ML033210410

Final RO & SRO Written

ML033210410
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	10/03/2003
From:	Gosekamp M Entergy Nuclear Vermont Yankee
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-271/03-301
Download: ML033210410 (151)

Text

MASTER EXAMINATION AND ANSWER KEY LICENSED OPERATOR INITIAL TRAINING PROGRAM Course: RO / SRO NRC Exam 2003 Exam Activity Code:

Date Exam Prepared: 19 September 2003 Date Exam Taken: 3 October 2003 Form TDD-5.2.2 Rev. 8,09/00

Facility:

Vermont Yankee Date of Examination:

10/3/03 Examination Level (circle one):

/ SRO Operating Test Number:

1 Administrative Topic I(

&xcq&w+

(see Note)

&I Conduct of Operations A 2 Conduct of Operations A73 Equipment Control M

Emergency Plan Describe activity to be performed 4 n Isolate leaking RHR piping weld leak (New)

Generic 2.1 2 4 Ability to obtain and interpret station electrical and mechanical drawings.

(CFR: 45.1 2 / 45.1 3)

IMPORTANCE RO 2.8 Preparation of Control Room Shift Turnover Checklist, HPCl flow control setpoint tape not properly set (New)

Generic 2.1.3 Knowledge of shift turnover practices.

(CFR: 41.10/45.13)

IMPORTANCE RO 3.0 Perform Secondary Containment Capability Test (New)

Generic 2.2.12 Knowledge of surveillance procedures (CFR41.10/45.13)

Importance RO 3.0 Control Room Emergency Communications Check (New)

Generic 2.4.43 Knowledge of emergency communication systems and techniques (CFR: 45.13)

Importance RO 2.8 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

Date of Examination:

10/3/03 Operating Test Number:

1 Administrative Topic -

(see Note)

M Conduct of Operations Describe activity to be performed e

~~

Take actions for inadequate shift staffing (new)

Generic 2.1.5 Ability to locate and use procedures and directives related to shift staffing and activities.

(CFR: 41.10/43.5/45.12)

IMPORTANCE SRO 3.4 Conduct of Operations Isolate leaking RHR piping leak and determine Technical Specification impact (new)

Generic 2.1 2 4 Ability to obtain and interpret station electrical and mechanical drawings.

(CFR: 45.12 / 45.13)

IMPORTANCE SRO 3.1 A 2 Equipment Control Determine if equipment can be removed from service for minor unscheduled maintenance (new)

Generic 2.2.17 Knowledge of the process for managing maintenance activities during power operations.

(CFR: 43.5 / 45.13)

IMPORTANCE SRO 3.5 A 4 Radiation Control Review and approve Emergency plan allowed radiation exposure Generic 2.3.4 Knowledge of radiation exposure limits and contamination control 1 including permissible levels in excess of those authorized.

(CFR: 43.4 / 45. IO)

IMPORTANCE SRO 3.1 (new) fk4 Emergency Plan 1 Determine protective action recommendation (bank)

Generic 2.4.29 Knowledge of the emergency plan.

(CFR: 43.5 / 45.1 1)

IMPORTANCE SRO 4.0 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

Facility: Vermont Yankee Exam Level (circle one):

/ SRO(1) / SRO(U)

Type Code*

System / JPM Title Date of Examination:

10/3/03 ODeratina Test No.:

1 Safety Function

h. Swap SJAE Suction Valves (516) (27106)

D, s 9

a. Perfotm Weekly Operable Control Rod Check (Stuck Rod)

(20107F) w D, R D

1 1

8

b. Parallel Main Generator to Grid (24507)

/I

c. RPV venting via the MSlVs (20043)

d. Bypass Reactor Building HVAC Trips (20041)

~~

e. Transfer MCC 89A from the Maintenance Tie to RUPS (26209)

Ilf. Core Spray Pump Surveillance (20901 F)

g. Initiate Manual Scram (OE 3107 Appendix F) (20023F)

I

i. Place Standby CRD FCV in Service (Loss of CRD Regulating Function) (201 06)

j. Respond to High Service Water Strainer D/P (27601)

k. Startup RPS Motor Generator (21202F)

I 7

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA

SRO NRC Exam 2003 Ouestion No. 1 Exam Bank Question No.: 5614 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-202 Objective: CRO 3j Question Level: Analysis Select the correct answer:

While operating at full power, you observe the following parameter changes:

MWe net 520 to 472 Turbine Control valves step change in the close direction Reactor Pressure 1010 to 998 psig Core Plate D/P 16 to 14 psid Core Flow 47 mlbs/hr to 48 mlbs/hr Based on these indications, your action should be to enter the procedure for:

a.

b.

d.

AnswedDistractor Inadvertent opening of an SRV.

Inadvertant opening of a bypass valve.

Jet pump failure.

Reactor low pressure from EPR failure.

References:

LOT-00-601 CRO Obj. 1,3 Justification Incorrect - Increasing flow and decreasing power can only be caused by a jet pump failure.

Incorrect - Ibypass valve opening would cause a reactor ower increase due to a reduction in feedwater temperature which would cause an increase in reactor pressure.

Correct Response - These indications are scaled data from the Quad Cities jet pump failure that occurred in 2002. These parameters closely match ON 3 14 1 symptoms, but not identical. On 3141 requires the J.P. Surveillance be Derformed.

Incorrect - Increasing flow and decreasing power can only be caused by a jet pump failure.

ON 3141, rev 8 Quad Cities J.P. Failure 2002 New

Task Associations Task Number Task Title 2000090501 Respond to Jet Pump Failure Knowledge and Abilities Associations Y

apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:(CFR 41.10,43.5,45.13):

Jet pump operability: Not-BWR-1 &2 Static Simulator Exams: None Last Revised: 09/16/2003 7:51:38 AM by Brown, Scott T.

SRO NRC Exam 2003 Question No. 2 Exam Bank Question No.: 5615 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-262 Objective: CRO 6 Question Level: Analysis Select the correct answer:

Off-site power has been lost (LNP) and a large break LOCA has occurred. The "A" EDG failed to start. Reactor pressure is 50 psig and lowering. Reactor level is off scale low.

What are your required actions:

AnswerDistractor Enter EOP 1 and 3 and confirm HPCI, RCIC, 2 RHR pumps, 1 CS pump iniectinn.

Enter EOP 1 and 4 and confirm 4 RHR pumps, 2 CS pumps injecting.

Enter EOP 1 and 3 and confirm 2 RHR pumps, 1 CS pump injecting.

Enter EOP 1 and 4 and confirm 1 RHR pump, 1 CS pump injecting.

References:

EOP-1, rev 2 OT 3122, rev 19 New Incorrect - HPCI and RCIC have isolated on low steam supply pressure and can not inject.

Incorrect - The "A" EDG start failure causes a loss of 4 KV Bus 4, and 3 of 6 low pressure ECCS pumps are without power.

Correct Response - The "B" EDG starts and powers 4 KV Bus 3. Two RHR and 1 CS pump are powered fiom this bus.

HPCI and RCIC have isolated on low steam supply pressure.EOP 1 is entered on low reactor water level and EOP 3 is entered on high drywell pressure Incorrect - There is one RHR pump in each RHR loop powered fiom each EDG, 2 RHR pumps will be running and injecting.

There are no entry conditions for EOP 4 Must integrate: Bus 4 is deenergized, all ECCS and RCIC have start signals, HPCI & RCIC have isolated on low steam supply pressure. Both RHR and one core spray injection valves have power available.

Task Associations

20003 10501 Respond to Low Reactor Water Level 295003 Knowledge and Abilities Associations 2.4.01 Knowledge of EOP entry conditions and immediate action 4.3 4.6 steps (CFR 41.10,43.5,45.13)

Static Simulator Exams: None Last Revised: 09/16/2003 8:Ol:Ol AM by Brown, Scott T.

SRO NRC Exam 2003

d.

Question No. 3 Exam Bank Question No.: 5616 Revision: 3 SRO Only: No Instructor Guide: LOT-00-601 Objective: CRO 2,3,4 Question Level: Comprehension Point Value: 1 Select the correct answer:

None will trip.

A reactor startup is in progress. Plant electrical loads are still on the startup transformers.

Breaker #13 on 125 VDC Bus 1 has tripped causing a loss of control power to 4 KV Bus 1. A reactor scram occurs and after the initial shrink RPV level is 177" and rising. Reactor Feed Pumps A & C are running.

Reactor Feed Pump breakers will respond as follows:

1 I Answer/Distractor I a. I A & C will trip.

Justification I

Incorrect - A has no control power and will not trip.

Correct Response - High level trip logic is powered from DC-1 C/DC-2C and is functional. A Reactor Feed Pump is powered from 4 KV Bus 1 and there is no control power. High RPV trip logic can not trip the A RFP breaker. C RFP breaker control power is available and will trip C RFP on high RPV level.

Incorrect - A has no control power and will not trip.

Incorrect - C has control power and will trip.

References:

ON 3 159, rev 4, page 4 note, third bullet New Must integrate: 173" high level trip will be reached. A RFP is powered from 4 KV Bus 1 and with no control power available can not be tripped by the high RPV level signal.

Task Associations

~~

~

Task Number Task Title 2000320501 Respond to a Loss of DC-1,2,3 Knowledge and Abilities Associations 1 System YUA NO. I statement

]RO ISROl

295004 AA1.03 I Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C.

POWER: (CFR 41.7,45.6): A.C. electrical distribution 3.4 3.6

SRO NRC Exam 2003 Question No. 4 Exam Bank Question No.: 5617 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-249 Objective: CRO 8 Question Level: Comprehension Select the correct answer:

345 KV Breaker 81-1T is open and white tagged for maintenance during fbll power operation. A large air leak occurs on 345 KV Breaker 1T and it trips open on low air pressure.

The Reactor Protection System (RPS) will:

AnswerDistractor not initiate a scram.

initiate a scram on control valve fast closure.

initiate a scram on stop valve closure.

initiate a scram on stop valve closure and control valve fast closure.

Justification Incorrect - A scram will occur above 30%

reactorhrbine power and a load reject.

Correct Response - With 81-1T open and 1T then tripping, a complete load reject occurs. The acceleration relay actuates to control turbine speed and sends a scram signal to RPS. The scram is armed when oDeratinrr above 30% Dower.

Incorrect - The turbine stop valves will be open, the control valves will shut rapidly to control turbine speed, a reactor scram will occur, turbine first stage pressure will decrease to < 30% load and bypass the stop valve closure scram and 30 seconds later low scram air header pressure will trip the turbine, shutting the stop valves.

Incorrect - The stop valve closure scram will be bypassed before the stop valves are trimed shut.

References:

LOT-00-212 Obj. CRO 3 ON 3154 rev 10 New Task Associations 2007300501 Knowledge and Abilities Associations Respond to Generator Load Reject

System 295005 I

I I MAIN TURBINE TRIP: (CFR 41.7.45.8): RPS I

I I

K/A No. Statement RO SRO AK2.01 Knowledge of the interrelations between and the following 3.8 3.9 Static Simulator Exams: None Last Revised: 07/25/2003 9:24:56 AM by Hallonquist, Nora E.

SRO NRC Exam 2003 14%, safety and relief valves Ouestion No. 5 Exam Bank Question No.: 561 8 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-129 Objective: 31 Question Level: Fundamental KnowledgelMemory Select the correct answer:

Incorrect - Decay heat value is too high.

SRV lift setuoint will not be reached.

The reactor has been operating at 100% power for 300 days. An I&C Technician causes a full reactor scram during testing due to a human performance error. (Scram discharge instrument volume high)

b.

c.

Fission product decay heat after the prompt drop will equal approximately

% core thermal power and will be removed by the 14%, bypass valves 7%, safety and relief valves Incorrect - Decay heat value is too high.

Incorrect - SRV lift setpoints will not be I

I Answer/Distractor I Justification EPR is in service and will control reactor pressure disapating the decay heat at a

References:

EOP-1, rev 2 OT 3 100, rev 7 New Task Associations 2000330501 Respond to a Reactor SCRAM I 295006 I AK1.01 I Knowledge of the operational implications of the 13.7 13.9 I following-concepts as they applyto SCRAM: (CFR 41.8 to 4 1.10): Decay heat generation and removal Static Simulator Exams: None

Last Revised: 07/31/2003 10:08:31 AM by Hallonquist, Nora E.

SRO NRC Exam 2003 Question No. 6 Exam Bank Question No.: 5619 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-612 Objective: A2, A4 Question Level: Analysis Select the correct answer:

The Control Room has been abandoned.

RCIC is in operation from the alternate shutdown panel due to a large fire in the cable vault.

As torus pressure rises, RCIC:

Will trip on high exhaust pressure.

Operation remains unaffected by backpressure.

Operation is affected and when it is SRV 71A & B should be opened and RPV level restored with RHR.

Operation is affected and when it is SRV 71A & B should be opened and RPV level restored with core sm-av.

Justification Incorrect - High back pressure (exhaust) is bypassed when operating from the alternate shutdown panel.

Incorrect -RCIC operation is negatively affected by high torus pressure and will not provide adequate feed to the FWV at high backpressures.

Correct Response - OP 2126 Incorrect - Core Spray can not be operated at the alternate shutdown panels.

References:

OP 3 126 rev 16, Appendix C, page 5 caution, Appendix A, page 3 of 7 New Task Associations Task Number Task Title 2007170501 Perform Shutdown from Outside the Control Room Knowledge and Abilities Associations Static Simulator Exams: None Last Revised: 09/18/2003 5:22:27 PM by Brown, Scott T.

SRO NRC Exam 2003 Ouestion No. 7 Exam Bank Question No.: 5620 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-603 Objective: CRO 3g Question Level: Comprehension Select the correct answer:

The running RBCCW pump has tripped and the standby pump can not be started. If no operator action is taken, which of the following components will be damaged?

140°F, no resin damage occurs at this be damaged and the recirc pumps are required to be shutdown 2 minutes after RBCCW is lost. CRD pump bearings and reduction gear are cooled by RBCCW and must be manually shutdown to prevent

References:

ON 3 147 rev 10 New Task Associations 20001 10501 Respond to RBCCW Failure PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: (CFR 41.7,45.8): System loads Static Simulator Exams: None Last Revised: 07/25/2003 9:32:53 AM by Hallonquist, Nora E.

SRO NRC Exam 2003 Lead compressors running and SA-PCV-1 open.

Lag compressors running and SA-PCV-1 open.

Lead compressors running and SA-PCV-1 shut.

Ouestion No. 8 Exam Bank Question No.: 5621 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-279 Objective: CRO le, 5 Question Level: Comprehension Select the correct answer:

1 to fully shut.

Incorrect - The procedure assumes lead compressors running and does not require them checked.

Incorrect -

Incorrect -

While operating at full power, the following annunciators are received:

CRP 6-D-1 Inst Air Receiver HDR Press LO CRP 5-C-8 Scram Pilot Air Hdr Press Hi/Lo CRP 5-E-2 FW VLV Lockup SignaVAir Fail Instrument air header pressure is continuing to lower. Procedurally you are required to confirm:

AnswerDi stractor I'Justification Lag compressors running and SA-PCV-1 shut.

Correct Response - Low scram air alarm 60 psig, low instrument air 90 psig, lag compressors start at 95 psig, SA-PCV-1 starts shut at 85 psig in the instrument air header and is full shut at 80 psig. The continuing lower pressure causes SA-PCV-

References:

ON 3 146, rev 15 ARS-5-C-8, rev 4 ARS-6-D-1, rev 3 New Must integrate Alarm Set Points, c procedure steps.

mpress rs control logic and PCV-1 operation, and required Task Associations 2000130501 Respond to a Loss of Instrument Air Pressure

apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: (CFR 41.7,45.6): Service air isolations valves: Plant-SDecific Static Simulator Exams: None Last Revised: 09/16/2003 8: 1450 AM by Brown, Scott T.

SRO NRC Exam 2003 Question No. 9 Exam Bank Question No.: 5622 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-601 Objective: CRO 3,4 Question Level: Comprehension Select the correct answer:

Shutdown cooling is operating and reactor pressure is 100 psig, cooling down for a scheduled outage. RHR 18 MOV (shut down cooling suction) shorts out and strokes the valve shut. The RHR pump trips and the valve can not be opened by any means. RWCU was secured for startup of shutdown cooling.

