Text

08-2005 - Initial Draft Written Ro/Sro Exam
	ML053330594
Person / Time
Site:	Palo Verde
Issue date:	08/31/2005
From:	Ryan Lantz; Operations Branch IV
To:	Overbeck G; Arizona Public Service Co
References
	50-528/05-301, 50-529/05-301, 50-530/05-301, ES-401, ES-401-6 50-528/05-301, 50-529/05-301, 50-530/05-301
	Download: ML053330594 (146)
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ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 1

Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 41007EK301 Importance 4.00 4.60 Rating:

Given the following plant conditions:

Unit 1 has tripped.

The following annunciators are in alarm:

CNDS SYS TRBL alarm (5B14A)

"SBCS COND INTLK" alarm (6A16B)

COND VAC LO alarm (6A16D)

The CRS has completed the SPTAs and entered the Reactor Trip Optimal Recovery Procedure.

As the Secondary Operator the CRS informs you to "Check that SBCS is maintaining Tcold 560 -

570°F".

Which ONE of the following describes the action the Secondary Operator should take and the reason?

A. ONLY the ADVs may be used to control steam generator pressure. This action is performed to allow a controlled RCS heat removal process using the steam generators.

B. ALL of the ADVs or SBCS Valves 7 & 8 may be used to control steam generator pressure. This action is performed to allow a controlled RCS heat removal process using the steam generators.

C. ONLY the SBCS Valves may be used to control steam generator pressure. This action is performed to maintain steam generator pressure below the secondary safety setpoints, preventing them from opening.

D. ALL of the ADVs or SBCS Valves may be used to control steam generator pressure. This action is performed to maintain steam generator pressure to prevent the RCS from overheating and lifting the primary safeties.

Answer: B Learning Objective:

0356 Analyze the MVA to determine is the SFSC acceptance criteria is satisfied.

100866 Active Question Bank 2004 Reference Id: Q10264 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40DP-9AP07, pg 12 of 22 OPTRNG_EXAM Page: 1 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam Knowledge of the reasons for the following as they apply to a reactor trip:

Actions contained in EOP for reactor trip The SFSC for Reactor trip requires both 125 Vdc class buses for the same train as the PB bus.

Reactor Trip Technical Guideline Page 12 of 22 40DP-9AP07 Instruction Step: 7 Maintain Tc This step ensures that the RCS heat removal safety function is being satisfied. Following an uncomplicated Reactor Trip RCS Tc should be controlled by the SBCS. The goal is to stabilize RCS Tc and remove decay heat.

Contingency Actions 7.1 If condenser vacuum is lost or if the MSIVs are closed the SBCS valves to the condenser are unavailable. For this case the ADVs or atmospheric SBCS Valves must be used to control steam generator pressure. This action is performed to maintain steam generator pressure below the secondary safety setpoints, preventing them from opening, and to allow a controlled RCS heat removal process using the steam generators.

OPTRNG_EXAM Page: 2 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 2

Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 42008AK201 Importance 2.70 2.70 Rating:

Given the following plant conditions:

PZR pressure is 1900 psig and slowly DECREASING

PZR level is 60% and slowly INCREASING

RCS subcooling is 23°F and DECREASING

A SIAS/CIAS/MSIS have been manually actuated on trend

SG #1 and SG #2 Narrow Range levels are 5% and increasing on both Steam Generators

SG #1 and SG #2 pressures are 1150 and STABLE

Containment pressure is 2.8 psig and slowly INCREASING

Containment temperature is 140°F and slowly INCREASING

Containment humidity is INCREASING

RDT pressure is 1.5 psig and STABLE Which ONE of the following could be the cause of the above conditions?

A. RCS leak from a cold leg B. S/G Safety Valve failed open C. RCS Safety Valve failed open D. Pressurizer steam space leak.

Answer: D Learning Objective:

L10452 Given PZR Safety Valve tailpipe temperatures and the steam tables analyze the data to determine the status of the PZR safety valve 6193004G11 Determine the exit conditions of a fluid for a throttling process.

6193004K115 K1.15 Determine the exit conditions for a throttling process based on the use of steam and/or water Reference Id: Q10268 Difficulty: 3.00 Time to complete: 4 10CFR Category: CFR 55.41 (14) 55.41 (14) Principles of heat transfer thermodynamics and fluid mechanics.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: Steam Tables Technical

Reference:

Steam Tables Knowledge of the interrelations between the Pressurizer Vapor Space Accident and the following: Valves Answer D is correct for the plant conditions given. RDT stable eliminates answers C. SG parameters eliminate answer B. Pressurizer level increase eliminates answer A.

