Text

August 2003 - Init Exam - SRO Only Written Examination Reference as Given
	ML032690973
Person / Time
Site:	Waterford
Issue date:	06/26/2003
From:	Gody A; Division of Reactor Safety IV
To:	Venable J; Entergy Nuclear Operations
References
	50-382/03-301 50-382/03-301
	Download: ML032690973 (27)
	v • d • e

Waterford 3 Examination Question Page 1 of 27 Examination Question Number 1

QUESTION ID:

5958 A

STATUS:

Revision LAST USED DESCRIPTION:

Reactor Trip Recovery AUTHOR:

avest REVISION 3

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

avest VERIFICATION DATE:

5/14/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

PPE CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

OP-902-009 1.1 00 12/13/2002 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 4.1-E7-EK3.01 4.0 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 low lube oil pressure.

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

Startup Transformer A differential current trip was detected and EDG A failed to start.

Pressurizer Pressure dropped to a low value of 1950 psia and all Pressurizer Backup Heaters had to be manually started.

Assuming all other indications responded as expected for an uncomplicated trip. As CRS, which Emergency Operating Procedure would you transition to and why?

A. OP-902-001, Reactor Trip Recovery, because procedure supports loss of power to one train of offsite power.

B. OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery, due to loss of electrical busses.

C. OP-902-006, Loss of Main Feedwater Recovery, due to loss of the feedwater pump.

D. OP-902-008, Functional Recovery, due to not meeting all safety functions in OP-902-000.

ANSWER A

COMMENTS Provide examinee with current revision of OP-902-009,Standard Appendices, Appendix 1, Diagnostics Flowchart B is wrong because the plant must lose all offsite power or all RCPs to reach it via diagnostics.

C is wrong because Feed pump B is still operating.

D is wrong because listed conditions do not require entry.

Cognitive Level: Comprehension/Analysis Tier/Group: 1/1 Question Source: Modified 10CFR Part 55 Content: 43.5

Page 2 of 27 Examination Question Number 2

QUESTION ID:

5572 A

STATUS:

Revision LAST USED DESCRIPTION:

Determine if HPSI throttle criteria is met during a PZR STM space break.

AUTHOR:

avest REVISION 2

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

avest VERIFICATION DATE:

5/15/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

PPE CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

OP-902-002 09 00 4/12/2001 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 4.2-A8-AA2.23 3.6 4.3 W-3-LP-OPS-PPE02 24 QUESTION The following conditions exist:

RCS Pressure is currently 1050 psia and stable.

100 gpm HPSI flow to each cold leg loop indicated on CP-8.

Containment pressure and Quench Tank pressure are 25 psia and rising together.

T-cold, T-hot, and Representative CET temperatures indicate 545 °F.

QSPDS levels 1 through 6 indicate voided on QSPDS 1 and 2

Vessel Plenum level on CP-7 reads 40%

SG 1 level is cycling between 68 and 71% WR

SG 2 level is 57% WR and dropping slowly

Pressurizer level is 100%.

Which course of action should you order?

A. Stop one HPSI pump and throttle flow on the other train.

B. Stop Both HPSI pumps one pump at a time.

C. Continue to allow full HPSI flow into the RCS.

D. Restore Letdown to service and attain Pzr level 33 - 60%.

ANSWER C

COMMENTS Pressurizer Safety valve is failed open, plenum level and subcooled margin are not met.

Ref. OP-902-002 Pgs. 21 and 37.

A and B would be viable options per step 23 of OP-902-002, if HPSI Throttle criteria were met.

D is a viable option for reducing pressurizer level if a true excess inventory condition exists per step 28 of OP-902-002.

Cognitive Level: Comprehension/Analysis Tier/Group: 1/1 Question Source: Modified 10CFR Part 55 Content: 43. 5

Page 3 of 27 Examination Question Number 3

QUESTION ID:

6059 A

STATUS:

Revision LAST USED DESCRIPTION:

Small Break LOCA Knowledge of Symptom Based EOP mitigation strategies AUTHOR:

avest REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

avest VERIFICATION DATE:

6/2/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

PPE CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

OP-902-002 09 00 4/12/2001 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 2-4-6 3.1 4.0 WLP-OPS-PPE02 18

Page 4 of 27 QUESTION Given the following:

Containment Pressure = 18.0 psia

S/G 1 pressure = 800 psia; S/G 2 pressure = 780 psia

S/G 1 level = 70% WR; S/G 2 Level = 68% WR

EFAS-1 and 2 were manually initiated and controllers are in Auto

Representative CET temperature is 380ºF

RCS pressure = 250 psia

RVLMS indicates 0% head level and 100% plenum level

RAS has occurred

LOCA occurred at 1520; Current time is 1800 Which of the following actions would be appropriate at this time?

A. Reset Containment Spray Actuation Signal to minimize corrosion of containment components and H2 generation.

B. Align one train of Shutdown Cooling for operation and commence RCS cooldown.

C. Restart one Reactor Coolant Pump in each loop to maximize heat removal capability.

D. Depressurize the S/Gs to restore them as a heat sink and cool the RCS to restore subcooled margin.

ANSWER D

COMMENTS A is incorrect because RAS has occurred and containment pressure is above CSAS setpoint.