ON 3 156, Loss of Shutdown Cooling, requires reactor level be restored to > 185". The reason for this step is to:

Answer/Distractor reduce natural circulation providing more accurate reactor coolant temperature monitoring via bottom head drain temperature.

promote natural circulation providing more accurate reactor coolant temperature monitoring via bottom head drain temDerature.

reduce natural circulation providing more accurate reactor coolant temperature monitoring via skin temperatures.

promote natural circulation providing more accurate reactor coolant temperature monitoring via skin temperatures.

Justification Incorrect - Bottom head drain temperature is not required to be monitored during a Loss of Shutdown Cooling. Reducing natural circulation is caused by lowering RPV level, not raising it, Incorrect - Bottom head drain temperature is not required to be monitored during a Loss of Shutdown Cooling.

Incorrect - Reducing natural circulation is caused by lowering RPV level, not by raising it.

Correct Response - Must recall ON 3 156 references SIL-357 and raises RPV level to promote natural circulation by placing a water seal on the dryer skirt.

Must recall that skin temperatures are required to be monitored during a Loss of Shutdown Cooling. Must integrate the two variables.

References:

ON 3 156, rev6, page 7 note, and step 96 New Task Associations Task Number Task Title

2000150501 Respond to a Loss of Shutdown Cooling following concepts as they applyto LOSS OF SHUTDOWN COOLING: (CFR 41.8 to 41.10): Natural circulation Static Simulator Exams: None Last Revised: 07/25/2003 9:35:20 AM by Hallonquist, Nora E.

SRO NRC Exam 2003 Question No. 10 Exam Bank Question No.: 5623 Revision: 5 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-620 Objective: 3 Question Level: Fundamental KnowledgeMemory Select the correct answer:

Refueling operations are in progress. An exposed bundle is full up, when the fuel grapple cable breaks and the bundle is dropped onto the core. 125 fuel pins are ruptured.

What response(s), if any, are you expected to confirm in the control room?

I AnswerDistractor I Justification

References:

Tech Spec, Bases 2 1 1, page 78 UFSAR, rev 18, Ch 14.6.4.4 New Task Associations 2737060101 Respond to Automatic Actions from Local Monitors Know1edg.e and Abilities Associations REFUELING ACCIDENTS: (CFR 41.7,45.8): Radiation-monitoring equipment Static Simulator Exams: None Last Revised: 09/18/2003 6:20:32 PM by Brown, Scott T.

SRO NRC Exam 2003 Question No. 11 Exam Bank Question No.: 5624 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-205 Objective: CRO 2 Question Level: Comprehension Select the correct answer:

Given the following sequence of events:

0800 "A" Loop of RHR is started in torus cooling 08 10 Reactor coolant leak in the drywell occurs 0820 Drywell pressure is 2.5 psig and rising 0830 Reactor water level is 127" and lowering 0840 Reactor water level is 82.5" and lowering 0850 Reactor pressure is 350 psig and lowering Under these conditions, which of the foolowing times is the earliest time that the torus cooling (RHR 39N34A) valves would close at:

b. 0830

c. 0840

d. 0850 Correct Response - The high drywell signal alone will close all non-LPCI iniection Daths Incorrect - If the operator does not know his low verses low low level setpoints this is a valid distractor.

Incorrect - If the operator is not aware that low low level and low reactor pressure are required this is a valid distractor.

Incorrect - This is a close signal to RHR 34N39A, but they were already closed at 0820.

References:

OP 2124, rev 50, page 5 Pilgrim 2003 NRC New Task Associations 2000070501 Knowledge and Abilities Associations Respond to Containment Hi Pressure

SRO NRC Exam 2003

d.

Question No. 12 Exam Bank Question No.: 5625 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-302 Objective: CRO 3 Question Level: Fundamental KnowledgeMemory Select the correct answer:

950 psig, normal During a reactor startup in accordance with OP-0105, reactor pressure must be maintained below switches are in to prevent a high reactor pressure scram until low condenser vacuum isolation bypass I Answer/Distractor I a. I 850 psig, bypass

References:

OP 0150, rev 10, page 40 Pilgrim 2003 NRC New Justification Incorrect - Low vacuum bypass must be in normal before exceeding 850 psig.

Incorrect - 850 psig can not be exceeded with the low vacuum isolation bypassed, procedure requires pressure > 750 and

<850 psig to return it to service.

Correct Response - For startup vac trip 1 &

2 are tripped to ensure Tech Spec compliance. Reactor heatup is begun without pressure control. The low vacuum isolation bypass must be returned to service to allow bypass valves to control pressure. If the stepskaution are not followed a high reactor pressure scram will occur.

Incorrect - 850 psig can not be exceeded with the low vacuum isolation bypassed, procedure requires pressure > 750 and 4 5 0 psig to return it to service..

Task Associations

Ability to explain and apply system limits and precautions (CFR 41.10,43.2,45.12)

Static Simulator Exams: None Last Revised: 09/16/2003 8:23:39 AM by Brown, Scott T.

3.4 3.8

SRO NRC Exam 2003 Question No. 13 Exam Bank Question No.: 5626 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-607 Objective: CRO 2 Question Level: Comprehension Select the correct answer:

Given the following conditions:

Reactor Level is 70" and steady Drywell and Torus pressure are 5.0 psig and lowering Dyrwell temperature is 240°F and lowering The "A" Loop of RHR is operating in drywell spray, torus sprays, and torus cooling When torus pressure is 2.5 psig you should confirm isolation of:

a. I Drvwell SDravs onlv.

b. I Torus Spravs onlv.

Drywell and Torus Sprays.

d. Drywell and Torus Sprays and Torus cooling.

Justification Incorrect -

Incorrect -

Correct Response - With an accident signal present, drywell and torus sprays automatically isolate when drywell pressure is less than or equal to 2.5 psig.

With a vacuum breaker failed open, torus and drywell pressure are equal.

Incorrect - Torus cooling does not isolate when drywell pressure goes below 2.5 psig.

References:

EOP-3, rev 3 EOP-3 is a required reference Pilgrim 2003 NRC Modified Task Associations 2000210501 Respond to High Drywell Temperature Knowledge and Abilities Associations

I Plant-specific Static Simulator Exams: None Last Revised: 09/16/2003 8:25:43 AM by Brown, Scott T.

SRO NRC Exam 2003 Question No. 14 Exam Bank Question No.: 5627 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-217 Objective: CRO 5b Question Level: Comprehension Select the correct answer:

RCIC is operating in the injection mode with its suction path from the torus. A slow leak develops in the torus.

As torus level continues to lower, RCIC:

Answer/Distractor will trip on low suction pressure.

will trip on high exhaust pressure.

suction will auto transfer to the CST on low torus water level.

suction will auto transfer to the CST on low suction pressure.

Justification Incorrect - The slow reduction in torus level will allow RCIC to continue to run with its exhaust line uncovered and its suction line submerged pressurizing the containment preventing a low suction pressure trip Correct Response EOP 3 study guide page 8-37. RCIC high exhaust pressure trip occurs at 43 psig and the primary containment vent rupture disc ruptures at 59 psig and is isolated by TSV 86 during oDerartion Incorrect - We have an Auto Swap on Low CST level. It makes sense to have one on low torus level but VYN does not.

Incorrect - A low suction pressure suction transfer makes sense but VYN does not have one.

References:

OP 2 12 1, rev 29 Pilgrim 2003 NRC EOP 3 study guide page 8-37 New Task Associations 2170030101 Manually Initiate Startup of the RCIC System Knowledge and Abilities Associations

I System 1 WA No. f Statement IRO (SROI 295030 EA1.02 Ability to operate andor monitor the following as they 3.4 3.5 apply to LOW SUPPRESSION POOL WATER LEVEL:

(CFR 41.7,45.6): RCIC: Plant-specific Static Simulator Exams: None Last Revised: 09/16/2003 8:41: 11 AM by Brown, Scott T.

SRO NRC Exam 2003 Question No. 15 Exam Bank Question No.: 5628 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-256 Objective: CRO 2 Question Level: Fundamental KnowledgelMemory Select the correct answer:

All reactor feedwater pumps have tripped causing a scram. HPCI and RCIC are unavailable.

Condensate pumps will be capable of feeding the reactor when reactor pressure is less than and their motor amps should be maintained less than amps.

I !

AnswerlDistractor 1 Justification 1

I d. I250 psig, 250 amps I Incorrect -

References:

LOT-00-610, CRO Obj. 6,7, 12 RP 2170, rev 21, page 6 New Task Associations

~

Task Number Task Title 20003 10501 Respond to Low Reactor Water Level Knowledge and Abilities Associations Static Simulator Exams: None Last Revised: 09/18/2003 6:26: 19 PM by Brown, Scott T.

SRO NRC Exam 2003 APRM downscales come in.

reactor power reaches the heating range with a negative period.

reactor water level reaches -19 inches.

only one SRV is open for reactor pressure control.

Ouestion No. 16 Exam Bank Question No.: 5629 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-610 Objective: CRO 2 Question Level: Analysis Select the correct answer:

Correct Response Incorrect - This is indication of the reactor being shutdown but is applicable when a cooldown is commenced and no boron has been injected.

Incorrect - This is the bottom of the ATWS level band of +6 to -19", injection should recommence at +6" - TAF.

Incorrect - Regardless of SRV conditions, injection is recommenced at TAF to insure adequate core cooling.

Given the following conditions:

ATWS in progress Reactor power is 20%

Torus temperature is 115°F Reactor pressure control is on SRVs 800- 1000 psig Reactor water level is +25" Injection has been terminatedprevented IAW OE 3107 Appendix GG Which of the following conditions would establish the upper end of the RPV level control band?

Answer/Distractor I Justification

References:

EOP-2, rev 4 Pilgrim 2003 NRC New EOP-2 is a required student reference Task Associations 2000310501 Respond to Low Reactor Water Level Knowledge and Abilities Associations

I System I WA NO. 1 Statement IRO ISROI 29503 1 EA2.02 Ability to determine and/or interpret the following as they 4.0 4.2 apply to REACTOR LOW WATER LEVEL:(CFR 41.10, 43.5.45.13l: Reactor Dower Static Simulator Exams: None Last Revised: 08/20/2003 8:41:46 AM by Hallonquist, Nora E.

SRO NRC Exam 2003 Question No. 17 Exam Bank Question No.: 5630 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-610 Objective: CRO 2 Question Level: Analysis Select the correct answer:

Given the following conditions:

ATWS 15% of the SLC tank has been injected Reactor level band is -19" to 40" At this point has been injected into the RPV. This amount of boron will allow

c.

d.

1 AnswerLIistractor cold shutdown boron weight, a cooldown cold shutdown boron weight, restoration of level to 127" to 177" I a. 1 hot shutdown boron weight, a cooldown WA No.

EK3.04 Statement RO SRO Knowledge of the reasons for the following responses as 3.2 3.7 Justification Incorrect -

Correct Response - EOP-2 Step ARCL-10 and Table I. Hot shutdown boron weight is 15% of the SLC tank. Cold shutdown boron weight is 30% of the SLC tank. Can raise the level band. can not cooldown.

Incorrect -

Incorrect -

References:

EOP-2, rev 4 New EOP-2 is a required student reference Task Associations 2000200501 Respond to ATWS Event(s)

Knowlec ze and Abilities Associations they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR

-OW:

(CFR 41.5,45.6): Hot shutdown boron weight: Plant-specific

Static Simulator Exams: None Last Revised: 07/25/2003 9:47:32 AM by Hallonquist, Nora E.

SRO NRC Exam 2003 600000 Ouestion No. 18 Exam Bank Question No.: 563 1 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-286 Objective: CRO 4a Question Level: Comprehension Select the correct answer:

AJS3.04 Knowledge of the reasons for the following responses as 2.8 3.4 they apply to PLANT FIRE ON SITE:: Actions contained in the abnormal procedure for plant fire on site An electrical fire is burning in MCC89A in the reactor building. To use water to fight the fire in MCC89A:

Answer/Distractor it must be deenergized and the Brigade Commander's permission is required to use water on an electrical fire.

it should be deenergized and the Brigade Commander's permission is required to use water on an electrical fire.

it must be deenergized and the Shift Manager's permission is required to use water on an electrical fire.

it should be deenergized and the Shift Manager's permission is required to use water on an electrical fire.

Justification Incorrect -

Incorrect -

Incorrect -

Correct Response-Fire hose stations in the area of MCC 89A are equipped with "E nozzles". They are brass, smaller than regular nozzles,and opened by lever action as opposed to twist action. They are also smaller when compared to regular nozzles.

They are specifically placed so that water can be used on energized electrical equipment to fight a fire.

References:

OP 3020, rev 25, definitions and page 10 New Task Associations 2867290401 Respond to Pyrotronics Panel Alarms Knowledee and Abilities Associations

Last Revised: 09/16/2003 8:49:39 AM by Brown, Scott T.

SRO NRC Exam 2003 Ouestion No. 19 Exam Bank Question No.: 5632 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-607 Objective: CRO 1 Question Level: Fundamental KnowledgeAlemory Select the correct answer:

When entering EOP-3, Primary Containment Control, which of the following is the preferred indication to be used to determine torus water temperature?

I d. I The higher of TI-16-19-33 A or C I Incorrect -

I

References:

EOP, rev 11, Vol4, Section 8, page 8-4 New Task Associations Task Number Task Title 2000190501 Respond to High Torus Water Temperature Knowledge and Abilities Associations POOL HIGH WATER TEMPERATURE and the following: (CFR 41.7,45.8): SPDS/ERIS/CRIDS/GDS:

Static Simulator Exams: None Last Revised: 07/29/2003 12:05:31 PM by Hallonquist, Nora E.

SRO NRC Exam 2003 295038 Question No. 20 Exam Bank Question No.: 5633 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-138 Objective: 17, 19 Question Level: Fundamental Knowledgehlemory Select the correct answer:

2.2.25 Knowledge of bases in technical specifications for limiting 2.5 3.7 conditiond for operations and safety limits (CFR 43.2)

A reactor pressure transient has occurred causing a violation of the high power MCPR safety limit of for two loop operation, and the resulting fuel damage could cause a member of the public to exceed mRem total body dose allowed for the year at the site boundary.

Answer/Distxactor I Justification

References:

ODCM (formerly T.S.), rev 30 Tech Specs 1.1 176 New Task Associations

~

Task Number Task Title 2007090501 Respond to High Off-Gas Radiation Know1edg;e and Abilities Associations Static Simulator Exams: None Last Revised: 07/3 1/2003 10: 1 1 :05 AM by Hallonquist, Nora E.

SRO NRC Exam 2003 Ouestion No. 2 1 Exam Bank Question No.: 5634 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-602 Objective: CRO 3 Question Level: Comprehension Select the correct answer:

During power operation an air leak into the main condenser causes SJAE off gas flow on CRP 9-6 FR-102-3 to go off scale high.

This will cause AS-FCV-36,36A, and 37 (steam jet air ejector steam supply valves) to trip shut when:

Answer/Distractor condenser backpressure reaches 22" Hg abs.

temperature in the SJAE discharge/AOG inlet reaches 375°F.

condenser backpressure reaches 12" Hg abs.

pressure in the SJAE discharge/AOG inlet reaches 4 psig.

Justification Incorrect - Lowering condenser vacuum does not affect the operation of FCV 36, 36A, 37.

Incorrect - Increased air inleakage causes the off gas temperature to decrease, not increase. FCV 36,36A, & 37 do not trip on off gas temr>erature changes.

Incorrect - Lower vacuum does not affect the operation of FCV 36,36A, 37.

Correct Response - AS-FCV-36,36A, 37 are tripped shut by increasing SJAE discharge/AOG inlet pressure at 4.0 psig and increasing as sensed bv PS-OG-1403.

References:

LOT-00-271 CRO obj. 5 OT 3120, rev 13 OP 21 50, rev 27 New Task Associations 200008050 1 Respond to a Loss of Condenser Vacuum Knowledge and Abilities Associations I 295002 I AK1.04 I Knowledge of the operational implications of the 13.0 13.3 I

I l

l following-concepts as they apply-to LOSS OF MAIN CONDENSER VACUUM: (CFR 41.8 to 41.10): Increased

I offgas flow Static Simulator Exams: None Last Revised: 08/20/2003 8:40:59 AM by Hallonquist, Nora E.

