge Tank ANSWER C. Vent Gas Collection Header COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-1 New Question History Page 59 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 56 QUESTION ID: 5991 - STATUS: Revision LAST USED A

DESCRIPTION: GWM and Ventilation AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/12/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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REFERENCES:

SIMULATOR SETUP PLANT SYSTEM: GWM CATEGORY: SYSTEM

REFERENCE:

REVISION: CHANGE: DATE:

NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.9-071-K3.04 2.7 2.9 WLP-OPS-GWM00 1 WLP-OPS-RMS 3 QUESTION The PNPO is venting the Volume Control Tank to the Gas Surge Tank. The packing for GWM-501, Gas Surge Tank Drain Isolation, blows out. Assuming the airborne radioactivity in the RAB reaches the alarm setpoint for the Plant Stack and HVAC Duct PIG D radiation monitors, which one of the following describes the status of the RAB Ventilation Systems?

A. CVAS Fans will be running.

B. RAB Normal Exhaust Fan will be tripped.

C. SBV Fans will be running.

D. RAB Ventilation Systems will not change.

ANSWER D. RAB Ventilation Systems will not change.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-1 New Question History Page 60 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 57 QUESTION ID: 5992 - STATUS: Revision LAST USED A

DESCRIPTION: GWM and releases AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/12/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X SIMULATOR SETUP PLANT SYSTEM: GWM CATEGORY: PROCEDURE

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OP-007-003 14 00 01/11/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.9-071-A4.06 2.8 3.3 WLP-OPS-GWM00 11 QUESTION Chemistry has sent the Gaseous Waste Release Permit to the Control Room for discharging Gas Decay Tank A. The CRS asks you to verify Meteorological Conditions are suitable for discharging the Gas Decay Tank. The PMC shows the following Meteorological Data information:

Wind Speed is 2.5 m/s.

Wind Direction is 50 degrees

Delta T is 1.43 degrees C

Air Temperature is 28.5 degrees C

Sigma Theta is 13.9 degrees Based upon the above information, the following is the status of the requirements to discharge the Gas Decay Tank:

A. Avoid Batch Gaseous Releases B. No Meteorological Restrictions on Gaseous Releases C. Releases Permitted for Stability Classes A-E.

D. No release is permitted.

ANSWER B. No Meteorological Restrictions on Gaseous Releases COMMENTS Give copy of OP-007-003, Gaseous Waste Management System, Attachment 11.5, Meteorological Conditions Requirements Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-1 New Question History Page 61 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 58 QUESTION ID: 5993 - STATUS: Revision LAST USED A

DESCRIPTION: HVF and ARM AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/12/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X SIMULATOR SETUP PLANT SYSTEM: ARM CATEGORY: ADMIN HVF

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TRM 3.3.3 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.7-072-K1.03 3.6* 3.7* w-3-lp-ops-hvf00 7 QUESTION I&C Maintenance wants to perform a calibration check on ARM-IRE-0300.1s, Fuel Handling Building Isolation Radiation Monitor. The other 3 FHB Isolation Radiation Monitors will be unaffected. Using the applicable sections of the Technical Requirements Manual, determine what action should be taken.

A. No action required.

B. Adjust Radiation Monitor Channel alarm/trip setpoint within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

C. Start the opposite Fuel Handling Building Emergency Filtration Train.

D. Suspend movement of fuel within the Spent Fuel Pool.

ANSWER A. No action required.

COMMENTS Provide copy of TRM 3.3.3.1 and TRM 3.9.12.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-1 New Question History Page 62 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 59 QUESTION ID: 5994 - STATUS: Revision LAST USED A

DESCRIPTION: HVC and ARM AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/12/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: ARM CATEGORY: SYSTEM HVC

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REVISION: CHANGE: DATE:

OP-901-401 00 01 08/06/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.7-072-A3.01 2.9* 3.1 W-3-LP-OPS-HVC00 2 WLP-OPS-RMS 2 QUESTION The crew is performing OP-903-051, Control Room Emergency Filtration Unit Operability Check, for Train A. Control Room Emergency Filtration Unit A has been running for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . Maintenance is doing an inspection of CROAIs and accidently actuates ARM-IRE-0200.1, CROAI A North Radiation Monitor. Which one of the following will be TRUE about Control Room Ventilation?

A. Control Room Emergency Filtration Unit B will be running.

B. Control Room Normal Ventilation Fans will be tripped.

C. Control Room Toilet Exhaust Fans will be tripped.

D. Kitchen/Conference Room Exhaust Fan will be running.

ANSWER C. Control Room Toilet Exhaust Fans will be tripped.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-1 New Question History Page 63 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 60 QUESTION ID: 5995 - STATUS: Revision LAST USED A

DESCRIPTION: RCS and TS 3.4.1.3 AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

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X SIMULATOR SETUP PLANT SYSTEM: RCS CATEGORY: ADMIN TS

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REVISION: CHANGE: DATE:

TS 3.4.1 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.4-002-K6.02 3.6 3.8 W-3-LP-OPS-RCS00 8 QUESTION The plant is in Mode 4. Reactor Coolant Pump 1A and SDC Train A are running. SDC Train B and RCP 2A are out of service. A Loss of Offsite Power occurs. Both Emergency Diesels start and re-energize the safety busses. SDC Train A is verified running. In relation to the Reactor Coolant System Technical Specifications, what is the applicable action for this event?

A. Immediately initiate corrective action and be in Mode 5 within twenty-four hours.

B. Suspend all operations involving a reduction in boron concentration.

C. No action required for up to one hour as long as no operations causing dilution occur.

D. Ensure Pressurizer Level is greater than 26% (900 cubic feet).

ANSWER A. Immediately initiate corrective action and be in Mode 5 within twenty-four hours.