B is incorrect because Shutdown Cooling entry conditions are not met.

C is incorrect because RCP operating curves are not met and CSAS has isolated CCW to the RCP seals for greater than 10 minutes.

D is correct because subcooled margin is < 28ºF and the S/Gs are currently hotter than the RCS so they must be steamed to get them to equilibrium conditions with the RCS before the RCS can be cooled down.

Cognitive Level: Comprehension/Analysis Tier/Group: 1/ 1 Question Source: New 10CFR Part 55 Content: 43. 5

Page 5 of 27 Examination Question Number 4

QUESTION ID:

6035 A

STATUS:

Revision LAST USED DESCRIPTION:

Appropriate procedure for rising containment sump level SDC malfunction AUTHOR:

evines REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

evines VERIFICATION DATE:

5/20/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

X SIMULATOR SETUP PLANT SYSTEM:

PPO CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

OP-901-131 OP-901-111 02 01 00 05 1/8/2002 6/14/2001 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 4.2-A25-AA2.03 3.6 3.8 WLP-OPS-PPO10 WLP-OPS-REQ21 01 01 QUESTION Given the following;

The plant is in Mode 5.

Shutdown cooling is in operation.

RCS level currently at 15 feet 1 inch and lowering.

Containment Sump and Safety Injection Sump levels rising.

Which of the following procedures would be fully implemented at this time?

A. OP-901-111, Reactor Coolant System Leak.

B. OP-901-131, Shutdown Cooling Malfunction.

C. OP-902-002, Loss of Coolant Accident Recovery.

D. OP-902-008, Functional Recovery Procedure.

ANSWER B

COMMENTS A is incorrect because OP-901-111 step 1 transitions to OP-901-131 B is Correct because OP-901-111 step 1 transitions to OP-901-131 C is incorrect because OP-902-002 would not be implemented in Mode 5 D is incorrect because OP-902-008 would not be implemented in Mode 5 Cognitive Level: Comprehension/Analysis Tier/Group: 1/ 1 Question Source: New Bank Modified 10CFR Part 55 Content: 43. 5

Page 6 of 27 Examination Question Number 5

QUESTION ID:

2894 A

STATUS:

Revision LAST USED DESCRIPTION:

NRC notifications AUTHOR:

avest REVISION 3

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

9/22/1997 REFERENCE VERIFIED:

avest VERIFICATION DATE:

6/2/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

OPEN REFERENCE X

SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

EP PPA CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

EP-001-020 UNT-006-010 26 17 01 02 4/20/2003 5/23/2002 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 2-4-41 2.3 4.1 W-3-LP-EP-SS 64 QUESTION Which one of the following events requires a notification to the NRC via ENS within ONE hour?

A. Exposure of.5 REM to the hands of a Radiation Technician while handling special nuclear material.

B. The reactor failed to trip automatically when TWO RC pressure instruments exceeded their reactor trip setpoint.

C. An unplanned reactor trip occurs from 100% power, due to failure of a main feedwater pump turbine.

D. One train of HPSI is inoperable for two hours due to inadvertently isolating a train while hanging clearance tags.

ANSWER B

COMMENTS A is incorrect, the threshold for a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months report to the NRC for Personnel exposure to extremeities is >250 Rad UNT 006-010 7.3.1 B is correct this is an Alert requiring 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months notification C is incorrect, 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months report to NRC UNT 006-010 7.2.8 D is incorrect, 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months report to NRC UNT 006-010 7.3.12 Cognitive Level: Memory Tier/Group: 1/ 1 Question Source: Bank 10CFR Part 55 Content: 43. 5

Page 7 of 27 Examination Question Number 6

QUESTION ID:

6036 A

STATUS:

Revision LAST USED DESCRIPTION:

Determine magnitude of offsite dose during SGTR using atmospheric dump valves AUTHOR:

evines REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

evines VERIFICATION DATE:

5/20/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

EP CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

EP-002-050 15 03 3/31/1998 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 4.1-E38-EA2.14 3.3*

4.6 WLP-OPS-EP02 22 QUESTION Given the following conditions; A tube rupture has occurred in S/G 1 The main condenser is not available.

A cooldown using the Atmospheric Dump Valves is required.

MSL 1 Radiation Monitor reads 20 mR/hr.

Met. Tower data;

§ Wind Speed = 1.8 m/sec

§ Differential Temp = -0.75 ºC Using the Nomogram, determine the projected TEDE dose at the exclusion area boundary for a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months event duration.

A. 50 mrem B. 100 mrem C. 160 mrem D. 200 mrem ANSWER B

COMMENTS Provide examinee with copy of EP 002-050 sect 3.0 and nomogram (D-EP-004)

A is incorrect because this value is the result of not multiplying the dose rate by the 2 hr duration B is correct.

C is incorrect because this value is the result of using the assumed flowrate for a S/G safety vice the Atmospheric Dump Valve.

D is incorrect because this value is the result of using the wrong stability class (D vs. C).