SRO NRC Exam 2003 Question No. 22 Exam Bank Question No.: 5635 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-288 Objective: CRO 5 Question Level: Comprehension Select the correct answer:

A large reactor coolant leak has occurred in the drywell. Primary Containment Control, EOP-3 was entered. Drywell cooling was maximized as directed by EOP-3. Several minutes later the Shift Technical Advisor observes all drywell RRUs are off.

The reason they tripped is:

thermal overload.

low drywell pressure (RHR drywell pressure logic).

high drywell pressure (RHR drywell pressure logic).

short circuit.

Justification Correct Response - Increased drywell pressure and moisture increase the work done by the RRU motors and cause the thermal overloads to trip at dyrwell messures of 10-14 Dsicr.

Incorrect - Low drywell pressure causes an isolation of the drywell sprays and torus but does not affect RRU operation.

Incorrect - The operator had already bypassed the RRU high drywell pressure RRU trip to restart them after the large leak caused drywell pressure to exceed 2.5 psig which trips the RRUs and is the entry condition for EOP-3.

Incorrect - The RRUs are qualified to operate post LOCA. The high humidity will not cause them to short out.

References:

DP 0166, rev 7, page 6 DR 93-0078 EDCR 90-405 New Task Associations 2227020401 Knowledge and Abilities Associations Startup Drywell RRUS Following a LOCA

I System I WA No. I Statement IRO ISRO1 I 295010 I AK3.02 I Knowledge of the reasons for the following responses as I 3.4 I 3.4 I

they apply to HIGH DRYWELL PRESSUkE: (CFR 41.5, 45.6): Increased drywell cooling Static Simulator Exams: None Last Revised: 09/16/2003 8:52:26 AM by Brown, Scott T.

SRO NRC Exam 2003

c.

Ouestion No. 23 Exam Bank Question No.: 5636 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-6 18 Question Level: Fundamental Knowledge/Memory Objective: 1, 13, 15 Select the correct answer:

60 minutes, peak torus temperature The "A" Recirculation Loop has just experienced a double-ended rupture of the suction line.

295013 LPCI injection must be shifted to the containment cooling mode no later than after the break to limit AK3.01 Knowledge of the reasons for the following responses as 3.6 3.8 they apply to HIGH SUPPRESSION POOL WATER TEMPERATURE: (CFR 41.5,45.6): Suppression pool I AnswerDistractor I 600 seconds, peak torus temperature

d. 60 minutes, peak drywell temperature 1

1

References:

USFAR, rev 18, 14.6.25 New Task Associations Justification Correct Response-USAR requires containment cooling established at 600 seconds post DBA LOCA Incorrect - USAR 14.6 page 21 requires containment in 30 minutes to limit drywell temperature Incorrect - 60 minutes is beyond the USFAR specified maximum time.

Incorrect - 60 minutes is beyond the USFAR specified maximum time.

Task Number Task Title 2000190501 Respond to High Torus Water Temperature I

I cooling: ooeration I

I Static Simulator Exams: None Last Revised: 09/16/2003 9:29:43 AM by Brown, Scott T.

SRO NRC Exam 2003

a.

Ouestion No. 24 Exam Bank Question No.: 5637 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-308 Objective: CRO 2,3,4, 5 Question Level: Fundamental KnowledgeMemory Select the correct answer:

A n s werDistractor Reactor pressure, 120°F The outboard MSNs have failed shut due to a loss of instrument air. Some control rod motion has occurred. Reactor power is 60%.

d.

This transient has caused the violation of the Safety Limit (SL) and may exceed the torus temperature limiting condition for power operation (LCO) of Fuel Cladding, 120°F

~ -,

29501 5 2.2.22 Knowledge of limiting conditions for operations and safety 3.4 4.1 Justification Incorrect - 60% power is within the capasity of the SRVsRVs.

Correct Response - MSIV closure in RUN is a required scram and the scram did not occur. -The safety limit shall be assumed to be exceeded. 110°F is the torus temperature LCO. MCPR is the actual thermal limit that is challenged.

Incorrect -60% power is within the capasity of the SRVsRVs.

Incorrect - Technical Specifications require a reactor scram when torus temperature exceeds 1 10°F.

References:

LOT-00-607 CRO Obj. 1 Tech Specs 188,7, page 146 New Task Associations Task Number Task Title 2000200501 Respond to ATWS Event(s)

Knowledge and Abilities Associations I limits (CFR 43.2,45.2)

Static Simulator Exams: None

Last Revised: 09/18/2003 6:3 1 :48 PM by Brown, Scott T.

SRO NRC Exam 2003

b.

Question No. 25 Exam Bank Question No.: 5638 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-607 Objective: CRO 2,3 Question Level: Comprehension Select the correct answer:

the volume of the gas in the containment would be insufficient to absorb the energy of a full RPV-ED.

Incorrect -

EOP-3, Primary Containment Control, requires an RPV-ED if torus level can not be restored and maintained below 14.75 feet.

c.

d.

The reason for this action is:

operation of an SRV at this level could Incorrect -

damage Tee-quencher supports.

during a DBA LOCA, the reactor pressure Incorrect -

vessel must be depressurized before the torus spray function is lost.

'1 Drimarv containment can not be assured.

I

References:

EOP, rev 11, Volume 4 LOI-EB 3769 Task Associations 2000230501 Respond to High Torus Water Level Knowledrre and Abilities Associations following-concepts as they applyto HIGH SUPPRESSION POOL WATER LEVEL: (CFR 41.8 to 41.10): Containment integrity Static Simulator Exams: None Last Revised: 07/31/2003 10: 1251 AM by Hallonquist, Nora E.

SRO NRC Exam 2003

b.

Question No. 26 Exam Bank Question No.: 5639 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-61 1 Objective: CRO 3,5 Question Level: Fundamental KnowledgeMemory Select the correct answer:

Local radiation readings as reported by an RP tech EOP-4, Secondary Containment Control, has been entered. To determine if any area radiation level is above its maximum safe level, which of the following should be reported to the CRS:

d.

1 Answer/Distractor Local radiation readings at the ARMS in the reactor building ARM readings on the Allen Bradley on CRP 9-21 295033 EA2.01 Ability to determine and/or interpret the following as they 3.8 3.9 apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS:(CFR 41.10,43.5,45.13).: Area radiation levels Correct Response - ERFIS is used for EOP decision making and provides the necessary reactor building radiation levels.

Incorrect - It is not expected or required to enter the reactor building to determine radiation level.

References:

EOP-4, rev 2 DP 0166, rev 7, page 7 New Task Associations Justification Incorrect - Allen Bradley provides area temperatures for EOP use and is next to the reactor building back panel ARM panels.

Incorrect - It is not expected or required to enter the reactor building to determine radiation level.

' T&k Number Task Title '

2727150401 Respond to ARM Alarms Static Simulator Exams: None Last Revised: 09/16/2003 9:40:29 AM by Brown, Scott T.

SRO NRC Exam 2003 Question No. 27 Exam Bank Question No.: 5640 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-223 Objective: CRO 4,5 Question Level: Comprehension Select the correct answer:

Reactor building ventilation radiation monitor "A" is bypassed by I&C for testing and is downscale. The "B" reactor building ventilation radiation monitor reading increases to 20 mR/hr.

Your response should be to:

Answer/Distractor direct I&C to return the "A" channel to service so that RB ventilation can be left on.

confirm PCIS Group 3 isolations and SBGT system startup.

manually secure RB ventilation, isolate HVAC 9,10,11,12 and start SBGT.

direct RP to monitor RB ventilation exhaust in accordance with the ODCM.

References:

OP 21 17, rev 17, Discussion New Task Associations Jus ti ficat ion Incorrect - This is a logical action if the student does not understand system operation during I&C testing.

Correct Response - Student must know that I&C keylocks only bypass upscale trips.

Two downscales on RB vent exhaust is an isolation signal, one upscale is an isolation.

Only one key lock bypass is allowed in bypass at any time. RB ventilation will trip and isolate and SBGT will start.

Incorrect - This is a logical action if the student does not understand system oDeration during; I&C testing.

Incorrect - This is a logical action if the student does not understand system operation during I&C testing.

Task Number Task Title 2737060101 Respond to Automatic Actions from Local Monitors Knowledge and Abilities Associations Ability to operate andor monitor the following as they apply to SECONDARY CONTAINMENT

VENTILATION HIGH RADIATION: (CFR 41.7,45.6):

Process radiation monitoring system Static Simulator Exams: None Last Revised: 09/16/2003 9:41:58 AM by Brown, Scott T.

SRO NRC Exam 2003 Question No. 28 Exam Bank Question No.: 5641 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-205 Objective: CRO 2,4 Question Level: Analysis Select the correct answer:

Given the following conditions:

Drywell pressure is 11 psig and rising Reactor pressure is 300 psig and lowering Reactor level is +20" and steady Core Spray A/B are injecting RHR A is operating in torus cooling RHR B is operating in torus spray U P S Feeder block keylocks are in block, the 5 minute timers are timed out Reactor level rapidly lowers to -1 50" and continues down. The RHR system will:

open A & B LPCI injection valves, close llkt torus cooling valves, close t t

~

torus spray valves.

close RHR A torus cooling valves, close RHR B torus spray valves.

open RHR Heat exchanger bypass valves, ciose t t ~ t t torus cooling ;alvei, close l l ~ l f torus spray valves, open A & B LPCI injection valves.

open RHR A & B LPCI injection valves, open A & B heat exchanger bypass valves.

Incorrect - RHR 27A and B injection signals 5 minutes timers have timed out and the UPS FDR blocks have been placed in block and RHR 27 A & B have been manually shut to establish torus cooling torus spray. RHR 27 A & B will remain shut.

Correct Response - At -48 the non LPCI injection paths are isolated.

Incorrect - The RHR 65 open signal was present for one minute and the time must have passed to establish torus cooling. To establish torus coolingkprays, the RHR 27 valves had to be shut which means that 5 minutes have passed since they auto opened and the UPS Feeders are in block.

Incorrect - All four valves will remain shut.

References:

LOT-03-262 CRO Obj. 6,7 OP 2124, rev 50, Appendix B & C New

Task Associations 203000 2000310501 Knowledge and Abilities Associations Respond to Low Reactor Water Level A3.05 Ability to monitor automatic operations of the RHWLPCI:

INJECTION MODE (PLANTSPECIFIC) including:

(CFR 41.7 / 45.7): Reactor water level 4.4 4.4 Static Simulator Exams: None Last Revised: 08/20/2003 9:04:48 AM by Hallonquist, Nora E.

SRO NRC Exam 2003 Ouestion No. 29 Exam Bank Question No.: 5642 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-205 Objective: CRO 2 Question Level: Fundamental KnowledgeMemory Select the correct answer:

Given the following conditions:

"A" Loop of RHR is operating in shutdown cooling Reactor pressure is 100 psig and slowly rising If reactor pressure continues to increase, the RHR system will:

I AnswerDistractor 17 & 18 (shutdown cooling to protect it from cavitation damage at 366 degrees F

c. shut RHR 17 & 18 (shutdown cooling suction) to protect the piping from overpressure at 350 psig.

d. trip the pump running in shutdown cooling to protect it fiom cavitation damage at 436 descrees F.

Correct Response - Correct isolation valves, correct setpoint for protective instrumentation.

Incorrect - The height of water above the pump suction prevents cavitation.

Incorrect - The piping on the suction line is only rated for 150 psig.

Incorrect - The height of water above the pump suction prevents cavitation.

References:

Tech Spec Table 3.2.1 186 New Task Associations Task Number Task Title 2000150501 Respond to a Loss of Shutdown Cooling Knowledge and Abilities Associations I

I I comDonents and contIols KFR 41.7'1 I

I I

Static Simulator Exams: None Last Revised: 09/16/2003 10:02:17 AM by Brown, Scott T.

SRO NRC Exam 2003

a.

b.

Question No. 30 Exam Bank Question No.: 5643 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-206 Objective: 1 Oc Question Level: Fundamental Knowledgehfemory Select the correct answer:

Vital AC Instrument AC The initiation logic that provides automatic HPCI initiation signals is powered from:

System K/A No. Statement RO SRO' 206000 K2.03 Knowledge of electrical power supplies to the following:

2.8 2.9 I Answer/Distractor Justification Incorrect -

Incorrect -

Correct Response - OP 2145 Appendix A, pages 1,5 Incorrect -

References:

OP 2145, rev 24, Appendix A New Task Associations

~

Task Number Task Title 2000320501 Respond to a Loss of DC-1,2,3 Knowledge and Abilities Associations I (CFR 41.7): Initiation logic: BWR-2, 3,4 Static Simulator Exams: None Last Revised: 07/29/2003 12:09: 15 PM by Hallonquist, Nora E.

SRO NRC Exam 2003

a.

b.

Question No. 31 Exam Bank Question No.: 5644 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-206 Objective: CRO 3,5b, 6b, 7 Question Level: Fundamental KnowledgeMemory Select the correct answer:

to trip and the minimum flow valve to open.

flow valve.

to run at 2200 rpm and the minimum flow Incorrect - The inhibit switch shuts the min Incorrect - The inhibit switch does not act HPCI has started automatically on a high drywell pressure signal. The CRS directs you to inhibit HPCI.

to trip and the minimum flow valve to close.

When you lock the collar in inhibit, you expect the turbine:

Correct Response - The inhibit switch energizes the turbine trip solenoid, and shuts the min flow valve so the CST does not drain to the torus.

I !

AnswerLDistractor 1 JtiStification valve to open.

I I

on the turbine speed control system, and it shuts the min flow valve.

to run at 2200 rpm and the minimum flow Incorrect - The inhibit switch does not act 1 on the turbine speed control system.

valve to close.

References:

OP 2120, rev 27 A R S 9-3-5-1, rev 0 New Task Associations Task Number Task Title 2007450501 Terminate and Prevent Injection to the RPV During an ATWS the HIGH PRESSURE Static Simulator Exams: None Last Revised: 07/25/2003 10:08:31 AM by Hallonquist, Nora E.

SRO NRC Exam 2003

a.

b.

Ouestion No. 32 Exam Bank Question No.: 5645 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-21 8 Objective: CRO 2 Question Level: Fundamental KnowledgeMemory Select the correct answer:

maintain both logics energized and shut all Incorrect -

SRVs.

deenergize the "A" logic and shut SRVs A Incorrect -

& c.

An ADS blowdown is in progress. All six low pressure ECCS pumps are running, when both Core Spray pumps trip due to improper overload trip settings.

209001 The ADS system will:

K3.02 Knowledge of the effect that a loss or malfunction of the 3.8 3.9 LOW PRESSURE CORE SPRAY SYSTEM will have on following;: (CFR 41.7 / 45.4): ADS logic

References:

LOT-00-206, CRO Obj. 8 New CWD 750-756 Task Associations Task N 2000310501 Respond to Low Reactor Water Level Knowledge and Abilities Associations I System I WA No. 1 Statement

/RO 1SROI Static Simulator Exams: None Last Revised: 07/29/2003 12:09:36 PM by Hallonquist, Nora E.

SRO NRC Exam 2003 21 1000 Question No. 33 Exam Bank Question No.: 5646 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-21 1 Objective: A 0 2g Question Level: Comprehension Select the correct answer:

K1.02 Knowledge of the physical connections and/or cause-effect 2.7 2.7 relationships between STANDBY LIQUID CONTROL SYSTEM and the following: (CFR 41.2 to 41.9 / 45.7 to 45.8): Core date differential Dressure indication The high pressure sensing line for the core plate D P instrumentation has a fitting leak of 10 gpm at the D/P cell. An ATWS event occurs and SLC "A" system is started.

The SLC system will inject:

1 1 Answer/Distractor some of the boron on the floor in the Southeast Corner Room.

I JUitification I

Incorrect -

I Incorrect -

Incorrect -

Correct Response - The core plate DP instrument high pressure tap is below the core plate and is the SLC injection path.

10 gpm of SLC in will go out the leak.

References:

LOT-00-216, CRO Obj. lb, c G191267 Sheet 1 New Task Associations Task Nynber Task Title 1

21 10050101 Inject Poison Solution into the Reactor Vessel Static Simulator Exams: None Last Revised: 08/12/2003 3:09:46 PM by Hallonquist, Nora E.

b.