COMMENTS Provide copy of TS 3.4.1.3 Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-2 New Question History Page 64 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 61 QUESTION ID: 5996 - STATUS: Revision LAST USED A

DESCRIPTION: ESF Bypasses AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/12/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: PPS CATEGORY: SYSTEM

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REVISION: CHANGE: DATE:

OP-010-003 01 02 04/03/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.2-006-K4.21 4.1 4.3 WLP-OPS-PPS00 4 QUESTION The plant is shutdown and in Mode 5. A plant heatup is commenced. Which of the following is FALSE concerning the RPS/ESFAS Pressurizer Pressure Bypass on CP-7.

A. It is operated using a key switch.

B. This bypass must be manually removed when RCS Pressure is greater than 500 PSIA.

C. Can be operated from LCP-43, Remote Shutdown Panel.

D. Cannot be enabled until Pressurizer Pressure is less than 400 PSIA.

ANSWER B. This bypass must be manually removed when RCS Pressure is greater than 500 PSIA.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-2 New Question History Page 65 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 62 QUESTION ID: 5997 - STATUS: Revision LAST USED A

DESCRIPTION: OP-901-120 and loss of all Pzr Heaters AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/12/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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REFERENCES:

SIMULATOR SETUP PLANT SYSTEM: PPO CATEGORY: PROCEDURE

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REVISION: CHANGE: DATE:

OP-901-120 02 02 02/23/2000 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.3-010-K6.03 3.2 3.6 W-3-LP-OPS-PPO10 4 QUESTION In the event that all Pressurizer Heaters are lost and cannot be immediately restored, OP-901-120, Pressurizer Pressure Control Malfunction, requires shifting the Pressurizer Level Setpoint Source from Reactor Regulating System (RRS) to CP-2 (RTGB). What is the purpose of this action?

A. Ensures Pressurizer can be maintained at upper band until heaters repaired.

B. RRS will not control Pressurizer Level correctly with all Pressurizer Heaters failed.

C. Defeats the Pressurizer Level input into the Pressurizer Pressure Controller.

D. Allows maintaining Pressurizer Level constant during required plant shutdown.

ANSWER D. Allows maintaining Pressurizer Level constant during required plant shutdown.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-2 New Question History Page 66 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 63 QUESTION ID: 5998 - STATUS: Revision LAST USED A

DESCRIPTION: Pzr Level Control and Loss of Charging Pumps AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/12/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: PPO CATEGORY: PROCEDURE

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OP-901-112 02 03 10/18/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.2-011-A2.04 3.5 3.7 W-3-LP-OPS-PPO10 6 QUESTION A large leak has occurred in the Charging Pump Discharge Header and flow cannot be established through the normal Charging Pump discharge path. The crew enters OP-901-112, Charging or Letdown Malfunction, and will restore Charging flow by aligning the Charging Header to HPSI and:

A. Starting HPSI Pump A and aligning SI-506A, HPSI Hot Leg Injection Flow Control Valve.

B. Starting HPSI Pump A and aligning any HPSI Cold Leg Injection Valve.

C. Aligning SI-506A, HPSI Hot Leg Injection Flow Control Valve and starting any Charging Pump.

D. Aligning any HPSI Cold Leg Injection Valve and starting any Charging Pump.

ANSWER D. Aligning any HPSI Cold Leg Injection Valve and starting any Charging Pump.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-2 New Question History Page 67 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 64 QUESTION ID: 5999 - STATUS: Revision LAST USED A

DESCRIPTION: RCS Inventory in OP-902-000 AUTHOR: dvince1 REVISION 1 REVISION DATE 06/12/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/12/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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REFERENCES:

SIMULATOR SETUP PLANT SYSTEM: PPE CATEGORY: PROCEDURE

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REVISION: CHANGE: DATE:

OP-902-000 09 00 02/12/2001 OI-038-000 01 01 08/23/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-4-1 4.3 4.6 WLP-OPS-PPE01 11 QUESTION The reactor was tripped due to a lube oil emergency on RCP 1A. The crew is carrying out OP-902-000, Standard Post Trip Actions. The PNPO notes that the Reactor Regulating System Hot Leg Indicator, RC-ITI-0111X, has failed high and Pressurizer Level setpoint is high also. The PNPO reports this and that all charging pumps are running. Pressurizer level is approaching 60%. What should the crew do about this failure?

A. Take no action until Standard Post Trip Actions are completed.

B. Enter OP-901-110, Pressurizer Level Control Malfunction, and perform concurrently with OP-902-000.

C. Place the Pressurizer Level Controller in manual and adjust Pressurizer Level as needed.

D. Secure two charging pumps by placing their control switches to Off.

ANSWER C. Place the Pressurizer Level Controller in manual and adjust Pressurizer Level as needed.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-2 New Question History Page 68 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 65 QUESTION ID: 6000 - STATUS: Revision LAST USED A

DESCRIPTION: PPS Trips AUTHOR: dvince1 REVISION 1 REVISION DATE 06/16/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/16/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: PPS CATEGORY: SYSTEM

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REVISION: CHANGE: DATE:

OP-009-007 05 01 02/08/2001 TS 3.3.1 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.7-012-A3.06 3.7 3.7 WLP-OPS-PPS00 9 WLP-OPS-TS04 1 QUESTION The plant is at 100%. CPC A LPD and DNBR bistables are in bypass for I&C Maintenance. I&C will be causing these bistables to trip and reset. While this is going on, CPC B fails and trips its LPD and DNBR bistables. What actions should the crew take as a result of this event? Assume I&C cannot restore CPC A within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

A. Bypass CPC B LPD and DNBR bistables within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

B. Remove CPC A bistables from bypass and bypass CPC B bistables within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

C. Perform a warm restart of CPC B within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

D. Place CPC B LPD and DNBR bistables in trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ANSWER D. Place CPC B LPD and DNBR bistables in trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

COMMENTS Provide copy of TS 3.3.1. Based upon actual event in plant.