Cognitive Level: Comprehension/Analysis Tier/Group: 1/ 1 Question Source: New 10CFR Part 55 Content: 43. 5

Page 8 of 27 Examination Question Number 7

QUESTION ID:

6037 A

STATUS:

Revision LAST USED DESCRIPTION:

Reduction of loads on Station Battery during Station Blackout AUTHOR:

evines REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

evines VERIFICATION DATE:

5/22/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

DC PPE CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

OP-902-005 11 00 4/12/2001 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 4.1-E55-EA1.04 3.5 3.9 WLP-OPS-PPE05 03 QUESTION Given the following Conditions:

At 0800 a Station Blackout occurred

Restoration of AC power is not anticipated until 1130.

Which of the following describe when you as the CRS must instruct the NPO to have the steps for reducing unnecessary station Battery loads completed?

A. 0815 B. 0830 C. 0845 D. 0900 ANSWER B

COMMENTS A is correct OP-902-005 step 14 requires reducing station loads if power is not expected to be restored within 30 minutes B is incorrect must reduce loads within 30 minutes C is incorrect must reduce loads within 30 minutes D is incorrect must reduce loads within 30 minutes Cognitive Level: Comprehension/Analysis Tier/Group: 1/ 1 Question Source: New 10CFR Part 55 Content: 43. 5

Page 9 of 27 Examination Question Number 8

QUESTION ID:

6033 A

STATUS:

Revision LAST USED DESCRIPTION:

Required Time and reason for downpower after a dropped CEA AUTHOR:

evines REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

evines VERIFICATION DATE:

5/20/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

CED TS PPO CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

TS 3.1.3 TS BASES OP-901-102 03 02 8/7/2001 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 4.2-A3-AK3.04 3.8*

4.1*

WLP-OPS-PPO10 WLP-OPS-PPO10 03 05 QUESTION While at 80% power, a shutdown bank CEA drops into the core. In accordance with the Tech Spec COLR, a downpower must be completed within _______ minutes to a maximum power level of ______, to ensure ___________.

A. 60, 50%, the potential effect of CEA misalignment limited to acceptable levels.

B. 45, 60%, the potential effect of CEA misalignment limited to acceptable levels.

C. 60, 50%, values used in CPCs for azimuthal power tilt remain valid.

D. 45, 60%, values used in CPCs for azimuthal power tilt remain valid.

ANSWER B

COMMENTS Provide examinee with copy of COLR 3/4 1-18A Required power reduction after single CEA deviation A.

Incorrect time and power level B. Correct time, correct power level, correct basis C.

Incorrect time, power level and reason D.

Incorrect reason Cognitive Level: Comprehension/Analysis Tier/Group: 1/ 2 Question Source: New 10CFR Part 55 Content: 43. 2

Page 10 of 27 Examination Question Number 9

QUESTION ID:

6062 A

STATUS:

Revision LAST USED DESCRIPTION:

Ability to monitor RPI for a stuck/inoperable CEA AUTHOR:

avest REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

avest VERIFICATION DATE:

6/3/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

CED TS PPO CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

TS 3.1.3 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 4.2-A5-AA1.05 3.4 3.4 WLP-OPS-PPO10 05

Page 11 of 27 QUESTION The reactor is at 90% power. While performing OP-903-005, Control Element Assembly Operability Check, the following indications are noted while inserting CEA 41:

CEAC 1 PID 041 = 144.25

CEAC 2 PID 041 = 143.5

CEA 41 Pulse Counter indication = 148.5 All other CEA PIDs indicate 150.0 on CEAC 1 and CEAC 2 and Pulse Counter indication. Attempts to withdraw CEA 41 with I&C personnel monitoring CEA 41 at the CEDMCS panel results in the following indication:

CEAC 1 PID 041 = 144.25

CEAC 2 PID 041 = 143.5

CEA 41 Pulse Counter indication = 150.75

I&C reports CEA 41 ACTM card is malfunctioning Based on these indications, what actions are required?

A. Enter 3.1.3.1 action a only B. Enter 3.1.3.1 action a and 3.1.3.1 action d C. Enter 3.1.3.5 only D. Enter 3.1.3.5 and 3.1.3.1 action d ANSWER C

COMMENTS Supply a copy of OP-903-005 and TS 3.1.3.1 and TS 3.1.3.5 to examinee.

A is incorrect because there is no indication of being untrippable or having mechanical interference or excessive friction.

B is incorrect because there is no indication of being untrippable or having mechanical interference or excessive friction and CEA misalignment is < 7 inches.

C is correct because CEA 41 is a Shutdown Bank B CEA and is < 145 withdrawn.

D is incorrect because CEA misalignment is < 7 inches.

Cognitive Level: Comprehension/Analysis Tier/Group: 1/ 2 Question Source: New 10CFR Part 55 Content: 43. 6

Page 12 of 27 Examination Question Number 10 QUESTION ID:

6038 A

STATUS:

Revision LAST USED DESCRIPTION:

Verify Liquid release permit to preclude accidental liquid release AUTHOR:

evines REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

evines VERIFICATION DATE:

5/22/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

BM CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

CE-003-512 00 02 1/17/2000 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 4.2-A59-AA2.02 2.9 3.9 W-3-LP-OPS-BM00 08 QUESTION A liquid radioactive release of the Boric Acid Condensate Tank is to be performed.

Given the attached Liquid Radioactive Waste Release permit for your review, determine which of the following would give you grounds for not approving the release?