SRO NRC Exam 2003 Add sodium pentaborate to the condensate demineralizer precoat tank and inject with condensate and feedwater systems.

Question No. 34 Exam Bank Question No.: 5647 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-626 Objective: CRO 4 Question Level: Fundamental KnowledgeMemory Select the correct answer:

I 21 1000 I K3.01 During an ATWS with the Standby Liquid Control System out of service, which one of the following is a procedurally directed method of alternate boron injection?

Knowledge of the effect that a loss or malfunction of the 4.3 I 4.4 I

STANDBY LIQUID CONTROL SYSTEM will have on following: (CFR 41.7 / 45.4): Ability to shutdown the reactor in certain conditions 1 Answer/Distractor

a. Add sodium pentaborate to the condensate I

I storage tank and mixhniect with HPCI.

Justification Incorrect -

Incorrect -

Correct Response - This is the only correct flow path available in procedure OE 3 107, the other flow paths would work but no Drocedure directs their use.

Incorrect -

References:

OE 3 107, rev 16, Appendix K, Modified Distractors Grand Gulf NRC 3/27/1998 INPO Bank Task Associations 2007600501 Perform Boron Injection Using CRD System from SLC Tank Static Simulator Exams: None Last Revised: 09/16/2003 10:04:37 AM by Brown, Scott T.

SRO NRC Exam 2003 Ouestion No. 35 Exam Bank Question No.: 5648 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-212 Objective: CRO 2 Question Level: Comprehension Select the correct answer:

When resetting a full scram the reset switch is positioned to the Group 1 and 4 position last. This ensures the relays that on reset, the solenoid valve that supplies air to open the scram discharge vent and drain valves when all the scram inlet and outlet valves are closed or are closing.

I Answer/Distractor 1 'Justification

References:

OP 2 134, rev 16, Page 9 Caution New Task Associations Task Number Task Title Ir 2127060101 Reset RPS Trips Knowledrre and Abilities Associations associated with operating the REACTOR PROTECTION SYSTEM controls including: (CFR 41.5 /45.5): Individual relay status: Plant-Specific Static Simulator Exams: None Last Revised: 09/18/2003 6:34:50 PM by Brown, Scott T.

SRO NRC Exam 2003 APRMs and ERFIS(CTP)

IRMsand APRMs I R M S APRMS Ouestion No. 36 Exam Bank Question No.: 5649 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-02-215 Objective: CRO 2i Question Level: Fundamental KiowledgelMemory Select the correct answer:

Incorrect - Core thermal power can not be accurately calculated with no RFPs running.

Incorrect - IRMs can not be driven into the core. Motor drive power is from PP6A on MCC6A powered fi-om Bus 1 which has lost power during the LNP.

Incorrect - IRMs can not be driven into the core. Motor drive power is from PP6A on MCC6A powered from Bus 1 which has lost power during the LNP.

Correct Response - RPS MG sets trip on the LNP and APRMs automatically transfer to VitaVInst AC An LNP occurs while operating at full power. Post scram reactor power can be monitored on:

AnswerDistractor 1,Justification

References:

OP 2 1 3 1, rev 14, Prerequisites New Task Associations 2000330501 2007020501 Respond to a Reactor SCRAM Respond to Loss of Normal Power INTERMEDIATE RANGE MONITOR (IRM) SYSTEM will have on following: (CFR 41.7 / 45.4): Reactor power indication Static Simulator Exams: None Last Revised: 09/16/2003 10:06:05 AM by Brown, Scott T.

SRO NRC Exam 2003 215003 Question No. 37 Exam Bank Question No.: 5650 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-02-215 Objective: CRO 8 Question Level: Analysis Select the correct answer:

K6.04 Knowledge of the effect that a loss or malfunction of the 3.0 3.0 following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: (CFR 41.7 / 45.7): Detectors A reactor startup is in progress. Reactor power is 50/125 scale on Range 7. IRM detectors A &

D were replaced during the outage and both have just failed downscale. The CRS directs IRM A

& D bypassed.

Under these conditions the remaining IRMs detectors satisfl operability requirements for:

Justification Correct Response - IRMs A, C & E provide signals to RPS A. IRMs B, D & F provide signals to RPS B. With IRMs A &

D failed, each RPS trip system still has two inputs and satisfied T.S. Table 3.1.1.

Incorrect -

Incorrect -

I d. I neither RPS trip system.

I Incorrect -

References:

OP 2130, rev 14, page 1 Tech Spec Table 3.1.1 Notes New Task Associations Task Number Task Title 2157160401 Respond to IRM System Alarms Static Simulator Exams: None Last Revised: 09/16/2003 10:07:35 AM by Brown, Scott T.

SRO NRC Exam 2003 Question No. 38 Exam Bank Question No.: 565 1 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-215 Objective: CRO 6 Question Level: Fundamental Knowledge/Memory Select the correct answer:

The SRM detector high voltage power supply is powered from:

I 208 VAC PP6A CKT 25 I Incorrect - This is the power source to the I drive motor.

Incorrect - This is the control power to the 120 VAC Instrument AC CKT 7 detector drive control circuits.

Incorrect - DC-1 CDC-2C provide no power to the SRMs.

Correct Response - OP 2 130, page 2A, 125 VDC DC-lCLlC-2C CKT 2/2

• 24 VDC A/B CKT 5/5

$ 8 Power Supplies

References:

OP 2 130, rev 15 New Task Associations 2157170401 Respond to SRM System Alarms I 215004 I K2.01 I Knowledge of electrical power supplies to the following: I 3.6 12.8 I

I (CFR 41.7): SRM channels/detectors Static Simulator Exams: None Last Revised: 07/25/2003 11 :56:54 AM by Hallonquist, Nora E.

SRO NRC Exam 2003 Ouestion No. 39 Exam Bank Question No.: 5652 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-05-215 Objective: CRO 6 Question Level: Comprehension Select the correct answer:

APRM downscale alarm has come in and APRM "E" indicates downscale on the CRP 9-5 bench board. The BOP is sent to the APRM cabinet to investigate. While attempting to check LPRM inputs, the BOP inadvertently positions the APRM "E" Mode Switch from the operate to the power position.

This action will cause:

a. alarms only.

b. alarms and rod block only.

alarms, rod block and 1/2 scram on RPS I "B".

References:

OP 2132, rev 16, page 2 of 5 new Justification Incorrect -

Incorrect -

Correct Response - Function switch out of operation causes alarms, rod block Task Associations 2157150401 Respond to APRM System Alarms I 21 5005 I Al.02 I Ability to predict and/or monitor changes in parameters I 3.9 I 4.0 I

associatedwith operating the AVERAGE POWER RANGE MONITOWLOCAL POWER RANGE MONITOR SYSTEM controls including: (CFR 41.5 /

45.5): RPS status Static Simulator Exams: None Last Revised: 09/16/2003 10:12:04 AM by Brown, Scott T.

SRO NRC Exam 2003 217000 Question No. 40 Exam Bank Question No.: 5653 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-217 Objective: CRO 4b Question Level: Fundamental KnowledgeMemory Select the correct answer:

K5.06 Knowledge of the operational implications of the 2.7 2.7 following concepts as they apply to REACTOR CORE ISOLATION COOLING SYSTEM (RCIC): (CFR 41.5 /

45.3): Turbine operation RCIC is operating and injecting. The RCIC controller is in manual. As reactor pressure lowers fkom 1000 psig to 600 psig, the RCIC turbine speed will:

I Answer/Distractor increase because the controller is flow sensing;.

I

d. decrease because the controller is speed sensing.

Incorrect - Speed will not increase, the controller does not sense flow in manual.

Incorrect - The controller does not sense flow in manual.

Correct Response - In manual, controller operation RCIC turbine speed is held constant.

Incorrect - In manual, the controller maintains a constant turbine meed.

References:

OP 2121 rev 19 New Task Associations 2170030101 Manually Initiate Startup of the RCIC System Knowledge and Abilities Associations Static Simulator Exams: None Last Revised: 09/18/2003 6:36:41 PM by Brown, Scott T.

SRO NRC Exam 2003 218000 Ouestion No. 41 Exam Bank Question No.: 5654 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-218 Objective: CRO 2 Question Level: Fundamental KnowledgeMemory Select the correct answer:

K3.02 Knowledge of the effect that a loss or malfunction of the 4.5 4.6 AUTOMATIC DEPRESSURIZATION SYSTEM will have on following: (CFR 41.7 / 45.4): Ability to rapidly An ADS blowdown is in progress with all RHR and CS pumps running. The pump discharge pressure switches for RHR pumps A and C and CS A fail to the low discharge pressure condition.

The ADS system will:

Answer/Distractor Continue the blowdown with all four SRVs Continue the blowdown with A and C SRVs onlv Continue the blowdown with B and D SRVs only Stop the blowdown bv shutting all SRVs Justification Correct Response-There are two pressure switches in the discharge of each of the six low pressure pumps. The loss of signal from six of these twelve pressure switches will have no impact on the ADS blown in orogress Incorrect -

Incorrect -

Incorrect -

References:

CWD 750/75 1 Modified bank 1703 Task Associations

~

Task Number Task Title 200031050.1 Respond to Low Reactor Water Level Knowledge and Abilities Associations I depressurize the reactor Static Simulator Exams: None Last Revised: 09/16/2003 10:46:28 AM by Brown, Scott T.

SRO NRC Exam 2003 Ouestion No. 42 Exam Bank Question No.: 5655 Revision: 3 SRO Only: No Instructor Guide: LOT-00-206 Objective: CRO 5,7, 10a Question Level: Analysis Point Value: 1 Select the correct answer:

DC-1 has been lost due to a fault. To comply with Technical Specifications and operating procedures, HPCI must be shut and its ACB

b. HPCI-15 inbd isolation, kept closed.

c. HPCI-16 outbd isolation. oDened.

Justification Incorrect -

Incorrect -

Incorrect -

Correct Response - Tech Spec to require that another valve in the process line must be closed and its position logged daily.

The student must know that an initiation signal would open HPCI 16 and cause rapid piping pressurization, possible valve or piping damage, therefore, the MOV ACB must be opened.

References:

LOT-0 1-223 CRO Obj. 1,4 OP 2120, rev 27, page 21 Tech Spec 3.7, page 158 OP 21 15, rev 43, page 10 New Students should have T.S. 3.7 as a reference Task Associations 2067090401 Respond to Automatic HPCI System Trip or Isolation Knowledge and AI lities Associations Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM NUCLEAR STEAM SUPPLY SHUT-OFF; and (b) based those predictions, use procedures to correct, control, or mitigate the conseauences of those abnormal conditions or

operations: (CFR 41.5 / 45.6): D.C. electrical distribution failures Static Simulator Exams: None Last Revised: 09/18/2003 6:38:34 PM by Brown, Scott T.

SRO NRC Exam 2003 Ouestion No. 43 Exam Bank Question No.: 5656 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-239 Objective: CRO 3 Question Level: Comprehension Select the correct answer:

A spurious MSIV isolation occurs from full power. All control rods fully insert. SRVs B, C, D (RV-71 B, C, D) lift and safety valve "A" (RV-SV2-70A) lifts. Drywell pressure rapidly rises to 5 psig and is now steady.

The lifting of Safety Valve "A" was

. The rapid rise in drywell pressure when Safety Valve "A" lifted was I a. I exnected. unexnected I Incorrect -

I

References:

SEI-03-200 Obj. 9 USAF, rev 18,4.4.3 Pilgrim 2003 NRC (modified)

New Task Associations 2000180501 Respond to High Reactor Pressure Knowledee and Abilities Associations relationships between RELIEF/SAFETY VALVES and the following: (CFR 41.2 to 41.9 / 45.7 to 45.8): Drywell pressure (for safety valves which discharge to the drywell airspace): Plant-Specific Static Simulator Exams: None

Last Revised: 09/18/2003 6:40:36 PM by Brown, Scott T.

SRO NRC Exam 2003

a.

Question No. 44 Exam Bank Question No.: 5657 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-259 Objective: CRO 5e Question Level: Comprehension Select the correct answer:

Total steam flow signal increases, feed flowlsteam flow mismatch increases reactor water level The plant is operating at 100% power. The "A" main steam line flow D/P instrument fails to zero PSID.

Which one of the following describes the response of the feedwater level control system?

259002 K5.01 Knowledge of the operational implications of the following concepts as they apply to REACTOR WATER I AnswerDistractor 3.1 3.1 Total steam flow signal decreases, feed flowhteam flow mismatch decreases flowkteam flow mismatch decreases reactor water level

d. Total steam flow signal decreases, feed flowhteam flow mismatch increases !

reactor water level Justification Incorrect -

Correct Response - Loss of one steam flow detector will result in indicated steam flow being less than actual. FWLC will close the feed reg valves to match feed flow to steam flow. Reactor level will lower opening the FRVs. Final reactor level will be lower.

Incorrect -

Incorrect -

References:

USAR 7.10, rev 18 Pilgrim 2003 New Task Associations 20003 10501 Respond to Low Reactor Water Level Knowledge and Abilities Associations

LEVEL CONTROL SYSTEM: (CFR 41.5 / 45.3):

GEMAC/Foxboro/Bailey controller operation: Plant-Specific Static Simulator Exams: None Last Revised: 09/16/2003 11:00:35 AM by Brown, Scott T.

SRO NRC Exam 2003

a.

Ouestion No. 45 Exam Bank Question No.: 5658 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-261 Objective: CRO 5 Question Level: Analysis Select the correct answer:

increase due to the exhaust heat added to the pool fiom HPCI.

During full power operation HPCI is started in full flow test for a post maintenance operability run. Initially torus pressure will:

261000 I AnswerDistractor K1.03 Knowledge of the physical connections and/or cause-effect 2.9 3.1 relationships between STANDBY GAS TREATMENT SYSTEM and the following: (CFR 41.2 to 41.9 / 45.7 to 45.8): Suppression Pool I b. 1 increase due to the exhaust heat added to I water volume.

References:

OP 4120 OP 21 17, rev 17 New Incorrect - The torus pressure decreases, not increases, on an HPCI start for Surveillance.

Incorrect - HPCI does not exhaust to the torus air space.

Correct Response - The torus is vented through the 3" line to SBGT during power operation. HPCI exhaust blower start starts both SBGT fans but leaves the reactor building suction valves shut.

SBGT draws a vacuum on the torus.

Incorrect - Torus water volume increases during a HPCI run.

Task Associations 2060030201 Perform HPCI Pump Operability Test Static Simulator Exams: None Last Revised: 07/29/2003 12: 15:21 PM by Hallonquist, Nora E.

SRO NRC Exam 2003 Question No. 46 Exam Bank Question No.: 5659 Revision: 6 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-264 Objective: CRO 11 Question Level: Comprehension Select the correct answer:

When paralleling an EDG for Surveillance Testing, which of the following conditions, as a minimum, must be satisfied for breaker closure to occur?

I I

Answer/Distractor 1 Justification

References:

OP 2142, rev 20, Discussion Section A R S 9-8-5-9, rev 7 New Task Associations Task Title 2640030201 Perform Emergency Diesel Generator Load Tests Knowledge and Abilities Associations 1262001 I K4.05 I Knowledge of A.C. ELECTRICAL DISTRIBUTION I 3.4 13.6 I L

design feature(s) and/or interlocks which provide for the following: (CFR 41.7): Paralleling of A.C. sources (synchroscope)

Static Simulator Exams: None Last Revised: 09/18/2003 6:41:58 PM by Brown, Scott T.

SRO NRC Exam 2003

c.

Ouestion No. 47 Exam Bank Question No.: 5660 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-262 Objective: Id, 3 Question Level: Comprehension Select the correct answer:

pressure down to 67 psig.

pressure that will allow breaker operation.

Must be opened before air pressure lowers Incorrect - 379 ATB does not An air leak has developed on 345 KV Breaker ATB-379. High pressure cylinder pressure is 425 psig and lowering. The compressor has tripped on overload. VELCO has authorized opening the 379 ATB.

d.

The breaker :

to 400 psig and automatic opening occurs.

can not be opened from the control room.

automatically trip on low air pressure.

Incorrect - The breaker can be opened

I to 400 psig and all tripping capability is I

I from the control room down to an air pressure of 400 +/- 10 psig.