OPTRNG_EXAM Page: 3 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 3

Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 41009EA110 Importance 3.80 3.90 Rating:

Given the following plant conditions:

A LOCA is in progress and the Reactor is tripped.

SPTAs are complete. The CRS is implementing the LOCA ORP.

RVLMS indicates 67% in the upper head and has been constant for the past 10 minutes.

THEN:

The QSPDS B04 indicator for reactor vessel level instantaneously drops to 41% in the upper head and stabilizes for another 10 minutes.

The crew should relate this change in indication with the:

A. sudden increase of the RCS leak rate.

B. RVUH void size has decreased from 67% to 41%.

C. expansion of the void in the vessel head to less than 67%.

D. expansion of the void in the vessel head to less than 41%.

Answer: C Learning Objective:

100866 Active Question Bank 2004 L10460 Given conditions of LOCA discuss the bases of the superheat value given in the Core Heat Removal SFSC L61243 Discuss the bases of the superheat value limit provided in the LOCA EOP.

Reference Id: Q10261 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40DP-9AP08, LOCA Tech Guide Ability to operate and monitor the following as they apply to a small break LOCA: Safety parameter display system C is correct, indicated level is based on heated junction thermocouple uncovery. Indicated level reading drops down to the next thermocouple once it is uncovered.

A, C, & D could be interpreted as correct if a linear relationship increased or if the level system was based on comparing pressure signals.

OPTRNG_EXAM Page: 4 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam Original question ID: Q12403 Points: 1.00 prior to modification Given the following plant conditions:

o A LOCA is in progress and the Reactor is tripped.

o SPTAs are complete. The CRS is implementing the LOCA ORP.

o RVLMS indicates 67% in the upper head and has been constant for the past 10 minutes.

Then:

The B02 indicator for reactor vessel level instantaneously drops to 41% in the upper head and stabilizes for another 10 minutes.

The crew should relate this change in indication with the:

A. sudden increase of the RCS leak rate.

B. sudden decrease of the RCS leak rate.

C. expansion of the void in the vessel head.

D. expansion of the void into the outlet plenum.

Answer: C OPTRNG_EXAM Page: 5 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 4

Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 41011EK101 Importance 4.10 4.40 Rating:

Given the following plant conditions:

A Loss of Offsite power has occurred.

All actions in the SPTAs have been completed.

The CRS has entered the LOCA procedure.

Loop T is 70 °F and STABLE.

Th and Tc are INCREASING.

The T between Th RTDs and the maximum quadrant CETs is 40 °F.

Based on these indications, the operator should perform which of the following?

A. Depressurize the RCS.

B. Establish hot leg injection.

C. Stop any feed or steaming to the SGs.

D. Ensure SG levels are 45-60% NR with proper SG feeding and steaming.

Answer: D Learning Objective:

100866 Active Question Bank 2004 L10471 Given conditions of a LOCA discuss the reactivity effects of a controlled cooldown to SDC conditions L96640 Implement the LOCA EOP L61256 Discuss the reactivity effects of a controlled cooldown to SDC conditions.

L62490 Given a LOCA Event, Tailboard the guidance included in the LOCA Emergency Procedure Technical Guideline.

Reference Id: Q10269 Difficulty: 3 Time to complete: 2 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40DP-9AP08, LOCA Tech Guide Knowledge of the operational implications of the following concepts as they apply to the Large Break LOCA:

Natural circulation and cooling, including reflux boiling D Correct, increasing SG level improves NC driving force.

A, B, & C do not improve NC.

OPTRNG_EXAM Page: 6 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 5

Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 42022AK103 Importance 3.00 3.40 Rating:

Given the following plant conditions:

Unit 1 at 100 % power

Pressurizer level setpoint is 53%

Charging Pump selector switch is in the "1-2-3" position

Pressurizer level is now lowering At which ONE of the following Pressurizer levels would you FIRST expect the E Charging pump to be operating due to an auto start?

A. 19%

B. 29%

C. 38%

D. 43%

Answer: B Learning Objective:

100866 Active Question Bank 2004 L75112 Describe the automatic features associated with the Pressurizer Level Control System operation of the Charging pumps.

Reference Id: Q61101 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (5) 55.41 (5) Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature, pressure and reactivity changes, effects of load changes, and operating limitations and reasons for these operating characteristics.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

Simplified Control System Drawing, PZR Level Control System Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Pump Makeup: Relationship between charging flow and PZR level At -23% from setpoint (53%) decreasing, the standby Charging Pump will auto start (53 -

23 = <30%).