A. CWPs available are less than CWPs required.

B. Dilution Flow is less than minimum required.

C. Max waste flow exceeds maximum limit allowed by procedure.

D. Sample collected prior to minimum required recirculation time.

ANSWER D

COMMENTS Provide examinee with copy of Release permit with prerelease data filled in (part 1). Miscalculation for recirc time and sample collected prior to required recirc time ( not representative sample results)

A is incorrect, available CWPs available within requirements B is incorrect, dilution flow correct for 2 CWPs in operation C is incorrect, max waste flow within limits of procedure D is correct sample, should be taken 390 minutes after recirc started sample collected 300 minutes after recirc started.

Cognitive Level: Comprehension/Analysis Tier/Group: 1/ 2 Question Source: New 10CFR Part 55 Content: 43. 5

Page 13 of 27 Examination Question Number 11 QUESTION ID:

6040 A

STATUS:

Revision LAST USED DESCRIPTION:

Vital equipment to be maintained during a control room evacuation with fire AUTHOR:

evines REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

evines VERIFICATION DATE:

5/22/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

PPO CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

OP-901-502 08 00 4/30/2003 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 4.2-A67-AA2.16 3.3 4.0 W-3-LP-OPS-PPO51 05 QUESTION Given the following; EDG B is out service for preventive maintenance HPSI pump B is out service for preventive maintenance LPSI pump B is out service for preventive maintenance Charging pump AB is out service for seal water replacement A cable spreading room fire is in progress.

You have ordered a control room evacuation.

Which of the following components would you make the highest priority for returning to service?

A. HPSI pump B B. EDG B C. LPSI pump B D. Charging pump AB ANSWER B

COMMENTS OP-901-502 page 30 caution prior to step 1 A is incorrect because HPSI pump B is racked out in section E2 of OP-901-502 B is correct because you are procedurally required to have EDG B available to implement section E2 of OP-901-502.

C is incorrect because must hav e EDG B in operation to support LPSI pump B operation.

D is incorrect because Charging AB will not have power in section E2 Cognitive Level: Comprehension/Analysis Tier/Group: 1/ 2 Question Source: New 10CFR Part 55 Content: 43. 5

Page 14 of 27 Examination Question Number 12 QUESTION ID:

6034 A

STATUS:

Revision LAST USED DESCRIPTION:

Knowledge of SRO fuel handling responsibilities during control room evacuation AUTHOR:

evines REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

evines VERIFICATION DATE:

5/20/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

RF CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

RF-005-001 TS 3.9.5 08 00 12/6/2001 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 2-2-29 1.6 3.8 W-3-LP-OPS-REQ04 01 QUESTION Given the following:

You are the SRO in charge of fuel handling.

A core reload is in progress The phone talker informs you that the control room is being evacuated due to a fire in CP 8 and communications will be secured.

Currently a new fuel bundle is being moved from the Spent Fuel Pool to the core and is inserted two feet into its core location.

Which of the following is the appropriate action?

A. Secure all movement of the fuel bundle and suspend core alterations.

B. Seat the fuel bundle in the core location, ungrapple the fuel bundle and reestablish communications prior to continuing.

C. Return the fuel bundle to the Rx Bldg Upender and suspend core alterations.

D. Raise the fuel bundle into the fuel mast and de-energize the Refueling Machine, reestablish communications prior to continuing.

ANSWER C

COMMENTS A is incorrect because the fuel bundle must be placed in a safe location when suspending core alterations.

B is incorrect because it is not safe to continue insertion of a fuel assembly without monitoring core counts or having continuous communication established and it is required to suspend core alterations.

C is correct definitions in Tech Spec state that suspension of core alterations shall not preclude placing fuel in a safe conservative position prior to suspending core alterations.

D is incorrect because suspended from the refueling mast is not considered a safe location even if at up limit and it is required is to suspend core alterations Cognitive Level: Comprehension/Analysis Tier/Group: 1/ 2 Question Source: New 10CFR Part 55 Content: 43. 6

Page 15 of 27 Examination Question Number 13 QUESTION ID:

6041 A

STATUS:

Revision LAST USED DESCRIPTION:

Knowledge of ECCS design interlocks between RCS and RHR AUTHOR:

evines REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

evines VERIFICATION DATE:

5/22/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

SDC SI CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

TS 3.5.2 OP-903-025 04 00 4/14/2003 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 3.2-006-K4.16 3.2 3.5 WLP-OPS-SDC00 04 QUESTION During calibrations of the Narrow Range (0-750 psia) Pressurizer Pressure loops, the following as-found values were obtained for the pressure interlocks that affect the following valves:

SI-401 A, SDCS Loop 2 Inside Containment Upstream Isolation - 410 psia

SI-401 B, SDCS Loop 1 Inside Containment Upstream Isolation - 425 psia

SI-331 A, Safety Injection Tank 1A Isolation - 515 psia

SI-332 A, Safety Injection Tank 2A Isolation - 518 psia Which of the valves is inoperable?