References:

OP 2 140, rev 24, Appendix A A R S 9-8-B-2, rev 4 ARS 9-8-B-5, rev 3 New Task Associations 29971 80301 Follow the 345KV Voltage Schedule Knowledge and Abilities Associations room: (CFR 41.7 / 455 to 45.8): All breakers and disconnects (including available switch yard): Plant-Specific Static Simulator Exams: None

Last Revised: 09/16/2003 11:02:28 AM by Brown, Scott T.

SRO NRC Exam 2003 262002 K4.01 Knowledge of UNINTERRUPTABLE POWER SUPPLY 3.1 3.4 (A.C./ D.C.) design feature@) and/or interlocks which provide for the following: (CFR 4 1.7): Transfer from prefenred power to alternate power supplies Question No. 48 Exam Bank Question No.: 5661 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-03-262 Objective: CRO 7 Question Level: Fundamental KnowledgeMemory Select the correct answer:

The plant has experienced a DBA LOCA. RUPS units will:

I Answer/Distractor I Justification manuallv reshut.

References:

UASR, rev 18, 8.4.5.2.1 Bank LO1 VYN #97, modified distractor "D" Task Associations Task Number Task Title 2627260101 Energize 480V Buses and MCCS Static Simulator Exams: None Last Revised: 07/25/2003 12: 19:07 PM by Hallonquist, Nora E.

SRO NRC Exam 2003

c.

d.

Question No. 49 Exam Bank Question No.: 5662 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-601 Objective: CRO 2, 3,4 Question Level: Fundamental KnowledgeMemory Select the correct answer:

No, the reactor feed pumps are likely to trip.

Yes, do it in less than 15 seconds.

The plant is operating at full power. Electrical Maintenance has requested permission to cycle the 4 KV Bus 1 DC control power knife switch to verify operability of the knife switch.

263000 Your direction to Electrical Maintenance is:

K1.O1 Knowledge of the physical connections and/or cause-effect 3.3 3.5 relationships between D.C. ELECTRICAL DISTRIBUTION and the following: (CFR 41.2 to 41.9 /

45.7 to 45.8): A.C. electrical distribution Justification Correct Response Incorrect - The recirc MG Low Lube Oil Trip is delayed for 6 seconds. Up until the last outage, the lube oil pumps tipped on a loss of DC control power. Now the lube oil pumps continue to run.