Cognitive Level Tier-Group RO SRO Question Source Comprehensive or Analysis 2-2 New Question History Page 69 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 66 QUESTION ID: 6001 - STATUS: Revision LAST USED A

DESCRIPTION: Rod Bottom Lights & Immediate Operator Actions AUTHOR: dvince1 REVISION 1 REVISION DATE 06/16/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/16/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: CED CATEGORY: SYSTEM

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REVISION: CHANGE: DATE:

NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.1-014-K4.03 3.2 3.4 W-3-LP-OPS-CED00 17 QUESTION The plant is at 100% power when CEA #1 drops into the core. The crew enters OP-901-102, CEDMCS or CEA Malfunction, and are performing a downpower brief.

After the brief is completed, the PNPO notes that CEA #2 rod bottom light is now illuminated and CEA #2 is indicating zero inches on CP-2 but the Lower Electrical Limit is not illuminated. A lamp test verifies LEL is functioning. The CEAC CRT for CEAC

1 on CP-2 shows CEA #2 inserted with a dotted line. Based on this information the crew should:

A. Continue the downpower.

B. Trip the reactor.

C. Evaluate Technical Specification 3.1.3.2, CEA Position Indicating Channels.

D. Enter OP-901-102, subsection E5, CEA Position Indication Malfunction, and perform concurrently.

ANSWER B. Trip the reactor.

COMMENTS The rod bottom light comes off a different set of switches than the RSPT. Also, it resets the pulse counters.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-2 New Question History Page 70 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 67 QUESTION ID: 3475 - STATUS: Approved LAST USED A

DESCRIPTION: T-Cold failed low AUTHOR: NRC REVISION 0 REVISION DATE 01/06/1995 APPROVAL: tbrown APPROVAL DATE: 01/11/1995 REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/16/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

REFERENCE:

X OPEN REFERENCE X SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM: RR CATEGORY: SYSTEM

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REVISION: CHANGE: DATE:

NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.7-016-A2.01 3.0* 3.1* W-3-LP-OPS-RR00 5 QUESTION The following conditions exist:

The plant is at 100% power The selected control channel T-Cold fails LOW Select the correct response of calculated Delta-T power as a result of this failure.

A. Tavg lowers, Delta-T power lowers.

B. Tavg increases, Delta-T power rises.

C. Tavg lowers, Delta-T power rises.

D. Tavg rises, Delta-T power lowers.

ANSWER C. Tavg lowers, Delta T rises.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-2 Bank Question History Page 71 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 68 QUESTION ID: 6002 - STATUS: Revision LAST USED A

DESCRIPTION: Containment Spray & Containment Sump Level AUTHOR: dvince1 REVISION 1 REVISION DATE 06/16/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/16/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: CS CATEGORY: SYSTEM

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NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.5-026-A1.03 3.5 3.5 WLP-OPS-CS00 1 QUESTION Which ONE of the following ensures adequate suction for the Containment Spray Pumps following a Recirculation Actuation Signal (RAS)?

A. Trisodium Phosphate Dodecahydrate baskets in Containment Sump.

B. Open throat nozzles in Containment Discharge line.

C. Mesh screens in Containment Sump.

D. Shutdown Cooling Heat Exchanger.

ANSWER C. Mesh screens in Containment Sump.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-2 New Question History Page 72 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 69 QUESTION ID: 4118 - STATUS: Approved LAST USED A

DESCRIPTION: Auto closure of CAP-101 (NRC SRO EXAM 95)

AUTHOR: NRC REVISION 0 REVISION DATE 01/15/1996 APPROVAL: tbrown APPROVAL DATE: 02/07/1996 REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/16/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

REFERENCE:

X OPEN REFERENCE X SPECIAL

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SIMULATOR SETUP PLANT SYSTEM: HVR CATEGORY: SYSTEM

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REVISION: CHANGE: DATE:

NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.8-029-K4.03 3.2 3.5 W-3-LP-OPS-HVR00 1 QUESTION Given the following:

The plant is at 100% power

A containment purge is in progress per OP-002-010, RAB HVAC and Containment Purge

RAB Vent Mode selector switch is in Containment Purge WHICH ONE (1) of the following will AUTOMATICALLY close containment air purge (CAP) inlet damper CAP-101?

A. CAP Exhaust valves CAP-203, 204, and 205 reach greater than 52° OPEN B. A Hi (ALERT) alarm actuates on ARM-IRI-5024S (Containment Purge Isolation Area Rad Monitor)

C. Containment pressure is at -6.0 inches water below atmospheric D. RAB normal exhaust flow decreases to 62,000 scfm ANSWER D. RAB normal exhaust flow decreases to 62,000 scfm COMMENTS Used on 1995 NRC SRO Exam.

Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-2 Bank Question History Page 73 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 70 QUESTION ID: 6003 - STATUS: Revision LAST USED A

DESCRIPTION: Spent Fuel Pool Cooling AUTHOR: dvince1 REVISION 1 REVISION DATE 06/16/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/16/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: FS CATEGORY: PROCEDURE

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REVISION: CHANGE: DATE:

OP-002-006 15 06 04/13/2002 OP-901-513 02 00 06/02/1998 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.8-033-K3.03 3 3.3 W-3-LP-OPS-FS00 4 QUESTION The Spent Fuel Pool is on Purification and Spent Fuel Pool Pump A is running. A leak occurs in the Fuel Pool Purification Pump suction line. If no action is taken, all of the following will occur due to the leak EXCEPT?