A. SI-401 A B. SI-401 B C. SI-331 A D. SI-332 A ANSWER B

COMMENTS Provide examinee with copy of TS 3.5.1 and 3.5.2 A is incorrect acceptable pressure band is 392-422 psia B is correct acceptable pressure band is 392-422 psia C is incorrect acceptable pressure band is 505-525 psia D is incorrect acceptable pressure band is 505-525 psia Cognitive Level: Comprehension/Analysis Tier/Group: 2/ 1 Question Source: New 10CFR Part 55 Content: 43. 2

Page 16 of 27 Examination Question Number 14 QUESTION ID:

6042 A

STATUS:

Revision LAST USED DESCRIPTION:

Predict impacts and use procedures to mitigate loss of air for CCW AUTHOR:

evines REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

evines VERIFICATION DATE:

5/22/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

CVC PPO CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

OP-500-007 15 00 4/11/2003 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 3.8-008-A2.05 3.3*

3.5 WLP-OPS-PPO10 03 QUESTION Given the following conditions:

LETDOWN HX OUTLET TEMP HI (G-B1), annunciator in alarm.

Letdown heat exchanger Temperature control CC-636 has failed closed due to a broken instrument air line.

LD HX Tube Outlet Temperature CVC-ITI-0224, currently reads 200 ºF ?and steady.

All of the following actions are applicable for the conditions given EXCEPT:

A. Remove purification filter from service within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

B. Verify ion exchangers bypassed.

C. Dispatch NAO to slowly open CC-636 Letdown HX TCV.

D. Isolate charging and letdown.

ANSWER D

COMMENTS OP-005-007 B1 to be given to examinee A is incorrect purification filter must be removed from service within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if temp >180 B is incorrect Ion exchangers must be verified bypassed when temp > 140 C is incorrect NAO must locally open CC-636 D is correct Charging and letdown are not isolated until temp 230 Cognitive Level: Comprehension/Analysis Tier/Group: 2/ 1 Question Source: New 10CFR Part 55 Content: 43. 5

Page 17 of 27 Examination Question Number 15 QUESTION ID:

5811 A

STATUS:

Revision LAST USED DESCRIPTION:

Time remaining to initiate SDC AUTHOR:

avest REVISION 3

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

avest VERIFICATION DATE:

6/2/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

EFW PPE CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

OP-902-009 1.1 00 12/13/2002 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 3.4-061-A1.04 3.9 3.9 W-3-LP-OPS-PPE04 7

QUESTION A Main Steam Line Break has occurred. A cooldown is desired. The following conditions exist:

The reactor tripped one hour ago

Two RCPs are operating

Th is 450°F

Condensate Storage Pool level is 72.7%

DWST level is 45%

EFW is supplying the intact Steam Generator Evaluate Condensate inventory and determine the maximum time remaining to place Shutdown Cooling in service.

A. 8 hrs B. 11 hrs C. 15 hrs D. 22 hrs ANSWER C

COMMENTS Supply Attachments 2-D through 2-G of OP-902-009 A is incorrect 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months would correspond to 190,000 gals required calculated from 100 % T-hot using four pump curve.

B is incorrect 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months based on correct inventory required using 4 pumps operating curve.

C is correct 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months based on correct inventory required using correct 2 pumps operating curve.

D is incorrect 22 corresponds to correct inventory required using no pumps operating curve Cognitive Level: Comprehension/Analysis Tier/Group: 2/ 1 Question Source: Bank 10CFR Part 55 Content: 43. 5

Page 18 of 27 Examination Question Number 16 QUESTION ID:

6050 A

STATUS:

Revision LAST USED DESCRIPTION:

Knowlege of pre and post maintenance operability for AC electrical system EDG AUTHOR:

evines REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

evines VERIFICATION DATE:

5/28/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

4KV EDG ED CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

TS 3.8.1 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 2-2-21 2.3 3.5 W-3-LP-OPS-EDG00 07 QUESTION Given the following;

EDG A is being taken out of service for preplanned PMs to replace fuel oil and lube oil filters and replace lube oil.

A temporary EDG is aligned for backup of EDG A.

Which of the following is NOT required to be performed at any time during the EDG A outage?

A. OP-903-066, Electrical Breaker Alignment Check within one (1) hour of declaring EDG A inoperable.

B. A manual start of EDG B within eight (8) hours of declaring EDG A inoperable.

C. OP-903-068, Emergency Diesel Generator and Subgroup Relay Operability Verification.

D. Restore EDG A to operable status within 10 days of taking the diesel out of service.

ANSWER B

COMMENTS Provide copy of T.S. 3.8.1.1 to examinee.

A is incorrect OP-903-066 is required to be performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of taking EDG out of service and every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months afterward.

B is correct Manual start of EDG B is not required if outage is for preplanned maintenance.

C is incorrect OP-903-068 must be performed prior to restoring EDG A operability.

D is incorrect EDG A must be returned to service within 10 days.

Cognitive Level: Comprehension/Analysis Tier/Group: 2/ 1 Question Source: New 10CFR Part 55 Content: 43. 2

Page 19 of 27 Examination Question Number 17 QUESTION ID:

6051 A

STATUS:

Revision LAST USED DESCRIPTION:

Ability to use computer to evaluate parametric information on system status CET QSPDS AUTHOR:

evines REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

evines VERIFICATION DATE:

5/28/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

RCS CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

OP-001-003 19 05 3/20/2002 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 2-1-19 3.0 3.0 WLP-OPS-REQ13 07 QUESTION Given the following initial conditions:

The plant is in MODE 5 preparing for entry into MODE 6.