Incorrect - The removal and restoration of control power to 4 KV Bus will not cause RFPS to tri~.

~~~

~

~~

Incorrect - 15 seconds is the time window for the recirc MG start sequence, which will trip the drive motor breaker on an incomplete start sequence.

References:

OP 2142, rev 20, page 6, Precaution 3 VYN LO1 Bank #1809, modified ON 3 159, rev 4, page 4 Task Associations

' Task Number Task Title 2000320501 2627390401 Respond to a Loss of DC-1,2,3 Respond to Loss of DC Control Power to a 4KV Bus

Static Simulator Exams: None Last Revised: 09/18/2003 6:44:17 PM by Brown, Scott T.

SRO NRC Exam 2003

b.

c.

d.

Question No. 50 Exam Bank Question No.: 5663 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-263 Objective: CRO 2 Question Level: Comprehension Select the correct answer:

shouldnot, 1 Incorrect -

should, 2 Incorrect -

should not. 2 Incorrect -

A ground has been detected on 125 VDC Bus DC-2. Ground meter indication is +127 VDC.

Under these conditions, DC-2 loads operate correctly, and you are required to initiate a priority work request.

References:

OP 2145, rev 24, page 7 New Task Associations 2637090401 Respond to a DC Ground Knowledrre and Abilities Associations Y

D.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR 41.5 / 45.6): Grounds Static Simulator Exams: None Last Revised: 07/3 1/2003 10: 14:40 AM by Hallonquist, Nora E.

SRO NRC Exam 2003 Ouestion No. 51 Exam Bank Question No.: 5664 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-603 Objective: CRO 3 Question Level: Fundamental Knowledgehfemory Select the correct answer:

The "B" EDG is running for surveillance. 125 VDC Bus DC-1 is lost.

Which of the following is correct?

a. All engine protective trips are disabled and the engine can be shutdown from the control room.

be shutdown from the I the engine can only be shutdown locally.

Justificatioh.

Incorrect - The control room can not open the output breaker or shutdown the engine under these conditions.

Incorrect - All engine protective features are lost (except overspeed).

Correct Response - ON 3 159 I

Incorrect - All engine protective features are lost (except overspeed).

References:

LOT-00-264 CRO Obj. 9c ON 3159, rev 4 Step 3 New A R S DB-F-3 Task Associations 2000320501 Respond to a Loss of DC-1,2,3 2647010401 Respond to DG Alarms following will have on the EMERGENCY GENERATORS (DIESEL/JET): (CFR 41.7 / 45.7): D.C.

Static Simulator Exams: None Last Revised: 08/20/2003 9:00:58 AM by Hallonquist, Nora E.

SRO NRC Exam 2003 Question No. 52 Exam Bank Question No.: 5665 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-279 Question Level: Fundamental Knowledge/Memory Objective: A 0 9d, 11; CRO Id Select the correct answer:

Air temperature in the instrument air dryer towers can be monitored on and will provide a Tower Overtemperature Alarm at on the tower that is I b. I ERFIS, 400"F, inservice Justification Incorrect - The inservice tower has no energy source to make it this hot.

Incorrect - The inservice tower has no enernv source to make it this hot.

Correct Response - Student must integrate location of indications, alarm setpoints and potential cause of the alarm - the heaters on the reactivating tower have failed to deenergize at their setpoint and temperatures have not stabilized out at Incorrect - Air dryer temperatures can not be read on ERFIS.

400-425 OF.

References:

OP 2190, rev 29 New Task Associations 2997070304 Monitor Plant Systems During Operator Rounds, Surveillance and Normal Plant Operations Knowledge and Abilities Associations I 300000 I A3.02 I Ability to monitor automatic operations of the 12.9 12.7 I

INSTRUMENT AIR SYSTEM including: (CFR 41.7 /

45.7): Air temperature Static Simulator Exams: None Last Revised: 09/16/2003 11:05:57 AM by Brown, Scott T.

SRO NRC Exam 2003 I 400000 I A3.01 Question No. 53 Exam Bank Question No.: 5666 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-208 Objective: CRO 7 Question Level: Fundamental Knowledge/Memory Select the correct answer:

Ability to monitor automatic operations of the 3.0 13.0 I COMPONENT COOLING WATER SYSTEM including:

(CFR 41.7 / 45.7): Setpoints on instrument signal levels for normal operations, warnings, and tips that are audicable to the CCWS A leak has developed in the RBCCW System. Makeup to the RBCCW expansion tank normally is and the standby pump is automatically started at header pressure.

I d. I automatic, 90 psig Justification Incorrect - Manual is a backup to the automatic makeuu.

Correct Response Incorrect - Manual is a backup to the automatic makeuu.

Incorrect - Standby pump starts at 70 psig not 90 psig.

References:

ON 3147, rev 10 New Task Associations Task Number Task Title 20001 10501 Respond to RBCCW Failure Knowledee and Abilities Associations Static Simulator Exams: None Last Revised: 09/18/2003 6:45:41 PM by Brown, Scott T.

SRO NRC Exam 2003

b.

c.

d.

Question No. 54 Exam Bank Question No.: 5667 Revision: 3 SRO Only: No Instructor Guide: LOT-02-20 1 Question Level: Fundamental KnowledgeNemory Point Value: 1 Objective: CRO 1 a, c, e, 3 Select the correct answer:

withdraw block, and you should confirm the control rod stopped moving.

withdraw block, and you should confirm the control rod deselected.

select block, and you should confirm the control rod stom moving.

Incorrect - A select block is applied, not a withdraw block.

Incorrect - The control rod should not drift but stop on the next notch. A drift alarm may occur.

Incorrect - The control rod is deselected with no settle function.

The reactor is operating at 50% CTP. A control rod is selected and notched out one notch fiom position 32 to 34. The rod sequence control timer fails, the withdraw bus remains energized and the control rod continues out.

The 2 second cycle auxiliary timer will provide a control rod:

References:

A R S 9-5-D-6 rev 4 New Task Associations ask Number Task Title 2010050101 Operate Control Rods Using Single Notch Mode Knowledge and Abilities Associations I201002 I A2.01 I Ability to (a) predict the impacts of the following-on the I 2.7 12.8 I REACTOR MANUAL CONTROL SYSTEM; and (b) based on theose predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR 41.5 / 45.6): Rod movement sequence timer malfunctions Static Simulator Exams: None Last Revised: 09/16/2003 11 : 1153 AM by Brown, Scott T.

SRO NRC Exam 2003

a.

%?

c.

MCPR limits are increased.

APRM Rod Blocks are reduced.

MAPLHGR limits are increased.

Incorrect -

Correct Response Incorrect -

Ouestion No. 55 Exam Bank Question No.: 5668 Revision: 5 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-202 Objective: CRO 4,5 Question Level: Fundamental Knowledgeh4emox-y Select the correct answer:

202002 During full power operation the "A" Recirc Motor Generator trips on differential overcurrent and repairs will take several weeks.

2.1.33 Ability to recognize indications for system operating 3.4 4.0 parameters which are entry-level conditions for Technical Specifications (CFR 43.2.43.3.45.3)

Which of the following limits must be changed to satisfy Tech Specs?

I AnswerDistractor 1 Justification I d. I LHGR limits are reduced.

I Incorrect -

References:

COLR Cycle 23, rev 0 Tech Specs 3.6.G.l.a, 203 LO1 EB #1650, modified Task Associations ask Number Task Title I

2007900501 Respond to a Loss of Bus 1 Using ON 3169 Knowledge and Abilities Associations Static Simulator Exams: None Last Revised: 09/18/2003 6:53:10 PM by Brown, Scott T.

SRO NRC Exam 2003 Question No. 56 Exam Bank Question No.: 5669 Revision: 4 Point Value: 1 SRO Only: No Question Level: Comprehension Instructor Guide: LOT-03-20 1 Objective: CRO 1 f, lj,2 Select the correct answer:

A reactor startup is in progress.

Reactor power on APRMs is 80%. Core flow is 85% of rated. Recirc drive flow is 80% of rated. Reactor power is being increased by control rod withdrawls when an RBM rod block occurs. RBM A is reading 89 and RBM B is reading 81.

To continue the power increase you must:

References:

OP 2133, rev 16 New A R S 9-5-M-7 Task Associations k N Task Title 2017360401 Respond to RBM HYINOP 2157180401 Respond to RBM System Alarms Knowlec ze and Abilities Associations J

ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR 41.5 / 45.6): Withdrawal of control rod in high power region of core: BWR-3,4, 5

Static Simulator Exams: None Last Revised: 09/18/2003 6:53:45 PM by Brown, Scott T.

SRO NRC Exam 2003 Question No. 57 Exam Bank Question No.: 5670 Revision: 1 SRO Only: No Instructor Guide: LOT-00-216 Question Level: Analysis Point Value: 1 Objective: CRO 4, 1 la, 14 Select the correct answer:

A reactor cooldown is in progress. LT-2-3-72A (ECCS) on CRP 9-5 will read when compared to actual RPV level, and as the cooldown continues you shouId transition to the level instrument.

b. Low, LT-2-3-681VB (transient)

c. high, LT-2-3-681VB (transient)

d. low, LI-2-3-86 (refuel)

Correct Response - The correct indicator is recall, but must also recall range &

calibration conditions that make this instrument the preferred instrument for shutdown cooling operations. (This is a recent procedure change, 9/19/02) Must also determine calibration conditions for LT-2-3-72A and how the cooldown affects it.

Incorrect - LI-2-3-68 is not preferred and not cold calibrated.

Incorrect - LI-2-3-681VB is no longer the procedurally preferred instrument.

Incorrect -LT-2-3-72 will read higher than actual level during a cooldown because it is hot calibrated.

References:

OP 2124, rev 50, LPC #7 VYC 332 New Task Associations 2057090101 Operate the RHR System in the Shutdown Cooling Mode Knowledge and Abilities Associations

control, or mitigate the onsequences of those abnormal conditions or operations: (CFR 41.5 / 45.6): Heatup or cooldown of the reactor vessel Static Simulator Exams: None Last Revised: 09/16/2003 12:55:46 PM by Brown, Scott T.

SRO NRC Exam 2003 219000 Ouestion No. 58 Exam Bank Question No.: 5671 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-205 Objective: CRO 2 Question Level: Fundamental Knowledgehlemory Select the correct answer:

K2.01 Knowledge of electrical power supplies to the following:

2.5 2.9 (CFR 41.7): Valves 480 VAC Bus 9 has been lost due to an electrical fault.

Which RHR Loop(s) could be used for torus cooling without the use of local manual valve operations:

a. I Neither "A" nor "B" Loop is available.

I Incorrect - "A" Loop valves have no power, B Loop valves have power.

Incorrect - "A" RHR Loop valves (65,34,

b. "A" Loop is available.

8,39,26,3 1) needed for torus cooling are owered from MCC 9B -> Bus 9 no

References:

OP 2124, rev 50 New Task Associations 2057190101 Startup the RHR System in the Torus Cooling Mode Knowledge and Abilities Associations Static Simulator Exams: None Last Revised: 09/16/2003 12:57:09 PM by Brown, Scott T.

SRO NRC Exam 2003 223001 K5.13 Knowledge of the operational implications of the 2.7 2.8 following concepts as they apply to PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES: (CFR 41.5 / 45.3): Oxygen concentation measurement: Plant-Specific Ouestion No. 59 Exam Bank Question No.: 5672 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-229 Objective: CRO 5 Question Level: Fundamental KnowledgeLMemory Select the correct answer:

During power operation the drywell oxygen concentration is monitored and the torus oxygen concentration is monitored L

I 1 AnswerDistractor

' I Justification continuously, periodically Correct Response - The drywell is

References:

OP 2125, rev 19, page 3 New Task Associations ask Number.Task Title 2297130101 Operate CAD Panel H2/02 Analyzer Knowledge and Abilities Associations Static Simulator Exams: None Last Revised: 07/25/2003 12:38:13 PM by Hallonquist, Nora E.

SRO NRC Exam 2003 Ouestion No. 60 Exam Bank Question No.: 5673 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-234 Objective: A 0 2a, b, c, 10a Question Level: Analysis Select the correct answer:

Refueling is in progress. You are over the fuel pool, grapple closed, bundle seated in the rack.

A loss of off-site power occurs (LNP). The refueling equipment will and OP 1101 requires the Refueling Crew to

a.

C.

d.

AnswerDistractor continue to operate, open the grapple.

stop as is, halt refueling operations, inform the Shift Manager.

continue to operate, halt refueling operations.

stop as is, restart the bridge and, with the refueling SRO's concurrence, open the m a d e.

Incorrect - All refueling motors are variable speed DC motors. This distractor is plausible if the student believes them to be powered from the station 125 VDC batteries.

Correct Response - The student must analyze that the LNP causes a loss of power to refueling equipment which fails as it. Then he must analyze that the EDG repowers the bus in 13 seconds. He must know that the refueling equipment is not load shed, and will be repowered. He must know that the bridge will not auto restart when power is restored. He must also know that OP 1 10 1 requires halting refueling should an LNP occur. His natural desire will be to restart the bridge and oDen the m a d e.

Incorrect - All refueling motors are variable speed DC motors. This distractor is plausible if the student believes them to be powered from the station 125 VDC batteries.

Incorrect -

References:

OP 1101, rev 35, Appendix A OT 3 122, rev 19, Appendix B New

Task Associations 2007020501 j Task Number Task Title Respond to Loss of Normal Power I 234000 I A2.03 Ability to (a) predict the impacts of the following on the FUEL HANDLING; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR 41.5 / 45.6): Loss of electrical Dower 2.8 3.1 Static Simulator Exams: None Last Revised: 08/20/2003 8:54:15 AM by Hallonquist, Nora E.

SRO NRC Exam 2003 Ouestion No. 61 Exam Bank Question No.: 5674 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-302 Objective: RO 13 Question Level: Comprehension Select the correct answer:

A plant startup is in progress. The turbine steam chest is warmed and the turbine is on the jacking gear. 1 &1/2 bypass valves are open. MS-6 (steam seal regulator inlet) motor shorts out and strokes the valve closed.

This will cause main condenser backpressure to and you should open'

a. Remain constant, MS-10 (steam seal regulator bypass)

b. Remain constant, MS-9 (steam seal regulator unloader)

Increase, MS-10 (steam seal regulator I

lunloader)

References:

ARS 9-7-K-9 New Task Associations Justification Incorrect - Back preesure will increase under the given conditions due to condenser air in leakage Incorrect -Back preesure will increase under the given conditions due to condenser air in leakage Correct Response-Student must analyze that the turbine steam seal normally comes from first stage turbine leakage at power.

During a startup at this point the turbine control valves are shut, and turbine first stage pressure is at a vacuum. Steam seal steam must be supplied by the main steam system through the regulator which has just been isolated. Loss of seal steam will cause backkpressure to rise and opening MS 10 will restore sealing steam and condenser backpressure will return to normal.

Incorrect - Opening the gland seal steam unloader will have no affect on the increasing condenser backpressure

Task Number Task Title 2450020101 Startup the Turbine to Rated Speed MAIN AND REHEAT STEAM SYSTEM will have on following: (CFR 41.7 / 45.4): Seal steadgland seal system Static Simulator Exams: None Last Revised: 09/16/2003 4:38:30 PM by Brown, Scott T.

SRO NRC Exam 2003 241000 Ouestion No. 62 Exam Bank Question No.: 5675 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-249 Objective: CRO 5,7,9 Question Level: Comprehension Select the correct answer:

A3.12 Ability to monitor automatic operations of the REACTOWTURBINE PRESSURE REGULATING SYSTEM including: (CFR 41.7 / 45.7): Turbine trip testing:

Turbine emergency governor testing is in progress at full power. AEter moving the emergency governor test switch from the Trip to the Reset position by procedure you would expect the:

2.9 turbine will trim 1

2.9

References:

OP 4160, rev 32, page 20 New Task Associations Task Number Task Title 24571 10201 Perform Emergency Governor Test Knowledge and Abilities Associations I System I WA No. 1 Statement L

IRO ISROI Static Simulator Exams: None Last Revised: 09/18/2003 7:02:59 PM by Brown, Scott T.

SRO NRC Exam 2003 256000 Question No. 63 Exam Bank Question No.: 5676 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-256 Objective: lj, 2 Question Level: Analysis Select the correct answer:

A4.07 Ability to manually operate and/or monitor in the control 2.9 2.9 room: (CFR 41.7 / 45.5 to 45.8): Lights and alarms CRP 9-6 Alarm D-4 "Atmos DRN Tk LVL Hi/Lo" is in alarm. Main condenser vacuum is slowly degrading.

When you direct the TB A 0 to investigate, in your prejob brief would tell him to expect:

I valve stuck oDen.

c. Tank Level Low, and the level control valve stuck shut.

d. Tank Level High, and the level control valve stuck shut.

Justification Correct Response - This event has happened at the plant and operators had difficulty diagnosing it. When the level control valve sticks open, the tank level goes Low and allows air to be drawn into the main condenser. A R S 9-6-D-4 discusses how to fail the LCV shut and stop the loss of vacuum.

Incorrect - When the tank overfills, vacuum is not affected.

Incorrect - The LCV sticking shut will overflow the tank - vacuum will not be affected.

Incorrect - These conditions are possible, but main condenser vacuum will not be affected.

References:

ARS 9-6-D-4, rev 3 New Task Associations 2567190401 Respond to Low Level Alarm in Atmosphere Drain Tank System

Static Simulator Exams: None Last Revised: 09/16/2003 1:03:02 PM by Brown, Scott T.

SRO NRC Exam 2003 290001 Question No. 64 Exam Bank Question No.: 5677 Revision: 1 Point Value: 1 Objective: A 0 3, CRO 3,5 SRO Only: No Instructor Guide: LOT-01-288 Question Level: Comprehension Select the correct answer:

2.1.30 Ability to locate and operate components, including local 3.9 3.4 controls (CFR 41.7,45.7)

The CRS has directed you to restart reactor building ventilation in accordance with OP 2192. To perform this task the reactor building exhaust fan control switch must be held in the "on" position for approximately seconds to allow for the startup of the AnswerD istractor I d. 120, transfer fans Justification 1

Incorrect - The transfer fans do not experience this time delay.

Incorrect - 20 seconds is too long, something: is not working: correctlv.

Correct Response - VYN has had many events (ER 960321 OP Ref) where these controls were not properly set or operated incorrectly. The time delay allows for relay timing, pneumatic damper positioning --> making up limit switches allowing fan start. Once the exhaust fan starts, the whole sequence occurs again with the sumlv fan.

Incorrect - 20 seconds is too long, something is not working correctly.

References:

OP 2192, rev 30, page 27 New Task Associations Task Number Task Title 2887210401 Respond to a Loss of Reactor Building Ventilation Static Simulator Exams: None Last Revised: 09/16/2003 1:04:12 PM by Brown, Scott T.

SRO NRC Exam 2003 290002 Ouestion No. 65 Exam Bank Question No.: 5678 Revision: 2 Point Value: 1 Objective: CRO 1, FND 3 SRO Only: No Instructor Guide: LOT-04-215 Question Level: Fundamental KnowledgeA4emox-y Select the correct answer:

K1.19 Knowledge of the physical connections andor cause-effect 2.5 2.6 relationships between REACTOR VESSEL INTERNALS and the following: (CFR 41.2 to 41.9 / 45.7 to 45.8): TIP By station procedure Op 2425 inter-calibration of the three TIP units is accomplished by:

References:

OP 2425 USAR rev 18 7.5.9.2.2 LOI-EB # 1912 Task Associations Task Number Task Title 21 50230101 Operate the Neutron Monitoring System Static Simulator Exams: None Last Revised: 09/16/2003 1:06:00 PM by Brown, Scott T.

SRO NRC Exam 2003 Question No. 66 Exam Bank Question No.: 5679 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-302 Objective: CRO 2 Question Level: Fwidamental Knowledgehlemory Select the correct answer:

You are performing a plant startup IAW OP 0105 and come to a step with an asterisk (*) at the end.

This asterisk means this is a:

AnswerDistractor Check sheet sign off required by an on shift RO licensed operator only.

check sheet sign off required by any on shift licensed operator.

Check sheet sign off required by an on shift SRO licensed operator only.

Chemistry hold point that requires contacting: the on shift Chemistrv Tech Justification 2

Incorrect -

Correct Response - Start-up check sheet sign offs are identified by asterisks following steps that operators must sign for when performing.

Incorrect -

Incorrect -

References:

LOT-01 -400 CRO Obj. 1 OP 0105, rev 10, Page 14 of 137 New Task Associations 2017400201 2990060301 Perform Heating and Pressurization of the Reactor Maintain Required Logs, Records, Charts, Printouts and Status Boards Knowledne and Abilities Associations Ability to make accurate, clear and concise logs, recordsm, status boards. and reDorts (CFR 45.12.45.13)