Must know from switch position the order of operation of the E charging pump as the standby pump.

OPTRNG_EXAM Page: 7 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 6

Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 42025AK203 Importance 2.70 2.70 Rating:

Given the following plant conditions:

Unit 2 is shutdown with train "A" LPSI aligned for Shutdown Cooling.

RCS Pressure is 350 psig.

RCS Tave is stable at 330°F.

Which of the following would cause the RCS to heatup?

A. Throttling open on EWA-HCV-135, EWA-P01 discharge valve.

B. Throttling closed on EWA-HCV-53, SDCHX A outlet isolation valve.

C. Throttling open on SIA-HV-685, the SDCHX inlet valve.

D. Throttling closed on SIA-HV-306, the SDCHX bypass valve.

Answer: B Learning Objective:

56506 Given the LMFRP is being performed and HR is in progress outline the major steps used to control Core and RCS heat removal in HR (LMFRP)

Reference Id: Q10191 Difficulty: 2.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

NONE Knowledge of the interrelations between the Loss of Residual Heat Removal System and the following: Service water or closed cooling water pumps Due to throttling down the EW flow the RCS will heatup. All the other distracters will cause a RCS cooldown.

OPTRNG_EXAM Page: 8 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 7

Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 42026AA103 Importance 3.60 3.60 Rating:

Given the following plant conditions:

Nuclear cooling water is experiencing an as yet unexplained low discharge pressure.

Essential Cooling Water Train "B" has been cross-connected to supply priority loads.

No other equipment is out of service or in an abnormal lineup.

Which ONE of the following identifies the plant conditions that will isolate essential cooling water to the reactor coolant pumps?

A. Containment pressure 9.0 psig.

B. Pressurizer pressure 1800 psia.

C. Instrument air header pressure 60 psig.

D. Both Steam Generator pressures at 850 psig.

Answer: A Learning Objective:

L56846 Describe the automatic features associated with the NC Containment Isolation Valves.

N76950 Describe the normal operation of the Essential Cooling Water system.

L65501 Describe the automatic functions associated with the Essential Cooling Water Cross-tie to Nuclear Cooling Water Valves EWA-UV-145 and EWA-UV-65.

L56837 From memory describe the interlocks associated with the Train 'A' EW to NC cross tie valves (EWA-UV-145 and EWA-UV-65)

Reference Id: Q5108 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ17, Inadvertent ESFAS Actuation, Att. C-13 SIAS Train A Ability to operate and / or monitor the following as they apply to the Loss of Component Cooling Water: SWS as a backup to the CCWS Question requires knowledge of the fact that the Train 'B' crosstie valve is manual, and therefore has NO automatic isolations. However, the NC isolation valves are still active when crosstied to either train of EW, and will isolate the system in response to a CSAS on Containment pressure.

OPTRNG_EXAM Page: 9 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 8

Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 42027G2417 Importance 3.10 3.80 Rating:

An event is in progress where RCS pressure drops to the SIAS setpoint. 40EP-9EO01, Standard Post Trip Actions, contingency action 5.2 for success path RC Pressure Control states, "IF Pressurizer Press drops to the SIAS setpoint, THEN ensure that SIAS is actuated."

When used in this situation, which ONE of the following describes what the term 'ensure' mean?

A. To evaluate conditions, inform the CRS and with his approval, take the necessary steps to establish the condition.

B. To evaluate conditions and, if the condition does not exist, manually take the necessary steps to establish the condition.

C. Identify the cause of the problem and report the condition when requested by the CRS to report the status of the RC Pressure Control Safety Function.

D. If the condition does not exist, take action to establish the condition prior to completing the Safety Function Status Checks for the optimal recovery procedure.

Answer: B Learning Objective:

L10422 Given a reactor trip describe the bases for the PZR pressure band (1837 to 2285 psia)

Reference Id: Q10192 Difficulty: 2.00 Time to complete: 2 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Memory Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40DP-9AP15, EOP Writers Guide Knowledge of EOP terms and definitions Answer B is correct because an evaluation of conditions is required before action is taken.

Permission is NOT required if the setpoint is reached or exceeded.

OPTRNG_EXAM Page: 10 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 9

Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 41029EK206 Importance 2.90 3.10 Rating:

Given the following plant conditions:

Unit 1 reactor operating at 101% full power.

Pressurizer pressure 2430 psia and rising.

Manual trip buttons on control board B05 have been depressed and did not trip the Reactor.

All actions inside the Control Room taken at Board 1 to de-energize CEDMCS have been unsuccessful.