A. Rising Spent Fuel Pool Temperature B. Spent Fuel Pool Pump A trip C. Uncovery of Spent Fuel Bundles D. Fuel Pool Purification Pump trip ANSWER C. Uncovery of Spent Fuel Bundles COMMENTS Siphon breakers prevent uncovery of spent fuel bundles Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-2 New Question History Page 74 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 71 QUESTION ID: 6004 - STATUS: Revision LAST USED A

DESCRIPTION: SG & ESF AUTHOR: dvince1 REVISION 1 REVISION DATE 06/16/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/16/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X OPEN REFERENCE SPECIAL

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SIMULATOR SETUP PLANT SYSTEM: EFW CATEGORY: SYSTEM SG

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REVISION: CHANGE: DATE:

NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.4-035-K1.14 3.9 4.1 WLP-OPS-EFW00 2 QUESTION The plant has been tripped due to a loss of both Main Feedwater Pumps. Emergency Feedwater Actuation Signals 1 and 2 have actuated. Currently, both Steam Generators are 25% Narrow Range and dropping slowly. If Steam Generator #1s Wide Range level indication on the A side was to fail to 50% WR, which ONE of the following describes the EFW Flow Control Valve Train A alignment to SG #1?

A. EFW Flow Control Valve would open to maintain 200 GPM.

B. EFW Flow Control Valve would open to maintain 400 GPM.

C. EFW Flow Control Valve would open fully.

D. EFW Flow Control Valve would not open.

ANSWER A. EFW Flow Control Valve would open to maintain 200 GPM.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-2 New Question History Page 75 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 72 QUESTION ID: 6005 - STATUS: Revision LAST USED A

DESCRIPTION: SG & Tube Rupture AUTHOR: dvince1 REVISION 1 REVISION DATE 06/16/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/16/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: SG CATEGORY: PROCEDURE

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REVISION: CHANGE: DATE:

OI-038-000 01 01 08/23/2001 OP-902-007 10 00 04/12/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.4-035-A4.06 4.5 4.6 WLP-OPS-PPE07 8 QUESTION A Steam Generator Tube Rupture with a concurrent loss of offsite power has occurred.

Following the rapid cooldown to 520°F Thot, which ONE of the following actions dealing with the isolation step is TRUE?

A. Isolate the affected Steam Generator by initiating Main Steam Isolation Signal.

B. If both Steam Generators have activity, isolate the one with the highest Wide Range level.

C. Although Blowdown valves fail close on a loss of power, the switches should be aligned to close.

D. The Atmospheric Dump Valve should be placed in manual and closed.

ANSWER C. Although Blowdown valves fail close on a loss of power, the switches should be aligned to close.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-2 New Question History Page 76 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 73 QUESTION ID: 6006 - STATUS: Revision LAST USED A

DESCRIPTION: Malfunctioning ADV AUTHOR: dvince1 REVISION 1 REVISION DATE 06/16/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/16/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: MS CATEGORY:

REFERENCE:

REVISION: CHANGE: DATE:

NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.4-039-A2.04 3.4 3.7 W-3-LP-OPS-MS00 4 QUESTION A controller failure causes Atmospheric Dump Valve #2 to open fully. The operators begin running back the Main Turbine to compensate for the failure. What amount of power should the operators expect to remove?

A. 2.5%

B. 5.0%

C. 7.5%

D. 10%

ANSWER B. 5.0%

COMMENTS A rewrite of question # 273B Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-2 Modified Bank Question History Page 77 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 74 QUESTION ID: 6007 - STATUS: Revision LAST USED A

DESCRIPTION: Offsite Power sources AUTHOR: dvince1 REVISION 1 REVISION DATE 06/16/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/16/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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X SIMULATOR SETUP PLANT SYSTEM: ED CATEGORY: ADMIN TS

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REVISION: CHANGE: DATE:

TS 3.8.1 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.6-062-K1.04 3.7 4.2 WLP-OPS-TS04 1 QUESTION The plant is at 50% power. Startup Transformer A is tagged out for repair. Technical Specification 3.8.1.1a has been entered and the OP-903-066, Electrical Breaker Alignment Check, was completed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago. While this is being worked on, the EDG System Engineer calls and states that the last surveillance run on EDG B showed that the air receivers did not function as required. The System Engineer states that EDG B should be considered inoperable. The SM declares EDG B inoperable. Based on this information, what action should be taken?

A. Run EDG A within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

B. Restore Startup Transformer to operability within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

C. Be in Hot Standby in the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

D. Restore EDG B to operability within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

ANSWER B. Restore Startup Transformer to operability within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

COMMENTS Give a copy of TS 3.8.1.1.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-2 New Question History Page 78 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 75 QUESTION ID: 6008 - STATUS: Revision LAST USED A

DESCRIPTION: Loss of DC Battery AB AUTHOR: dvince1 REVISION 1 REVISION DATE 06/16/2002 APPROVAL: APPROVAL DATE:

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SIMULATOR SETUP PLANT SYSTEM: DC CATEGORY: SYSTEM

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OP-901-313 01 04 06/14/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.6-063-K2.01 2.9* 3.1* W-3-LP-OPS-PPO30 4 QUESTION A loss of Battery AB bus will cause all of the following EXCEPT?

A. CCW Pump AB cannot be started nor aligned to replace CCW Pump A.

B. If EFW AB Pump is running, it will roll to a stop due to steam isolations failing closed.

C. If EFW AB Pump is running it will overspeed due to failure of governor valve.

D. Manual control of the 31 AB Bus breakers is lost.

ANSWER B. If EFW AB Pump is running, it will roll to a stop due to steam isolations failing closed.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-2 New Question History Page 79 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 76 QUESTION ID: 6009 - STATUS: Revision LAST USED A

DESCRIPTION: EDG Automatic Starts AUTHOR: dvince1 REVISION 1 REVISION DATE 06/16/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/16/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: EDG CATEGORY: SYSTEM

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NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.6-064-A3.01 4.1 4 W-3-LP-OPS-EDG00 2 QUESTION Which ONE of the following is TRUE about the Emergency Diesel Generator A Air Compressors?