An RCS drain down is in progress to install nozzle dams in each steam generator.

PZR level is currently at 30% Cold Cal.

Jumpers have been installed on 1 CET for QSPDS 1 and 1 CET for QSPDS 2 to facilitate the drain down, all other CETs are currently disconnected.

The CRS notes that the dedicated CET from QSPDS 1 is no longer providing valid readings.

Which of the following would be required?

A. Stop the RCS drain down immediately and refill to = 75% Cold Cal PZR level and restore at least two CETs from either QSPDS before continuing.

B. Stop the RCS drain down before lowering RCS level < 5% Cold Cal PZR level and restore at least two CETs from either QSPDS before continuing.

C. Stop the RCS drain down prior to lowering RCS level < 18 ft MSL and restore 1 CET from QSPDS channel 1 before continuing.

D. Stop drain RCS down immediately and restore 1 CET from QSPDS channel 1 before continuing.

ANSWER C

COMMENTS Modified from question 5703A A is incorrect this is an initial condition prior to commencing drain down B is incorrect drain down must be secured prior to 18 ft MSL C is correct drain down must be secured prior to 18 ft MSL D is incorrect loss of CET does not require securing draindown prior to 18 ft MSL.

Cognitive Level: Comprehension/Analysis Tier/Group: 2/ 2 Question Source: Modified 10CFR Part 55 Content: 43. 5

Page 20 of 27 Examination Question Number 18 QUESTION ID:

6052 A

STATUS:

Revision LAST USED DESCRIPTION:

Ability to predict impacts and use procedures to mitigate consequences of fire protection malfunctions AUTHOR:

evines REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

evines VERIFICATION DATE:

5/28/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

ANP FPD CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

TRM 3.3.3 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 3.8-086-A2.03 2.7 2.9 W-3-LP-OPS-FP00 06 QUESTION ANP 102 goes closed due to Safety Injection actuation relay circuit failure, causing Annulus Negative Pressure (ANP) fans to secure.

Which of the following describe the compensatory measures required to be implemented.

A. Establish a fire watch within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

B. Return a ANP fan to service within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months C. After 14 days establish a fire watch within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

D. Verify annulus temperature less than 120°F once per hour.

ANSWER A

COMMENTS TRM 3.3.3.8.1 A is correct fire watch must be established within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if Annulus negative pressure system not in operation.

B is incorrect fire watch must be established within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if Annulus negative pressure system not in operation.

C is incorrect fire watch must be established within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if Annulus negative pressure system not in operation.

D is incorrect fire watch must be established within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if Annulus negative pressure system not in operation.

Cognitive Level: Memory Tier/Group: 2/ 2 Question Source: New 10CFR Part 55 Content: 43. 5

Page 21 of 27 Examination Question Number 19 QUESTION ID:

4581 A

STATUS:

Revision LAST USED DESCRIPTION:

Minimum Shift Composition AUTHOR:

avest REVISION 3

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

1/14/1998 REFERENCE VERIFIED:

avest VERIFICATION DATE:

6/19/2003 TYPE:

Multiple Choice TIME:

3 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

OPEN REFERENCE X

SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

PPA CATEGORY:

ORAL BOARD SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

OP-100-001 19 00 6/12/2003 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 2-1-4 2.3 3.4 w-3-lp-ops-ppa00 2

QUESTION The plant is operating at 100% power. The Shift Manager on shift plans to observe the TB Watchstander perform a task in the plant.

What minimum requirement has to be met prior to the Shift Manager leaving the Control Room for the observation?

A. Assign the STA (on shift) the Control Room Command function.

B. Assign an SRO (other than the STA) the Control Room Command function.

C. Log his beeper number and expected location in the Station Log.

D. Perform a shift turnover to another qualified Shift Manager.

ANSWER B

COMMENTS.2 of OP 100-001 lists requirement.

A is incorrect during Shift Manager absence from the control room another SRO (other than the STA) must be designated for control room command and control function.

B is correct during Shift Manager absence from the control room another SRO (other than the STA) must be designated for control room command and control function.

C is incorrect during Shift Manager absence from the control room another SRO (other than the STA) must be designated for control room command and control function.

D is incorrect during Shift Manager absence from the control room another SRO (other than the STA) must be designated for control room command and control function.

Cognitive Level: Memory Tier/Group: 3 Question Source: Bank 10CFR Part 55 Content: 43.2

Page 22 of 27 Examination Question Number 20 QUESTION ID:

4202 D

STATUS:

Revision LAST USED DESCRIPTION:

Ultimate Heat Sink Tech Spec AUTHOR:

avest REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

avest VERIFICATION DATE:

6/13/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

CC TS CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

TS 3.7.4 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 2-1-33 3.4 4.0 W-3-LP-OPS-CC00 10 QUESTION The plant is operating at 100% power with Dry Cooling Tower Fans 2B, 6B, 7B, and 15A out of service. The control room is monitoring dry bulb temperatures every two hours.

The last set of readings were taken 5 minutes ago and indicate as follows:

Dry Bulb Temperature = 84.3°F You are informed via the Civil Defense Radio that National Weather has issued a Severe Thunderstorm Warning and a Tornado Watch for Tangipahoa, St. Tammany, Jefferson, Orleans, St. Charles and St. John parishes. Assuming no other equipment is out of service, which of the following describes the required actions to be taken?