Static Simulator Exams: None Last Revised: 09/16/2003 1 : 1 1 :29 PM by Brown, Scott T.

SRO NRC Exam 2003 Question No. 67 Exam Bank Question No.: 5680 Revision: 3 Point Value: 1 SRO Only: No Instructor Guide: LOT-03-400 Objective: CRO 1 Question Level: Fundamental KnowledgeMemory Select the correct answer:

The reactor has been manually scrammed due to the loss of EPR and MPR. The CRS directs you to control reactor pressure 800-1000 psig using the Bypass Opening Jack (BPOJ), before the SRVs lift again.

DP 0166 allows operation of the bypass opening jack( BPOJ):

Correct Response - DP 0166 states this action can be performed fkom memory post scram. If the operator takes the time to

References:

DP 0166, rev 7, page 6 New Task Associations 2000330501 Respond to a Reactor SCRAM Static Simulator Exams: None Last Revised: 09/18/2003 7:06: 15 PM by Brown, Scott T.

SRO NRC Exam 2003 Ouestion No. 68 Exam Bank Question No.: 5681 Revision: 2 Point Value: 1 SRO Only: No Instructor Guide: LOT-01-400 Objective: CRO 3 Question Level: Fundamental KnowledgeMemory Select the correct answer:

You are relieving the reactor operator during power operation and have not been on shift for 20 days. The "A" EDG is out of service due to cylinder failure several days ago.

To determine when the failure occurred, you would review the current copy of:

VYAPF 0152.01 Control Room Shift Turnover Check List VYAPF 0152.02 Tech Spec/TRM Components Inoperable Check List VYAPF 0152.03 Shift Briefing Check List VYAPF 01 52.04 Control Room Turnover Sheet Justification Incorrect -

Correct Response - 0152.02 requires logging date & time. Tech Spec equipment is declared inoperable.

Incorrect -

Incorrect -

I

References:

OP 0152, rev 22 New Task Associations Task Number Task Title 2990030301 Conduct Shift and Relief Turnover Knowledge and Abilities Associations Static Simulator Exams: None Last Revised: 09/16/2003 1 : 15:03 PM by Brown, Scott T.

SRO NRC Exam 2003 Ouestion No. 69 Exam Bank Question No.: 5682 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-402 Objective: CRO 2,3 Question Level: Fundamental Knowledgeklemory Select the correct answer:

Due to a failed vibration switch, the RECIRC PUMP MOTOR A VIBR HI annunciator (4-C-7) is in constant alarm and has been disabled. It is anticipated the annunciator will remain disabled for 15 months until the next refueling outage.

Which one of the following is correct regarding the disabled annunciator?

AnswedDistractor A Temporary Modification (TM) will be written for this configuration change and will require PORC review after six months.

A Minor Modification (MM) will be written for this configuration change and will require PORC review after six months.

A Temporary Modification (TM) will be written for this configuration change and will require PORC review after twelve months.

A Minor Modification (MM) will be written for this configuration change and will require PORC review after twelve months.

Justification Correct Response - OP 3140/AP 0020 Incorrect -

Incorrect -

Incorrect -

References:

AP 0020, rev 25, page 8 OP 3 140, rev 17, page 4 LO1 EB #327 1, modified Task Associations ask Number Task Title 34101 10302/0 Approve Temporary Modifications 3

Knowledge and Abilities Associations I system ~ W A NO. I Statement IRO ISRO)

0 Static Simulator Exams: None Last Revised: 07/02/2003 3:23:25 PM by Hallonquist, Nora E.

2.2.1 1 Knowledge of the process for controlling temporary 2.5 3.4 changes (CFR 41.10,43.3,45.13)

SRO NRC Exam 2003 Question No. 70 Exam Bank Question No.: 5683 Revision: 1 SRO Only: No Question Level: Fundamental KnowledgeMemory Point Value: 1 Instructor Guide: LOT-02-201 Objective: CRO la, b, 7 Select the correct answer:

You are performing control rod coupling checks IAW OP 41 1 1, Section C (VYOPF 41 1 1.03), on a control rod at position 48 prior to a reactor startup.

To perform this check you must:

References:

OP 41 11, rev 39, page 12 New Task Associations 201 7130201 Perfonn Nuclear Instrumentation Response and Coupling Integrity Verification - First Withdrawal Knowledge and Abilities Associations including operating those controls associated with plant equipment that could affect reactivity (CFR 45.1)

Static Simulator Exams: None Last Revised: 08/12/2003 3:39:03 PM by Hallonquist, Nora E.

SRO NRC Exam 2003 Ouestion No. 71 Exam Bank Question No.: 5684 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-271 Objective: CRO 5 Question Level: Fundamental Knowledge/Memory Select the correct answer:

A valid off gas Hi-Hi radiation alarm has been in for 35 minutes on RAN-OG-3 127 and 3 128 (Final Delay Line Inlet Monitors).

You must confirm the closure of:

References:

OP 2150, rev 27, page 6 LO1 EB #71, modified Task Associations 2007090501 Respond to High Off-Gas Radiation Knowledee and Abilities Associations

- ~ _ _..

I System I WA NO. I Statement IRO ISRO]

10 12.3.1 1 I Ability to control radiation releases (CFR 45.9,45.10)

I 2.7 1 3.2 I Static Simulator Exams: None Last Revised: 08/12/2003 3:39:32 PM by Hallonquist, Nora E.

SRO NRC Exam 2003 0

Question No. 72 Exam Bank Question No.: 5685 Revision: 4 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-602 Objective: CRO 3 Question Level: Comprehension Select the correct answer:

2.3.10 Ability to perfom procedures to reduce excessive levels of 2.9 radiation and guard against personnel exposure (CFR 43 -4.45.10) 3.3 A reactor startup is in progress. The reactor is critical and reactor pressure is 300 psig. Main Condenser backpressure is 15" Hg Abs. A high worth control rod which was stuck at position 00 drops to position 46.

You should confirm automatic closure of:

I Answer/Distractor

a. MSIVs and recirc sample valves

b. MSIVs, main steam drains, and recirc sam le valves Hogger discharge valve, steam packing.

ex haus ter suction valves ster discharge valves Justification Incorrect - This isolation was removed in 2002.

Incorrect - This isolation was removed in 2002.

Incorrect - SPE have no suction valves.

Hogger discharge valve is manual valve -

no auto closure Correct Response - Tech Spec Amendment 212, Plant Design Change, removed the MSIV isolation in the fall of 2002. OT 3112

References:

OT 3 1 12 rev 14, page 5 New Task Associations 2007 100501 Respond to Fuel Element Failure Knowledge and Abilities Associations I System 1 WA No. I Statement IRO ISRO]

Static Simulator Exams: None Last Revised: 09/16/2003 1:17:27 PM by Brown, Scott T.

SRO NRC Exam 2003

d.

Question No. 73 Exam Bank Question No.: 5686 Revision: 3 Point Value: 1 SRO Only: No lnstructor Guide: LOT-00-610 Objective: CRO 3 Question Level: Fundamental KnowledgeMemory

• • • • • • • • • • • • • • • • x*************************************************************

Select the correct answer:

Excessive hydrodynamic loading on downcomer during RPV/ED If torus temperature or RPV pressure can not be maintained below the Heat Capacity Temperature Limit Curve (HCTL), then EOP-3 Primary Containment Control, requires RPV/ED.

This action is performed to avoid:

I Answer/Distractor Overpressurizing the Primary Containment during RPVLED Justification Incorrect -

Incorrect -

Correct Response Incorrect -.

References:

EOP Vol4, rev 11, Ch 13.7 LOI-EB # 2226 Task Associations 2000200501 Respond to ATWS Event(s)

Knowledee and Abilities Associations Static Simulator Exams: None Last Revised: 09/16/2003 2:06:42 PM by Brown, Scott T.

SRO NRC Exam 2003 Ouestion No. 74 Exam Bank Question No.: 5687 Revision: 1 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-607 Objective: CRO 2,3 Question Level: Comprehension Select the correct answer:

A small LOCA has occurred. Conditions are listed below. No operator actions have been taken.

Reactor pressure 800 psig and slowly lowering Reactor level 100 and steady Drywell temperature 240°F and slowly rising Drywell pressure 11 psig and slowly rising Torus pressure 11 psig and slowly rising Torus air temperature 236°F and slowly rising Torus level 1 1.60 feet and slowly rising Torus water temperature 9 1 OF and slowly rising The crews priority should be:

I AnswerDistractor primary containment has failed.

heat capacity of the torus will be Dressure sumression Dressure.

Justification Incorrect -

I Correct Response - Torus air temperature -

140°F above torus water temperature indicates the pressure suppression function has failed and sprays are required to Drevent containment failure.

Incorrect -

Incorrect -

References:

EOP-3, rev 1 1, Study guide Page 8-4 New Task Associations Task Number Task Title 2000190501 2000210501 2000230501 Respond to High Torus Water Temperature Respond to High Drywell Temperature Respond to High Torus Water Level

Knowledee and Abilities Associations 0

1 system l y w ~

NO. I Statement IRO ISROI 2.4.23 Knowledge of the bases for prioritizing emergency 2.8 3.8 procedure implementation during emergency operations (CFR41.10,45.13)

Static Simulator Exams: None Last Revised: 07/29/2003 12:24:3 1 PM by Hallonquist, Nora E.

SRO NRC Exam 2003

c.

d.

Ouestion No. 75 Exam Bank Question No.: 5688 Revision: 0 Point Value: 1 SRO Only: No Instructor Guide: LOT-00-622 Objective: CRO 4 Question Level: Fundamental Knowledge/Memory Select the correct answer:

red, above and below it yellow, above and below it Incorrect -

Incorrect -

An EOP override is identified by a box, and applies to all steps within the procedure leg.

References:

VY EOP Users Guide, rev 1 New Task Associations Task Number Task Title 2000200501 Respond to ATWS Event(s)

Knowledge and Abilities Associations 141.10,45.13)

Static Simulator Exams: None Last Revised: 07/25/2003 12:58:32 PM by Hallonquist, Nora E.

SRO NRC Exam 2003 Question No. 76 Exam Bank Question No.: 5689 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-05-215 Objective: SRO 1 Question Level: Analysis Select the correct answer:

The A & B Recirc pumps are operating when the "A" pump trips. Parameters are as follows:

"B" Loop Drive flow B Loop Jet Pump flow A Loop Jet Pump flow Delta W = 0 19,700 gpm 18 mlb&

2 mlb&

"A" Loop Drive flow 0 a m The APRM scram setpoint is less than or equal to under these conditions

a.

b.

d.

Answer/Distractor 54.0%

67.2%

74.0%

81.5%

Justification Incorrect - This answer is plausible if the operator assumes a complete loss of the flow simal.

Incorrect - This answer is plausible if the operator believes the Jp flow provides the flow bias signal:.66(W-deltaW) + 54 =

.66(18-2'1+ 54 Correct Response -.66(W-deltaW) + 54 =

bias scram uses recirc drive flow signal

.66(19700/65000 - 0) = 74% APRM flow Incorrect -.66(W-deltaW) + 54 =.66(20) +

54

References:

LO1 EB #1377 modified T.S. Table 3.1.1 Task Associations Task Number Task Title 3 1071 90302/0 Direct Response to Recirc Pump Trip 3

Knowledge and Abilities Associations I295001 I AA2.02 I Ability to determine and/or interpret the following as they I 3.1 I 3.2 I

apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:(CFR 41.10,43.5,45.13):

Neutron monitoring Static Simulator Exams: None Last Revised: 08/19/2003 4:00:57 PM by Hallonquist, Nora E.

SRO NRC Exam 2003 295004 Ouestion No. 77 Exam Bank Question No.: 5690 Revision: 1 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-601 Objective: SRO 8 Question Level: Analysis Select the correct answer:

AA1.01 Ability to operate and/or monitor the following as they 3.3 3.4 apply to PARTIAL OR COMPLETE LOSS OF D.C.

The HPCI system is operating in full flow test for surveillance. CRP 9-8-N-2 "Batt chg faiVDC-1 GND" has been cycling in and out since HPCI was started.

The probable cause for the ground is the:

HPCI Aux Oil Pump, HPCI surveillance can continue.

HPCI Exhaust Blower, HPCI surveillance can continue.

HPCI Condensate Pump, HPCI should be secured.

HPCI MOV 14 valve, HPCI should be secured.

Justification Incorrect - The HPCI aux oil pump starts on system startup and shuts down based on pressure supplied by the attached lube oil Incorrect - The HPCI exhaust blower runs continuously when HPCI runs - will not cycle.

Correct Response - The condensate pump cycles on hotwell level - on-off-on, etc. It is the probable cause of the ground which if left unattended could degrade to a fault and a loss of DC Dower.

p p

Incorrect - MOV 14 stroked open and remains deenergized for the HPCI run -

will not cvcle.

References:

LOT-00-203 CRO 8c, SRO OP 2145, rev 24 A R S 9-8-N-2, rev 5 New Task Associations

, Task Number Task Title 2637090401 Respond to a DC Ground

POWER: (CFR 41.7,45.6): D.C. electrical distribution systems Static Simulator Exams: None Last Revised: 09/16/2003 2: 1152 PM by Brown, Scott T.

SRO NRC Exam 2003 295018 Question No. 78 Exam Bank Question No.: 5691 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-601 Objective: SRO 8 Question Level: Fundamental Knowledgeklemory Select the correct answer:

AA2.04 Ability to determine and/or interpret the following as they 2.9 2.9 apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:(CFR 41.10,43.5, 45.13): System flow The plant is operating at fill power when CRP 9-4-C-5 ' ' P u p Motor A CLG WTR Flow Lo" alarms (Recirc Pump). As the CRS you would direct:

I a. I an A 0 to the northeast corner room to I Incorrect - The core spray spargers have I

check local indications.

s, which can only be seen in

References:

A R S 9-4-C-5, rev 5 New Task Associations

,Task Number Task Title 4

3440380302/0 Direct Shift Personnel Actions to Ensure Plant Safety During off Normal 3

Conditions Static Simulator Exams: None Last Revised: 09/16/2003 2:14:27 PM by Brown, Scott T

SRO NRC Exam 2003

a.

b.

Ouestion No. 79 Exam Bank Question No.: 5692 Revision: 1 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-601 Objective: SCRO (CRS) 5,7 Question Level: Comprehension Select the correct answer:

Main Steam Lines, RPV bottom head Main Steam Lines. RPV beltline Shutdown cooling has been lost due to an electrical fault on RHR 17 MOV which destroyed the valve stem.

Primary containment is open Reactor head is on Reactor coolant temperature is 195°F and increasing RHR A pump is running - Torus suction and discharging to the reactor SRV A is open RHR B pump is running - Torus cooling and torus In this lineup reactor pressure must be maintained < 250 psig to protect the temperature must be maintained > 80°F to protect the Justification Incorrect -

Incorrect -

Incorrect -

Correct Response - ON 3 156, page 8; Tech Specs 3.6.A.3, bases page 138, last paragraph, Figure 3.6.1

References:

ON 3156, rev 6, page 8 Tech Spec 3.6 New Task Associations 2000150501 Respond to a Loss of Shutdown Cooling Knowledge and At lities Associations COOLING: (CFR 41.7,

Static Simulator Exams: None Last Revised: 07/3 1/2003 10:25:45 AM by Hallonquist, Nora E.

SRO NRC Exam 2003

d.

RPV-ED and enter RPV Flooding.

Ouestion No. 80 Exam Bank Question No.: 5693 Revision: 3 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-614 Objective: SRO 1 Question Level: Analysis Select the correct answer:

The "A" Main Steam Line is leaking in the drywell. The following plant conditions exist.

All control rods are in Drywell temperature is 285°F and rising Drywell pressure is 3.0 psig and rising Drywell RRUs have been restarted Reactor water level is 145" Reactor pressure is 920 psig Torus level is 11 ft As the CRS you should order:

I 1 Answer/Distractor

References:

EOP-3, rev 3 New EOP-3 is required for student reference.

Task Associations Justification Incorrect - Drywell sprays are not allowed, UNSAFE on the DWSIL curve Incorrect - Drywell sprays are not allowed, UNSAFE on the DWSIL curve Correct Response - RPV-ED is required because drybell temperature cannot be restored to < 280OF.

Incorrect - RPV Flooding is not required.

Must determine still safe on RPV Level Instrument Saturation Curve at SRV reclosing pressure of 50 psig.

I Task Number Task Title 200021 0501 Respond to High Drywell Temperature Knowledge and Abilities Associations

I System I K/A NO. I Statement IRO ISROI 295024 EA2.02 Ability to determine and/or interpret the following as they 3.9 4.0 apply to HIGH DRYWELL PRESSURE:(CFR 41.10, 43.5,45.13).: Drywell temperature Static Simulator Exams: None Last Revised: 08/19/2003 3:55:49 PM by Hallonquist, Nora E.

SRO NRC Exam 2003

b.

Question No. 81 Exam Bank Question No.: 5694 Revision: 0 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-602 Objective: SRO 6 Question Level: Comprehension Select the correct answer:

OT 31 15, Low Reactor Pressure, if unsuccessful in controlling pressure with EPR and MPR. scram the reactor.

A plant startup is in progress. Reactor power is 398 MWT and plant loads are on the Auxiliary Transformer. Reactor pressure is 930. The CRO reports EPR Stroke is failing to zero.

As the CRS you should direct:

raise on EPR to raise reactor pressure, if unsuccessfid, cutout EPR, if unsuccessful with MPR, scram the reactor.

Justification*

Incorrect - Not allowed to exceed 25%

CTP with a pressure regulator out of service Incorrect - Wrong procedure, misdiagnosed Correct Response - Must diagnose that lowering EPR Stroke causes high reactor pressure. OT 3 1 16 directs EPR cutout, and MPR setpoint lowered. When operating 25% RTP thermal limits are suspect, proceeding > 25% is not allowed. 398 MWT = 25% CTP, Thermal Limits compliance is required to satisfy Tech SDecs Incorrect - Wrong procedure, misdiagnosed

References:

OT 31 16, rev 8 OP 0105 New Task Associations Task Number Task Title 2000180501 Respond to High Reactor Pressure 3440420302/0 Direct Corrective Actions to Mitigate the Consequences of an Off Normal 3

Event

apply to HIGH REACTOR PRESSURE:(CFR 41.10,43.5, 45.13).: Reactor power Static Simulator Exams: None Last Revised: 08/19/2003 3:54:03 PM by Hallonquist, Nora E.

SRO NRC Exam 2003 L

Question No. 82 Exam Bank Question No.: 5695 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-614 Objective: SRO 1 Question Level: Comprehension Select the correct answer:

141.6,45.4)

An earthquake has caused an LNP and a crack in the torus. Plant conditions are as follows:

REV level band 127"- 177" RFV pressure is 100 psig and lowering A & B RHR Loops in torus cooling Toms level is 8 ft lowering CS "A" is injecting at 1000 gpm As the CRS you should direct torus temperature monitored on:

a. ERFIS - average torus water temperature

b. CRP 9-3 TI-19-33C torus water I

I temnerature k m R F I S - Points M062kl064 (RHR heat w**> I

d. I CRP 9-47 TR-16-19-40 Torus water I

I temnerature Justification Incorrect -

Incorrect -

Correct Response - ERFIS average torus temperature is preferred but at this torus level the detectors are monitoring torus air space temperature and not water temperature. The EOP Study Guide directs monitoring of points M062M064.

Incorrect -

References:

LOT-00-614, SRO 1 EOP Study Guide, rev 1 1, page 8-6 New Task Associations Task Number Task Title 2000190501 Respond to High Torus Water Temperature Knowledee and Abilities Associations

Static Simulator Exams: None Last Revised: 0911 8/2003 7: 12:Ol PM by Brown, Scott T.

SRO NRC Exam 2003 Ouestion No. 83 Exam Bank Question No.: 5696 Revision: 1 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-603 Objective: SRO 4 Question Level: Comprehension Select the correct answer:

A large fire is burning on the Turbine Building roof. Light smoke is entering the control room.

As CRS you should direct:

1 Shutdown Methods.

cable vault or switchgear rooms that cause a loss of control room habitability/hctionality.

Incorrect - Shutting down Turbine

b. OP 2 192, Shutdown Turbine Building

References:

OP 2192, rev 30, Section J.2.a, Discussion Section page 4 New Task Associations 3447020302/0 Call in Off Site Fire Department 3

Static Simulator Exams: None Last Revised: 07/25/2003 1 :06:24 PM by Hallonquist, Nora E.

SRO NRC Exam 2003 Ouestion No. 84 Exam Bank Question No.: 5697 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-308 Objective: SCRO 1 Question Level: Fundamental KnowledgeMemory Select the correct answer:

The reactor coolant system pressure safety limit is based on the and will not be exceeded during the design basis overpressure transient with SRV(s) out of service.

References:

LOT-00-239, SCRO 1 T.S. 12, rev 160, page 19 T.S. 3.6, rev 196, page 142 New Task Associations Task Number Task Title 2000180501 Respond to High Reactor Pressure Static Simulator Exams: None Last Revised: 08/12/2003 3:47:17 PM by Hallonquist, Nora E.

SRO NRC Exam 2003 Question No. 85 Exam Bank Question No.: 5698 Revision: 4 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-610 Objective: SRO 3,4 Question Level: Comprehension Select the correct answer:

A high reactor water level transient has occurred. Reactor water level is 250". MSIVs are shut.

All high pressure injection sources are secured. Operators are attempting to control pressure with SRVs. From CRP 9-3, it appears that the SRVs are not responding to the manual actuations. No tailpipe pressure switch actuations. Pressure control is sluggish and remains >