A. Both are required to be operable to maintain the EDG operable.

B. Both are powered from the non-safety side of their respective MCCs.

C. Both automatically start on a SIAS or Undervoltage signal.

D. Both have receivers that contain enough air for five EDG starts each.

ANSWER D. Both have receivers that contain enough air for five EDG starts each.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-2 New Question History Page 80 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 77 QUESTION ID: 1996 - STATUS: Approved LAST US ED A

DESCRIPTION: Auto actions on high alarm CW Rad. Monitor AUTHOR: TPM REVISION 0 REVISION DATE 08/05/1991 APPROVAL: rfletch APPROVAL DATE: 11/25/1997 REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/17/2002 TYPE: MULTIPLE CHOICE TIME: 2 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: BD CATEGORY: SYSTEM RMS

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OP-003-010 16 02 08/21/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.7-073-K4.01 4 4.3 W-3-LP-OPS-BD00 2 QUESTION While discharging Blowdown to Circ Water, the Blowdown Radiation Monitor Alarms (high) with the Activity reading continuing to rise slowly. Five minutes later the Circ Water Radiation Monitors Alarms. Which of the following best describes the automatic action, which should have occurred.

A. BD-303, Blowdown to Circ Water and Metal Waste Pond Isolation valve, auto closes when the BLOWDOWN Radiation Monitor High Alarm is received.

B. BD-303, Blowdown to Circ Water and Metal Waste Pond Isolation Valve, auto closes when the CIRC Water Radiation Monitor High Alarm is received.

C. BD-303, Blowdown to Circ Water and Metal Waste Pond Isolation Valve, auto closes with HIGH CIRC Water Radiation providing the operator places the key switch to close position.

D. BD-303 Blowdown to Circ Water and Metal Waste Pond Isolation Valve, auto closes when the Circ Water Radiation ALERT Alarm is received.

ANSWER B. BD-303, Blowdown to Circ Water and Metal Waste Pond Isolation Valve, auto closes when the CIRC Water Radiation Monitor High Alarm is received.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-2 Bank Question History Page 81 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 78 QUESTION ID: 6010 - STATUS: Revision LAST USED A

DESCRIPTION: CW Pumps Start limitations AUTHOR: dvince1 REVISION 1 REVISION DATE 06/17/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/17/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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OP-003-006 11 06 06/05/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-1-20 4.3 4.2 WLP-OPS-CW00 8 QUESTION The crew is starting up the Circulating Water System. The River Water Supply Pump is running. Circ Water Pump B has been started and is running normally. The CRS directs starting Circ Water Pump A and C. Which of the following describes starting these Circ Water Pumps?

A. The River Water Supply Pump must be stopped prior to starting the second Circ Water Pump.

B. The second Circ Water Pump will start as soon as the control switch is taken to start.

C. The third Circ Water Pump may be started once the white Hold Light of the second Circ Water Pump extinguishes.

D. Three Condenser Waterboxes are required to be in service prior to starting the third Circ Water Pump.

ANSWER C. The third Circ Water Pump may be started once the white Hold Light of the second Circ Water Pump extinguishes.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-2 New Question History Page 82 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 79 QUESTION ID: 6011 - STATUS: Revision LAST USED A

DESCRIPTION: Fire Protection and Fire Doors AUTHOR: dvince1 REVISION 1 REVISION DATE 06/17/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/17/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: FPP CATEGORY: ADMIN

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FP-001-015 17 00 05/28/2002 TRM 3.7.11 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.8-086-A1.03 2.7 3.2* W-3-LP-OPS-FP00 5 QUESTION While making watchstation rounds, the RCA watch reports that Door 171, -35 RAB Access to SI Pump Room A, has a broken door latch and will not close. Based on this information, the crew should declare Door 171 inoperable and:

A. Declare Controlled Ventilation Area System Trains A Inoperable.

B. Establish a continuous fire watch.

C. Verify Door 170, -35 RAB Access to SI Pump Room A, operable by testing CVAS system.

D. Log SI Pump Room A air temperatures at least once per hour.

ANSWER C. Verify Door 170, -35 RAB Access to SI Pump Room A, operable by testing CVAS system.

COMMENTS Give copy of TRM 3.7.11, TS 3.7.7, and Attachment 8.4 & 8.5 of FP-001-015.

Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-2 New Question History Page 83 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 80 QUESTION ID: 6012 - STATUS: Revision LAST USED A

DESCRIPTION: SDC and Nil Ductility AUTHOR: dvince1 REVISION 1 REVISION DATE 06/17/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/17/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.4-005-K5.01 2.6 2.9 W-3-LP-OPS-SI00 1 WLP-OPS-TYH10 12 QUESTION In Mode 5 with RCS Loops filled, the plant is protected from brittle fracture events by ensuring:

A. Reactor Coolant Pumps all de-energized.

B. Shutdown Cooling Suction Header Relief valves are aligned for service.

C. Pressurizer level is less than 33% full.

D. Steam Generator temperature is at least 100°F above the RCS Temperature.

ANSWER B. Shutdown Cooling Suction Header Relief valves are aligned for service.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-3 New Question History Page 84 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 81 QUESTION ID: 6013 - STATUS: Revision LAST USED A

DESCRIPTION: Quench Tank Rupture disk AUTHOR: dvince1 REVISION 1 REVISION DATE 06/17/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/17/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.5-007-K3.01 3.3 3.6 W-3-LP-OPS-RCS00 6 QUESTION A Steam Generator Tube Rupture has occurred. The crew is taking actions in OP-902-007, Steam Generator Tube Rupture Recovery. Due to the CIAS, ____________ is aligned to the Quench Tank and could eventually result in rising containment pressure.

A. Reactor Vessel Gasket Leak Off B. Pressurizer Vent System C. Containment Vent Header D. RCP Control Bleedoff ANSWER D. RCP Control Bleedoff COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-3 New Question History Page 85 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 82 QUESTION ID: 4120 - STATUS: Approved LAST USED N

DESCRIPTION: Response of CCW pump AB and system with SIAS and LOOP AUTHOR: bmather REVISION 1 REVISION DATE 06/29/1996 APPROVAL: tbrown APPROVAL DATE: 07/05/1996 REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/17/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.8-008-A3.08 3.6* 3.7* W-3-LP-OPS-CC00 02, 05 QUESTION CCW pumps B and AB are operating. Although CCW pump AB is replacing A the AB bus is powered from the B-side. The CCW pump A Unavailable alarm is locked in.