A. Enter TS LCO 3.7.4 Action a and perform actions within the required time frames.

B. Enter TS LCO 3.7.4 Action b and perform actions within the required time frames.

C. Enter TS LCO 3.7.4 Action c and perform actions within the required time frames.

D. Remain in TS LCO 3.7.4 Action d and continue actions within the required time frames.

ANSWER C

COMMENTS Provide TS 3.7.4 to and SD-CC Figure 4 to examinee This question was modified from 4202B A and B are incorrect because Action 3.7.4.c covers the prescribed condition.

C is correct. The number of fans OOS were within requirements until the Tornado watch was issued. At that point 3.7.4.c should be entered because Fans 7B and 15A are under the missile shield and are required to be operable with a Tornado Watch in effect.

D is incorrect because a Tornado Watch is in effect.

Cognitive Level: Comprehension/Analysis Tier/Group: 3 Question Source: Modified 10CFR Part 55 Content: 43. 2

Page 23 of 27 Examination Question Number 21 QUESTION ID:

6065 A

STATUS:

Revision LAST USED DESCRIPTION:

Knowledge of process for managing maintenance activities during shutdown AUTHOR:

avest REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

avest VERIFICATION DATE:

6/3/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

RF TS CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

RF-004-001 10 00 12/17/2002 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 2-2-18 2.3 3.6 W-3-LP-OPS-REQ04 WLP-OPS-TS04 06 02 QUESTION The plant is in Mode 6 preparing to commence core alterations. Core alterations are scheduled to start on 8/22/03 at 1400. Refueling activities are currently on schedule. TS Boration flowpath is BAM Tank A and gravity feed valves via Charging Pump A. The following surveillances were last performed at the following times:

OP-903-002, Boration Flowpath Valve Lineup Verification - 1800, 7/23/03

OP-903-003, Charging Pump Operability Check, Charging Pump A - 1400, 5/10/03

OP-903-101, Startup Channel Functional Test, Startup Channel 1 - 0500, 8/22/03

OP-903-101, Startup Channel Functional Test, Startup Channel 2 - 0700, 8/22/03 Which surveillance must be performed prior to commencing core alterations, if refueling activities remain on schedule?

A. OP-903-002 B. OP-903-003 C. OP-903-101, Channel 1 D. OP-903-101, Channel 2 ANSWER C

COMMENTS Provide pages 1 and 2 of RF-004-001, Attachment 9.5 to examinee A is incorrect because it is within the 31 day periodicity.

B is incorrect because it is within 1.25 (115 days) of the 92 day (Quarterly) periodicity.

C is correct because it is not within the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months time frame for starting core alterations and the 1.25 does not apply.

D is incorrect because it meets the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Cognitive Level: Comprehension/Analysis Tier/Group: 3 Question Source: New 10CFR Part 55 Content: 43. 2

Page 24 of 27 Examination Question Number 22 QUESTION ID:

6055 A

STATUS:

Revision LAST USED DESCRIPTION:

Knowledge of new and spent fuel movement procedures AUTHOR:

avest REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

avest VERIFICATION DATE:

6/19/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

RF CATEGORY:

ADMIN PROCEDURE

REFERENCE:

REVISION:

CHANGE:

DATE:

OP-100-001 RF-001-001 19 10 00 00 6/12/2003 3/27/1903 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 2-2-28 2.6 3.5 W-3-LP-OPS-REQ04 W-3-LP-OPS-RFUEL 03 09 QUESTION Which of the following personnel are authorized to suspend core alterations?

A. Shift Manager and Refueling Director B. Refueling Director and Refueling Controller C. Refueling Controller and Fuel Handling Supervisor D. Fuel Handling Supervisor and Shift Manager ANSWER D

COMMENTS This question is the same as question 5552A in the Operations bank.

A is incorrect because the Refueling Director is not authorized unless he happens to be an SRO filling the Fuel Handling Supervisor position.

B is incorrect because the Refueling Director and Refueling Controller are not authorized, unless they happen to be an SRO filling the Fuel Handling Supervisor position.

C is incorrect because the Refueling Controller is not authorized unless he happens to be an SRO filling the Fuel Handling Supervisor position.

D is correct per RF-005-001 and OP-100-001.

Cognitive Level: Memory Tier/Group: 3 Question Source: Bank 10CFR Part 55 Content: 43. 7

Page 25 of 27 Examination Question Number 23 QUESTION ID:

448 B

STATUS:

Revision LAST USED DESCRIPTION:

Emergency exposure limits per EP-002-030 AUTHOR:

avest REVISION 2

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

avest VERIFICATION DATE:

6/13/2003 TYPE:

Multiple Choice TIME:

2 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

OPEN REFERENCE X

SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

EP RAD CATEGORY:

PROCEDURE

REFERENCE:

REVISION:

CHANGE:

DATE:

EP-002-030 09 00 4/8/2003 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 2-3-4 2.5 3.1 W-3-LP-EP-SS 55 QUESTION Given the following:

A Large Break LOCA has occurred

HPSI Pump A has developed a 40 gpm leak on the pump suction

Attempts to isolate HPSI Pump A from the Safeguards Valve Gallery failed due to a broken reach rod on the suction isolation valve

All ESF Pumps are taking a suction from the SI Sump

An Emergency Team member has volunteered to enter Safeguards Pump Room A to close HPSI Pump A suction valve locally The maximum allowed TEDE exposure that the Emergency Coordinator can authorize the Emergency Team member to receive while performing this evolution is:

A.