1055 psig.

In accordance with station procedures you should direct as a minimum:

b.

C.

SRV operations to stop, RPV head vents used for pressure control.

SRV operations to stop, RPV head vents used for pressure control, and RWCU started in the letdown mode.

SRV tailpipe temperatures and primary containment parameters monitored.

SRV tailpipe temperatures and primary containment parameters monitored, k d RWCU started in the letdown mode.

Justification

~

~~

~

Incorrect - RPV head vents are not allowed to be used for RPV pressure control under these conditions.

Incorrect - RPV head vents are not allowed for RPV pressure control under these conditions.

Incorrect - Allowing continued SRV operations with flooded steam lines increases the potential for tailpipe damage.

Actions must be taken to drain the main steam lines.

Correct Response - OP 3 1 14 requires primary containment parameters to be monitored when SRVs are opened with flooded steam lines. SRV tailpipe pressure switches may not indicate open SRVs when the steam lines are flooded. OT 31 14 directs monitoring tailpipe temperatures. EOP-1 pressure control leg directs use of RWCU in letdown if not fuel failure exists. This action will also lower RPV water level and reduce the potential for damage to SRV tailpipes.

References:

OT 3 114, rev 12 EOP-1 rev 2 1/26/2000 Plant Hatch event

New Task Associations: 2000060501 Respond to high reactor water level Knowledge and Abilities Associations operate the facility between shutdown and designated Dower levels (CFR 45.2)

Static Simulator Exams: None Last Revised: 09/16/2003 4:45:53 PM by Brown, Scott T.

SRO NRC Exam 2003 Ouestion No. 86 Exam Bank Question No.: 5699 Revision: 1 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-615 Objective: SRO 1 Question Level: Comprehension Select the correct answer:

Reactor pressure is being controlled manually with SRVs. When the third SRV is opened a step increase in Primary Containment pressure occurs. Drywell pressure remains greater than torus pressure.

As the CRS you must order:

Answer/Distractor ltBtt SRV to remain shut, due to a tail pipe vacuum breaker failure "C" SRV to remain shut, due to a tail pipe vacuum breaker failure "B" SRV to remain shut,due to a tail pipe break in the torus air mace "C" SRV to remain shut, due to tail pipe break in the torus air mace Justification Correct Response - OP 2122 requires SRVs to be opened in sequence a,c,b,d.

"B" is the third SRV to be opened. The student must know this from memory. The student must then determine where the piping from the SRV to below the torus water line has failed by analyzing Primary Containment response. Drywell pressure remaining above torus pressure indicates the pressure suppression function is working and that the failure must be in the d w e l l.

Incorrect -

Incorrect -

Incorrect -

References:

P&ID G191167,191156 Clinton NRC 2000 MODIFIED Task Associations 2000070501 Knowledge and Abilities Associations Respond to Containment Hi Pressure

295010 AA2.02 Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE:(CFR 41.lo, 43.5,45.13): Drywell pressure Static Simulator Exams: None Last Revised: 09/16/2003 2:35:35 PM by Brown, Scott T.

3.8 3.9

SRO NRC Exam 2003 295034 1

EK3.02 Knowledge of the reasons for the following remonses as 4.1 4.1 Ouestion No. 87 Exam Bank Question No.: 5700 Revision: 1 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-261 Objective: SRO 1 Question Level: Fundamental KnowledgeMemory Select the correct answer:

Which of the following is the basis for the automatic initiation of SBGT on reactor building ventilation exhaust high radiation levels?

AnswerDistractor Provides for the maintenance of a positive pressure in the secondary containment, therefore preventing any of the fission products released into the containment from being released into the environment Provides for the cleanup of the secondary containment atmosphere, allowing personnel entry into the secondary containment during a DBA LOCA Provides for the recirculation of the secondary containment atmosphere without exhausting air outside of containment Provides for the filtration of the secondary containment atmosphere of radionuclides prior to their release into the environment, maintaining off site releases within limits Justification Incorrect -

Incorrect -

Incorrect -

Correct Response

References:

OP 21 17, rev 17, page 1 Tech Spec 3.7 Bases Grand Gulf 1 1998 NRC Task Associations Task Number Task Title 341 0320302/0 Evaluate Plant System Performance and Coordinate Appropriate Actions 3

per Technical Specifications/TRM/ODCM in the Event A Limiting Condition for Operation is Entered or not Satisfied Knowledge and Abilities Associations

they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION: (CFR 41.5,45.6):

Starting SBGTERVS: Plant-specific Static Simulator Exams: None Last Revised: 08/19/2003 3:49:54 PM by Hallonquist, Nora E.

SRO NRC Exam 2003 Question No. 88 Exam Bank Question No.: 5701 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-205 Objective: SCRO 1 Question Level: Analysis Select the correct answer:

The reactor has been shutdown for 20 days. Shutdown cooling is in service. Parameters are as follows:

Reactor level 160" for I&C Surveillances Reactor coolant temperature is 95°F SDC flow is 4500 gpm Under these conditions, thermal stratification:

AnswerlDistractor will not occur. Flow may be lowered to 1 100 gpm before stratification is a concern.

will occur. OP 2124 directs flow raised to a minimum of 5500 gpm.

will not occur. Flow may be lowered to 4100 gpm.

will occur. OP 2 124 directs flow raised to 6700 gpm.

Justification Incorrect - 1100 gpm is the RHRSW Pump min flow limit, not a thermal stratification limit.

Incorrect - 4100 gpm is for pump min flow concerns, not thermal stratification. OP 2124 has no 5500 gpm limit.

Incorrect - Thermal stratification will occur under these conditions and that is why the procedure does not allow oDeration here.

Correct Response - OP 2124

References:

OP 2124, rev 50, Precaution #37 GESIL 357 Task Associations 2057970101 Swap Shutdown Cooling Loops Knowledge and Abilities Associations

use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

I (CFR 41.5 / 45.6): Inadequate system flow Static Simulator Exams: None Last Revised: 09/16/2003 2:37:06 PM by Brown, Scott T.

SRO NRC Exam 2003 AnswerDistractor c

a. do, RHRSW

b. do not, RHRSW

c. do, HPCI

d. do not, HPCI Question No. 89 Exam Bank Question No.: 5702 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-614 Objective: SRO 1,2 Question Level: Analysis Select the correct answer:

Justification Incorrect - Not safe on NPSH curve Correct Response - NPSH is not satisfied under these conditions.

Incorrect - HPCI can not be run with torus level < 7 A:

Incorrect - HPCI can not be run with torus level < 7 ft An earthquake has caused a breach of the reactor coolant system and the torus.

RPV-ED is complete "A" Core Spray is injecting at 3500 gpm Torus level is 6 ft RPV level is -30" and steady Torus temperature is 185'F "A" and "B" RHR are running in torus cooling Torus pressure is 4 psig You meet the NPSH requirements for the Core Spray Pump and by procedure can be used to makeup to the torus.

References:

LOT-00-6 10, SRO 3 EOP-1, rev 2 EOP-3, rev 3 EOP Study Guide 13.18, rev 1 1 EOP App T & X, rev 16 New Student required reference: EOP-1, EOP-3 Task Associations 2000240501 2000310501 Respond to Low Torus Water Level Respond to Low Reactor Water Level

Knowledge and Abilities Associations System I WA No. I Statement bIR0 ISROI 209001 3 - 3 1 A2.09 Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those predictions, use procedures to correct, 3.1 I

I control, or mitigate the consequences of those abnormal I

I I

I I conditions or operations: (CFR 41.5 / 45.6): Low I

l l

I suppression pool level Static Simulator Exams: None Last Revised: 09/16/2003 2:39:00 PM by Brown, Scott T.

SRO NRC Exam 2003 Question No. 90 Exam Bank Question No.: 5703 Revision: 0 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-223 Objective: SRO 3 Question Level: Comprehension Select the correct answer:

A plant shutdown is in progress to repair a recirc pump seal leak. Reactor power is 6%. The drywell is being purged through the 18" line to allow early primary containment entry.

This mode of operation is allowed by Technical Specifications for per calendar year. This restriction assures the integrity of the Tech Spec, must also understand the concept that on a LOCA SBGT 2A/B open before the primary containment isolation valves can stroke shut. This event has the potential to rupture both SBGT trains and make secondary containment unavailable.

By limiting the time the 18" valves are

References:

Tech Spec Bases, rev 197, page 165/166, Section 3.7 OP 21 15, rev 43, page 4 New Task Associations 3410320302/0 Evaluate Plant System Performance and Coordinate Appropriate Actions 3

per Technical Specifications/TRM/ODCM in the Event A Limiting Condition for Operation is Entered or not Satisfied Knowledge and Abilities Associations

Static Simulator Exams: None Last Revised: 07/25/2003 1 : 14:46 PM by Hallonquist, Nora E.

SRO NRC Exam 2003 264000 Ouestion No. 91 Exam Bank Question No.: 5704 Revision: 4 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-264 Objective: SCRO la Question Level: Analysis Select the correct answer:

K6.01 Knowledge of the effect that a loss or malfunction of the 3.8 3.9 following will have on the EMERGENCY GENERATORS (DIESEL/JET): (CFR 41.7 / 45.7):

The plant is operating at full power.The "B" Core Spray pump is inoperable. The "A" EDG air compressor has tripped on thermal overload. Air receiver pressure is 190 psig and slowly lowering. Both receivers are in service. CRP 9-8-E-7 EDG low starting air pressure is in.

For these conditions you should declare the "A" EDG inoperable:

a.

b.

I

d.

AnswerDistractor 1 Justification Immediately, enter a 7 day LCO, and verify the other EDG is operable within 24 Incorrect -

hours.

When receiver pressure is < 150 psig, enter Incorrect -

a 7 day LCO, and verify the other EDG is operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Immediately, and be in cold shutdown in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

When receiver pressure is < 150 psig and be in cold shutdown in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Correct Response Incorrect -

References:

OP 2126, rev 33, Precaution 25 Tech Spec 3.10 New Tech Spec 3.10 is a required student reference Task Associations 341 0320302/0 Evaluate Plant System Performance and Coordinate Appropriate Actions 3

per Technical Specifications/TRM/ODCM in the Event A Limiting Condition for Operation is Entered or not Satisfied Knowledge and Abilities Associations I System I WA NO. 1 Statement

]RO ISROI

Static Simulator Exams: None Last Revised: 09/16/2003 2:43: 15 PM by Brown, Scott T.

SRO NRC Exam 2003 Question No. 92 Exam Bank Question No.: 5705 Revision: 3 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-205 Objective: SCRO 1 Question Level: Comprehension Select the correct answer:

When the A RHR Loop is placed in torus cooling OP 2 124 (FWR) procedure requires a LCO to be entered.

When the second loop of torus cooling is placed in service, a LCO is entered.

These actions reduce the potential challenges to the RPV water level safety limit of inches above top of enriched hel.

by procedure to ensure LPCI availability.

The concern is a loss of power to the torus

References:

Tech Spec 3.7.A.1, rev 192 OP 2124, rev 50, Precaution 41 New Tech Spec 3.7 is a required student reference Task Associations ask Number Task Title 341 0320302/0 Evaluate Plant System Performance and Coordinate Appropriate Actions 3

per Technical Specifications/TRM/ODCM in the Event A Limiting Condition for Operation is Entered or not Satisfied 3440470302/0 Clarify Technical Specifications/TRM/ODCM and Application of Action 3

Statement Requirements Knowledge and Abilities Associations

Static Simulator Exams: None Last Revised: 09/16/2003 2:5 1 :44 PM by Brown, Scott T.

SRO NRC Exam 2003

b.

c.

Question No. 93 Exam Bank Question No.: 5706 Revision: 3 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-233 Objective: SRO 1 Question Level: Fundamental KnowledgeMemory Select the correct answer:

120,150 Incorrect -

140.170 Incorrect -

Refueling is in progress. Shutdown cooling is out of service for MOV testing of RHR 17 & 18.

Fuel pool temperature is 1 18°F and rising. RBCCW cooling has been maximized.

Prior to O F normal &el pool cooling should be secured and standby fuel pool cooling started. Refueling operations tending to raise fuel pool temperature must be stopped when OF is reached.

Id. 1120,170 I Incorrect -

References:

OP 2 1 84, rev 22, Precaution 9 ech Spec 3.12 New Tech Spec 3.12 is a required student reference Task Associations 2337140401 Respond to Fuel Pool Cooling System Alarms 341 0320302/0 Evaluate Plant System Performance and Coordinate Appropriate Actions 3

Knowlec per Technical Specifications/TRM/ODCM in the Event A Limiting Condition for Operation is Entered or not Satisfied ge and Abilities Associations FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or

Static Simulator Exams: None Last Revised: 09/16/2003 2:52:52 PM by Brown, Scott T.

SRO NRC Exam 2003 Question No. 94 Exam Bank Question No.: 5707 Revision: 0 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-308 Objective: SCRO (CRS) 1 Question Level: Fundamental KnowledgeMemory Select the correct answer:

The MSIVs are shut. The reactor is critical in accordance with OP 0105, Appendix A, "Reactor Heatup with the MSIVs Closed."

Which one of the following defines the Tech Spec mode of operation?

I !

AnswerDistractor I Justification 1

References:

Tech Spec definitions New Task Associations Task Number Task Title 341 0320302/0 Evaluate Plant System Performance and Coordinate Appropriate Actions 3

per Technical Specifications/TRM/ODCM in the Event A Limiting Condition for Operation is Entered or not Satisfied Knowledge and Abilities Associations Static Simulator Exams: None Last Revised: 07/25/2003 1 :24:08 PM by Hallonquist, Nora E.

SRO NRC Exam 2003 0

Question No. 95 Exam Bank Question No.: 5708 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-138 Objective: 22,24 Question Level: Analysis Select the correct answer:

2.1.25 Ability to obtain and interpret station reference materials 2.8 3.1 such as graphs, monographs, and tables which contain performance data (CFR 41.10,43.5,45.12)

Core flow is 60%. The recirculation motor generator scope tube mechanical stops are set for 109.5% speed. MCPR Option "A" has been selected based on full core scram times. Core exposure is 11,000 MWd/St. The MCPR operating limit is:

1 : Option A > 10,375 MWd/ST, MCPR =

1.61; From Figure 2.2-1: 60% flow

References:

COLR, rev 0, Cycle 23 Tech Spec New COLR is a required student reference Task Associations

'Task Nurn Task Title 341 0320302/0 Evaluate Plant System Performance and Coordinate Appropriate Actions 3

per Technical Specifications/TRM/ODCM in the Event A Limiting Condition for Operation is Entered or not Satisfied Static Simulator Exams: None Last Revised: 09/16/2003 2:54:41 PM by Brown, Scott T.

SRO NRC Exam 2003 0

2.2.21 Knowledge of pre-and post maintenance operability 2.3 3.5 requirements (CFR 43.2)

Question No. 96 Exam Bank Question No.: 5709 Revision: 0 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-400 Objective: SCRO 3 Question Level: Fundamental KnowledgeMemory Select the correct answer:

RPS "A" System has been tripped for replacement of backup scram relay contacts. The work party has informed the Shift Manager that work is complete and the equipment can be returned to service. The RPS A trip can be reset under to allow the post maintenance testing required to demonstrate its operabiltiy provided that is completed first.

References:

AP 0125, rev 12, Admin Limit 5.2 New Task Associations Task Number Task Title 34201 80302/0 Assist in Evaluating the Progress of Maintenance on Technical 3

Specifications/TRM/ODCM or Safety Related Equipment Static Simulator Exams: None Last Revised: 07/25/2003 1 :26:06 PM by Hallonquist, Nora E.

SRO NRC Exam 2003 Question No. 97 Exam Bank Question No.:

5710 Revision: 1 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-223 Objective: SRO 3 Question Level: Fundamental Knowledgehfemory Select the correct answer:

OP 2 1 15 Figure 2 provides a graph of purge flow rate verses purge time for the drywell and torus. This minimum purge time for a given flow rate:

1, J~nswer/~istractor 1 Justification

References:

OP 21 15, rev 43 New Task Associations Number Task Title 2230020 104 Purge Containment with Nitrogen (Inerting) 34501 501 02/0 Direct PurgeNent of the Containment Building 3

Know1edg.e and Abilities Associations Knowledge of the process for performing a containment t)urge (CFR 43.2.45.10)

Static Simulator Exams: None Last Revised: 07/25/2003 1:26:58 PM by Hallonquist, Nora E.

SRO NRC Exam 2003 0

Question No. 98 Exam Bank Question No.: 571 1 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-404 Objective: SRO 1 Question Level: Analysis Select the correct answer:

2.3.10 Ability to perform procedures to reduce excessive levels of 2.9 radiation and guard against personnel exposure (CFR 43.4,45.10) 3.3 A point source in the reactor building is reading 500 m/hr at a distance of two (2) feet. Two options exist to complete rework on a valve located near this radiation source.

Option 1: Operator X can perform the task in thirty (30) minutes working at a distance of four (4) feet from the point source Option 2: Operators X and Y, who are trained in the use of a special extension tool, can perform the task in seventy five (75) minutes at a distance of eight (8) feet from the point source Which one of the following options is preferable and consistent with the ALARA program?

I AnswerDistractor I a. I Option 1, since X would receive 3 1.25 Option 2, since the exposure per person is 39.06 mRem Option 2, since the exposure per person is 78.12 mRem Justification Incorrect -

Correct Response - Inverse square rule x time x 1 Incorrect -

Incorrect -

References:

LOT-00-059, rev 6, page 5 of 12 Palisades 2001 NRC Task Associations 3430290302/0 Assess Exposure Limits of Personnel for Assigned Duties 3

Knowledge and Abilities Associations

Static Simulator Exams: None Last Revised: 08/19/2003 3:44:38 PM by Hallonquist, Nora E.

SRO NRC Exam 2003 Question No. 99 Exam Bank Question No.: 5712 Revision: 2 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-900 Objective: SRO 1,4 Question Level: Fundamental KnowledgeMemory Select the correct answer:

AT 12:OO the plant experiences a full power ATWS with no control rod motion after initiation of ARI/RPT.

As the Plant Emergency Director (PED) you should classify this event no later than and you should notify outside authorities no later than minutes after the classification is made.

I !

Answer/Distractor I Justification

References:

DP 0093, rev 2, Appendix A page 3 New Task Associations Task Number Task Title 3440170302/0 Analyze Indications to Determine that an Emergency Plan Event is in 3

Progress Knowledge and Abilities Associations I plan implementation (CFR 45.1 1)

Static Simulator Exams: None Last Revised: 07/3 1/2003 10:49:28 AM by Hallonquist, Nora E.

SRO NRC Exam 2003 Question No. 100 Exam Bank Question No.: 5713 Revision: 1 Point Value: 1 SRO Only: Yes Instructor Guide: LOT-00-900 Objective: SRO (CRS) 1,4 Question Level: Fundamental KnowledgeMemory Select the correct answer:

An alert EAL was declared 35 minutes ago. You are the Plant Emergency Director (PED). The Operations Support Center (OSC) and the Technical Support Center (TSC) are manned and have relieved you of your responsibilities. The Emergency Operations Facility (EOF) has not assumed any responsibilities yet.

An escalation to the Site Area Emergency is made by the OSC Coordinator/TSC Coordinator/PED. Who is responsible to notify the states?

' I AnswerDistractor

b. OSC Coordinator

c. TSC Coordinator

d. Site Recovery Manager Justification Correct Resuonse Incorrect - The OSC does not have an NAS Orange phone Incorrect - The TSC does not have an NAS Orange phone Incorrect - The EOF does have an NAS Orange phone but they have not yet assumed responsibility for states notifications.

References:

OP 3540, rev 3, page 5 of 16 Task Associations 3440390302/0 Perform Required Notifications of On Site and Off Site Personnel for Off 3

Normal Events Knowledee and Abilities Associations f System 1 WA No. I Statement IRO ISROl 10 12.4.43 I Knowledge of emergency communications systems and I 2.8 13.5 1

I techniques (CFR 45113)

Static Simulator Exams: None Last Revised: 07/25/2003 1 :30:16 PM by Hallonquist, Nora E.