Which of the following describes the status of the CCW system in the event of a concurrent loss of offsite power and SIAS?

A. CCW pumps B & AB running B. CCW pumps A & B running C. Only CCW pump B running D. All CCW pumps running ANSWER C. Only CCW pump B running COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-3 Bank Question History Page 86 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 83 QUESTION ID: 6014 - STATUS: Revision LAST USED A

DESCRIPTION: H2 Recombiners and ignition AUTHOR: dvince1 REVISION 1 REVISION DATE 06/17/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/17/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.5-028-A2.02 3.5 3.9 W-3-LP-OPS-HRA00 1 QUESTION A Loss of Coolant Accident has occurred. The Hydrogen Analyzers were put in service and now show H2 concentration in Containment is 4%. What is the concern with this concentration?

A. Corrosion B. Detonation C. Flammabilty D. Self Sustaining Reaction ANSWER C. Flammabilty COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-3 New Question History Page 87 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 84 QUESTION ID: 6015 - STATUS: Revision LAST USED A

DESCRIPTION: SBCS & RCS AUTHOR: dvince1 REVISION 1 REVISION DATE 06/17/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/17/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: SBC CATEGORY: SYSTEM

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NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.4-041-K1.05 3.5 3.6 W-3-LP-OPS-SBC00 3 W-3-LP-OPS-SBC00 4 QUESTION The Steam Bypass Control System Permissive Signal uses __________ as a bias to enable the system to respond quickly to plant disturbances.

A. Pressurizer Pressure B. RCS Temperature C. Steam Flow D. Secondary Pressure ANSWER A. Pressurizer Pressure COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-3 New Question History Page 88 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 85 QUESTION ID: 6016 - STATUS: Revision LAST USED A

DESCRIPTION: Loading Turbine AUTHOR: dvince1 REVISION 1 REVISION DATE 06/17/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/17/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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REVISION: CHANGE: DATE:

OP-010-004 01 01 04/16/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-1-32 3.4 3.8 W-3-LP-OPS-TUR00 9 QUESTION The plant is at 13% power. The Turbine is ready to roll. The HP Turbine 1st Stage Metal Temperature is 205 degrees F. MS Crossover Header Temperature is 250 degrees F.

Governor End Bearing 1 Temperature is 115 degrees F. Using OP-010-004, Attachment 9.5, Turbine Startup, determine the acceleration rate, initial load, and hold time at initial load.

A. 110 RPM, 58 MW and 50 minutes B. 180 RPM, 58 MW and 45 minutes C. 60 RPM, 58 MW and 55 minutes D. 180 RPM, 58 MW and 50 minutes ANSWER D. 180 RPM, 58 MW and 50 minutes COMMENTS Give copy of OP-010-004, Attachment 9.5, Turbine Startup Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 2-3 New Question History Page 89 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 86 QUESTION ID: 6017 - STATUS: Revision LAST USED A

DESCRIPTION: ACCW AUTHOR: dvince1 REVISION 1 REVISION DATE 06/17/2002 APPROVAL: APPROVAL DATE:

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SIMULATOR SETUP PLANT SYSTEM: ACC CATEGORY: SYSTEM

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OP-002-001 12 09 06/05/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.4-076-A2.01 3.5* 3.7* W-3-LP-OPS-CC00 3 QUESTION Which ONE of the following signals/interlocks will trip a running Auxiliary Component Cooling Water pump?

A. SIAS until loaded on Sequencer B. Low CCW Temperature C. Ground on ACCW Pump Breaker D. Low Dry Cooling Tower Basin Level ANSWER C. Ground on ACCW Pump Breaker COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-3 New Question History Page 90 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 87 QUESTION ID: 6028 - STATUS: Revision LAST USED A

DESCRIPTION: Instrument Air Dryer Pressure setpoint AUTHOR: dvince1 REVISION 1 REVISION DATE 06/21/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/21/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: AIR CATEGORY: SYSTEM

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REVISION: CHANGE: DATE:

OP-003-016 10 02 03/20/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 3.8-078-A3.01 3.1 3.2 WLP-OPS-AIR00 4 QUESTION The Instrument Air Dryers bypass at _______________.

A. 105 psig B. 100 psig C. 95 psig D. 90 psig ANSWER C. 95 psig COMMENTS Rewrite of question 2293A. Dave Vincent 6/20/02 Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 2-3 Modified Bank Question History Page 91 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 88 QUESTION ID: 6018 - STATUS: Revision LAST USED A

DESCRIPTION: Conduct of Operations - NPO Responsibilities AUTHOR: dvince1 REVISION 1 REVISION DATE 06/17/2002 APPROVAL: APPROVAL DATE:

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SIMULATOR SETUP PLANT SYSTEM: PPA CATEGORY: ADMIN

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OP-100-001 18 02 03/23/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-1-1 3.7 3.8 WLP-OPS-EXP00 2 QUESTION In accordance with OP-100-001, Operations Standards and Management Expectations, the Nuclear Plant Operator has the responsibility to do all of the following EXCEPT:

A. Authorize placement of Clearances in Mode 5 if designated by SM to do so.

B. Manually trip the reactor if approaching an automatic trip setpoint.

C. Take immediate actions in accordance with annunciator responses, abnormal and emergency procedures in order to return the unit to a safe condition.