10 REM B.

25 REM C.

75 REM D.

100 REM ANSWER A

COMMENTS A is correct per EP-002-030, 10 REM is limit (TEDE) for corrective actions for accident mitigation B is incorrect because 25 REM is limit (TEDE) for lifesaving measures per EP-002-030 C is incorrect because the limit is 10 REM per EP-002-030; however 75 REM was the previous limit for corrective action limit for accident mitigation.

D is incorrect because the limit is 10 REM per EP-002-030; however 100 REM was the previous limit for lifesaving measures.

Cognitive Level: Comprehension/Analysis Tier/Group: 3 Question Source: Bank 10CFR Part 55 Content: 43. 4

Page 26 of 27 Examination Question Number 24 QUESTION ID:

5739 A

STATUS:

Revision LAST USED DESCRIPTION:

Ability to take actions in the facility Emergency Plan (Toxic Chemical Emergency)

AUTHOR:

avest REVISION 1

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

avest VERIFICATION DATE:

5/29/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

X OPEN REFERENCE SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

EP CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

EP-004-010 09 00 4/10/2003 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 2-4-38 2.2 4.0 W-3-LP-OPS-PPO50 WLP-OPS-EP02 03 26 QUESTION Given the following conditions:

A pipe that carried Vinyl Chloride failed at Dow Chemical

The leak has not been isolated

Failure time was 09:50

Current time is 09:56

The plume travel time is 25 minutes, based on current wind speed

Wind direction is from 135° What emergency classification should you declare and which Tab of EP-004-010 should be implemented?

A. Declare an Unusual Event and implement Tab A, Standby B. Declare an Alert and implement Tab B, Site Evacuation C. Declare an Alert and implement Tab C, Shelter D. Declare a Site Area Emergency and implement Tab C, Shelter ANSWER C

COMMENTS This question is modified from question 5739N.

A is incorrect because chemicals are not within the EAB and Vinyl Chloride is a large hazard.

B is incorrect because response time is less than 45 minutes.

C is correct because chemicals are within the EAB, W3 is less than 5 miles from Dow Chemical, Vinyl Chloride is a large hazard, the release is not secured, W3 is downwind of the release, and response time is less than 45 minutes.

D is incorrect because personnel have not been sheltered for greater than 30 minutes.

Cognitive Level: Comprehension/Analysis Tier/Group: 3 Question Source: Modified 10CFR Part 55 Content: 43. 5

Page 27 of 27 Examination Question Number 25 QUESTION ID:

5684 N

STATUS:

Revision LAST USED DESCRIPTION:

Prioritization of Safety Functions in OP-902-008 AUTHOR:

avest REVISION 2

REVISION DATE 6/26/2003 APPROVAL:

APPROVAL DATE:

REFERENCE VERIFIED:

avest VERIFICATION DATE:

6/2/2003 TYPE:

Multiple Choice TIME:

5 POINTS:

1 QUIZ ONLY:

CLOSED

REFERENCE:

OPEN REFERENCE X

SPECIAL

REFERENCES:

SIMULATOR SETUP PLANT SYSTEM:

PPE CATEGORY:

PROCEDURE SRO LEVEL

REFERENCE:

REVISION:

CHANGE:

DATE:

OP-902-008 12 00 4/12/2001 NRC KA NUMBER:

RO SRO TRAINING MATERIAL:

OBJECTIVE 2-4-21 3.7 4.3 W-3-LP-OPS-PPE08 6

QUESTION OP-902-008, Safety Function Recovery Procedure has been implemented. Refer to the attached Safety Function Tracking Sheet and determine the priority for addressing the safety functions.

A. 1, 2, 3, 4, 5, 6, 7, 8, 9 B. 1, 7, 5, 2, 8, 3, 4, 6, 9 C. 1, 7, 2, 3, 8, 4, 5, 6, 9 D. 1, 5, 6, 2, 7, 3, 4, 8, 9 ANSWER B

COMMENTS Check (a) the following on the Safety Function Tracking Sheet:

Success Path in Use - RC-3, MVA-DC-1, MVA-AC-2, IC-2, PC-1, HR-2, CI-1, CPTC-2, CCGC-1 SFSC Met - MVA-DC-1, MVA-AC-2, PC-1, CPTC-2, CCGC-1 A is incorrect because this group of numbers just follows the order in which the safety functions are laid out in the procedure with no regard to their status.

B is correct because it follows the methodology laid out in section E0 of OP-902-008.

C is incorrect MVA-AC-2 is prioritized higher than some safety functions not meeting any Safety Function Status Checklist criteria.

D is incorrect because this order would result from overlooking the fact that MVA-AC and CTPC do not meet success path 1 criteria.

Cognitive Level: Comprehension/Analysis Tier/Group: 3 Question Source: Bank 10CFR Part 55 Content: 43. 5

ML032690973

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