D. Take actions necessary to maintain unit parameters within Limiting Safety System Settings for normal operations.

ANSWER B. Manually trip the reactor if approaching an automatic trip setpoint.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 3 New Question History Page 92 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 89 QUESTION ID: 6019 - STATUS: Revision LAST USED A

DESCRIPTION: TS 3.0.3 AUTHOR: dvince1 REVISION 1 REVISION DATE 06/17/2002 APPROVAL: APPROVAL DATE:

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TS 3.0.3 TS 3.7.3 TS 3.7.4 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-1-12 2.9 4 WLP-OPS-TS02 6 QUESTION Plant is at 100% power. AB Bus is aligned to the B side. A relay failure causes Dry Cooling Tower B to bypass and the crew enters TS 3.7.4a. As soon as this action is completed, CCW Pump A trips on overcurrent. The crew enters OP-901-510, Component Cooling Water Malfunction, and aligns CCW Pump AB to replace CCW Pump A. What further action should the crew take?

A. Enter TS 3.7.3.

B. Enter cascading Tech Specs on Train A.

C. Enter cascading Tech Specs for Train A and Train B.

D. Enter TS 3.0.3.

ANSWER D. Enter TS 3.0.3.

COMMENTS Provide copies of TS 3.7.3 & 3.7.4. We do not cascade on two trains.

Cognitive Level Tier-Group RO SRO Question Source Comprehensive or Analysis 3 New Question History Page 93 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 90 QUESTION ID: 6020 - STATUS: Revision LAST USED A

DESCRIPTION: Mode of Operation AUTHOR: dvince1 REVISION 1 REVISION DATE 06/17/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/17/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-1-22 2.8 3.3 W-3-LP-OPS-TS00 3 QUESTION Hot Standby is defined as a Keff of __________ and an average coolant temperature of A. < 0.99, 350°F < Tavg > 200°F B. < 0.99, 350°F C. <0.99, 200°F D. 0.99, 350°F ANSWER B. < 0.99, 350°F COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 3 New Question History Page 94 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 91 QUESTION ID: 6021 - STATUS: Revision LAST USED A

DESCRIPTION: Clearance Procedure & MOVs AUTHOR: dvince1 REVISION 1 REVISION DATE 06/17/2002 APPROVAL: APPROVAL DATE:

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UNT-005-003 16 03 05/29/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-2-13 3.6 3.8 W-3-LP-OPS-CLR00 16 QUESTION Which ONE of the following is TRUE if a Motor Operated Valve is being tagged for isolation and must be manually closed?

A. The Clearances Tagged Position must be changed to Manually Closed.

B. The MOV must be manually stroked to prove operability.

C. The System Engineer must concur with closing the MOV manually.

D. The MOV should be manually cracked off its shut seat when clearing the Danger Tag.

ANSWER D. The MOV should be manually cracked off its shut seat when clearing the Danger Tag.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 3 New Question History Page 95 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 92 QUESTION ID: 2395 - STATUS: Approved LAST USED A

DESCRIPTION: Actions for exceeding safety limit on RCS pressure AUTHOR: mjesse REVISION 1 REVISION DATE 10/18/1994 APPROVAL: tbrown APPROVAL DATE: 10/26/1994 REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/17/2002 TYPE: MULTIPLE CHOICE TIME: 1 POINTS: 1 QUIZ ONLY: CLOSED

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TS 2.1.2 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-2-22 3.4 4.1 W-3-LP-OPS-RCS00 8 QUESTION The plant is in Mode 3. The Primary Operator reports that Pressurizer Pressure indicates 2775 psia on all four safety channel meters. DETERMINE which of the following actions apply.

A. Reduce pressure to less than 2750 psia within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , be in Hot Standby within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

B. Reduce pressure to less than 2750 psia within 5 minutes. Notify NRC as soon as possible not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

C. Be in Hot Standby within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Notify NRC as soon as possible not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

D. Be in Hot Standby within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , be in Hot Shutdown within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and be in Cold Shutdown within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (TS 3.0.3).

ANSWER B. Reduce pressure to less than 2750 psia within 5 minutes. Notify NRC as soon as possible not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 3 Bank Question History Page 96 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 93 QUESTION ID: 6022 - STATUS: Draft LAST USED A

DESCRIPTION: Refueling Procedures AUTHOR: REVISION 0 REVISION DATE 06/17/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: VERIFICATION DATE:

TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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SIMULATOR SETUP PLANT SYSTEM: RF CATEGORY: ADMIN

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RF-001-001 09 00 12/12/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-2-26 2.5 3.7 W-3-LP-OPS-REQ04 3 QUESTION During Refueling, the _______________ has the authority to suspend Core Alterations.

A. Fuel Handling Supervisor B. Fuel Handling Engineer C. Core Physics Monitor D. Refueling Contractor ANSWER A. Fuel Handling Supervisor COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 3 New Question History Page 97 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 94 QUESTION ID: 3445 -B STATUS: Draft LAST USED DESCRIPTION: CNTMT building entries, areas designated as very high radiation areas AUTHOR: bcoble REVISION 0 REVISION DATE 04/02/1999 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/17/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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HP-001-213 11 02 06/06/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-3-10 2.9 3.3 W-3-LP-OPS-PPA01 2 QUESTION The three areas where access is forbidden when the reactor is in Mode 1 in accordance with HP-001-213, Control of Reactor Containment Building Power Entries are:

A. Safety Injection Sump, Containment Sump, and the Reactor Cavity B. Hot and Cold Leg D ring Wall penetrations, Safety Injection Sump, and the Reactor Cavity.

C. Hot and Cold Leg D ring Wall penetrations, Containment Sump, and the Reactor Cavity.

D. Hot and Cold Leg D ring Wall penetrations, Safety Injection Sump, and the Containment Sump ANSWER C. Hot and Cold Leg D ring Wall penetrations, Containment Sump, and the Reactor Cavity.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 3 Bank Question History Page 98 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 95 QUESTION ID: 6023 - STATUS: Revision LAST USED A

DESCRIPTION: Hi Radiation Area AUTHOR: dvince1 REVISION 1 REVISION DATE 06/17/2002 APPROVAL: APPROVAL DATE:

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HP-001-107 14 02 03/06/2002 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-3-2 2.5 2.9 WLP-OPS-PPA00 3 QUESTION Entry into a High Radiation Area A. Requires Shift Manager and Radiation Protection Superintendents permission.

B. Will always be done with a Health Physics Escort.

C. Can be exempted from RWP requirements if done under emergency conditions.

D. Will need a key since these areas are always locked.

ANSWER C. Can be exempted from RWP requirements if done under emergency conditions.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 3 New Question History Page 99 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 96 QUESTION ID: 6024 - STATUS: Revision LAST USED A

DESCRIPTION: Containment Purge AUTHOR: dvince1 REVISION 1 REVISION DATE 06/17/2002 APPROVAL: APPROVAL DATE:

REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/17/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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OP-002-010 14 00 12/06/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-3-9 2.5 3.4 W-3-LP-OPS-HVR00 8 QUESTION The plant has initiated Containment Purge to raise the Oxygen level in Containment.

While doing the purge, the TGB watch reports that the portable barometer reading on the RAB roof is reading 29.85 INHG. The PMC shows that Containment to Ambient Differential Pressure is 11.3 INWC. The CRS asks you to calculate Containment Pressure IAW OP-903-001, Att 11.15, Containment Pressure Calculation. What pressure do you report?

A. 15.15 PSIA B. 15.09 PSIA C. 15.06 PSIA D. 15.00 PSIA ANSWER B. 15.09 PSIA COMMENTS Must add 0.05 to the barometer reading. Provide copy of OP-903-001, Att 11.15, Containment Pressure Calculation.

Cognitive Level Tier-Group RO SRO Question Source Comprehensive or Analysis 3 New Question History Page 100 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 97 QUESTION ID: 3520 - STATUS: Approved LAST USED A

DESCRIPTION: Determine which actuations have occurred based on indications AUTHOR: NRC REVISION 0 REVISION DATE 01/06/1995 APPROVAL: tbrown APPROVAL DATE: 01/11/1995 REFERENCE VERIFIED: dvince1 VERIFICATION DATE: 06/18/2002 TYPE: Multiple Choice TIME: 5 POINTS: 1 QUIZ ONLY: CLOSED

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NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-4-2 3.9 4.1 W-3-LP-OPS-PPE01 11 QUESTION The following plant conditions exist:

A feedline break has occurred inside containment.

Containment pressure is 17.4 psia.

Containment radiation levels are normal.

PZR pressure is 1825 psia.

RWSP level is 90%.

S/G #1 is at 925 psia and 50% WR.

S/G #2 is at 580 psia and 20% WR.

WHICH ONE (1) of the following groups of actuation signals should have occurred?

A. SIAS, MSIS, CIAS, EFAS-1 B. SIAS, MSIS, CIAS, EFAS-2 C. SIAS, CIAS, CSAS, EFAS-1 D. MSIS, CSAS, CIAS, EFAS-2 ANSWER A. SIAS, MSIS, CIAS, EFAS-1 COMMENTS Cognitive Level Tier-Group RO SRO Question Source Comprehension or Analysis 3 Bank Question History Page 101 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 98 QUESTION ID: 6025 - STATUS: Revision LAST USED A

DESCRIPTION: Identifying Post Accident Instrumentation AUTHOR: dvince1 REVISION 1 REVISION DATE 06/18/2002 APPROVAL: APPROVAL DATE:

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NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-4-3 3.5 3.8 WLP-OPS-MCD05 1 QUESTION At Waterford 3, Post Accident Monitoring Instrumentation is designated by:

A. The instrument identification number (UNID) will have a S at the end of the number.

B. An orange border around the nameplate.

C. The instrument lettering is colored red.

D. By location on the control panel.

ANSWER B. An orange border around the nameplate.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 3 New Question History Page 102 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 99 QUESTION ID: 6026 - STATUS: Revision LAST USED A

DESCRIPTION: EOP Terms - Verifying SIAS initiation AUTHOR: dvince1 REVISION 1 REVISION DATE 06/18/2002 APPROVAL: APPROVAL DATE:

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OI-038-000 01 01 08/23/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-4-17 3.1 3.8 WLP-OPS-PPE08 9 QUESTION The CRS has asked you to verify SIAS Initiation, which one of the following should be checked?

A. SIAS alarms and status lights.

B. HPSI pump flow is acceptable.

C. SIAS alarms, status lights, pump status and flow control valves open.

D. Pumps status and flow control valves open.

ANSWER C. SIAS alarms, status lights, pump status and flow control valves open.

COMMENTS Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 3 New Question History Page 103 of 104

Waterford 3 Examination Question Examination Bank Examination Question Number 100 QUESTION ID: 5776 - STATUS: Draft LAST USED A

DESCRIPTION: Immediate Operator Actions on Control Room Evacuation.

AUTHOR: dcassid REVISION 0 REVISION DATE 06/21/2000 APPROVAL: APPROVAL DATE:

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OP-901-502 06 02 01/03/2001 NRC KA NUMBER: RO SRO TRAINING MATERIAL: OBJECTIVE 2-4-49 4 4 W-3-LP-OPS-PPO51 2 QUESTION The following are Immediate Actions in accordance with OP-901-502, Control Room Evacuation, with the EXCEPTION of:

A. Trip the Reactor and verify all CEAs fully inserted.

B. Verify SGFPs are in Reactor Trip Override.

C. Reset the Moisture Separator Reheater controls.

D. Verify Pressurizer Spray Valve Selector Switch is in Both.

ANSWER B. Verify SGFPs are in Reactor Trip Override.

COMMENTS REF: OP-901-502, Evacuation of the Control Room and Subsequent Plant Shutdown.

R5 C2. Page 5.

Used on 2000 NRC SRO Initial Written Examination.

Cognitive Level Tier-Group RO SRO Question Source Memory or Fundamental Knowledge 3 Bank Question History Used on 2000 NRC SRO Initial Written Examination Page 104 of 104

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