Which ONE of the following identifies the next required action for reactivity control? Dispatch an area operator to:

A. Locally open NAN-S01F.

B. Locally de-energize PNA-D25 and PNB-D26.

C. The CEDMCS panels to open individual CEA breakers.

D. Locally open reactor switchgear breakers.

Answer: D Learning Objective:

L10403 Given plant conditions following a reactor trip analyze whether the Reactivity Control Safety Function is met and what contingency actions are required if it is not L91171 Address Reactivity Control Safety Function with two Stuck CEA's 105794 As an operating crew respond to inadvertent MSIV/MSIVs closure L55896 GENERIC EOP KNOWLEDGE Reference Id: Q6847 Difficulty: 2.00 Time to complete: 5 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Memory Question Source: PV Bank Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40DP-9AP06, SPTA Tech Guide Knowledge of the interrelations between the and the following an ATWS: Breakers, relays, and disconnects Answer D is procedurally directed; the action results in a Rx Trip and does not result in loss of power to other equipment.

Distracter B could be interpreted as a course of action to try to minimize the reactivity excursion. This path is not procedurally directed.

OPTRNG_EXAM Page: 11 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam Original question ID: Q6847 Points: 1.00 prior to modification Given the following plant conditions:

Unit 1 reactor operating at 101% full power.

Pressurizer pressure 2430 psia and rising.

Manual trip buttons on control board B05 have been depressed and did not trip the Reactor.

All actions inside the Control Room taken at Board 1 to deenergize the RTSG (Reactor Trip Switch Gear) have been unsuccessful.

Which ONE of the following identifies the next required action for reactivity control?

A. Open Main Generator output breakers.

B. FAST CLOSE the main steam isolation valves.

C. Dispatch Area Operator to locally open NAN-S01F.

D. Dispatch Area Operator to locally open reactor switchgear breakers.

Answer: D OPTRNG_EXAM Page: 12 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 10 Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 2130 Importance 3.90 3.40 Rating:

Given the following plant conditions:

A SGTR has occurred on S/G #1.

A SIAS has initiated.

The CRS has requested that the charging pump suction be realigned.

You have been directed to perform Appendix 10 of the Standard Appendices and align the charging pumps suction to the RWT (Refueling Water Tank).

CHB-HV-530 (RWT outlet to B Train Safety Injection) is open

The A Charging pump is in Pull to Lock.

The Auxiliary operators actions require local operation of the following valves:

o CHB-V327 (RWT to Charging Pump Suction) o CHA-V316 (A - Charging Pump CHA-P01 suction isol valve) o CHA-V755 (A - Charging Pump CHA-P01 alternate suction isol valve)

Which of the following is correct concerning the Area Operators expected local operation?

A. All valves require manual operation and are all located in the Charging Pump A valve gallery.

B. CHB-V327 requires local operation at the associated motor control center (MCC) breaker while CHA-V316 and CHA-V755 require manual operation in the Charging Pump A valve gallery.

C. All valves require manual operation and are located in the 70 ft.

Mechanical Piping Penetration Room.

D. CHB-V327 requires manual operation in the 70 ft. Mechanical Piping Penetration Room and CHA-V316 and CHA-V755 require manual operation in the Charging Pump A valve gallery.

Answer: D Learning Objective:

EGEP013 Given a transient that results in RWT level dropping below 73%, align Charging Pump alternate suctions N64159 Discuss the purpose and strategies of the "Reactivity Control" Safety Function.

N62461 Given the appropriate references discuss and explain the Auxiliary Operator actions for Standard Appendix 11 L89992 As an operating crew Mitigate a SGTR in natural circulation Reference Id: Q2119 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: New OPTRNG_EXAM Page: 13 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40EP-9EO10, Standard Appendices, Appendix 11 Ability to locate and operate components, including local controls Only D is correct due to location and types of valves. CHB-327 is a manual valve.

Not all valves are located in the piping penetration area, neither the charging pump valve gallery.

OPTRNG_EXAM Page: 14 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 11 Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 42040AK103 Importance 3.80 4.20 Rating:

Given the following plant conditions:

Unit 1 tripped from 100% full power.

SPTA's in progress

SIAS, CIAS, MSIS, and AFAS-1 have initiated.

The RCS is in forced circulation.

Steam Generator #1 pressure is 750 psia and dropping rapidly.

Steam Generator #1 level is 8% WR and dropping rapidly

Steam Generator #2 pressure is 940 psia and slowly lowering.

Steam Generator #2 level is 37% WR and slowly lowering.

Auxiliary feedwater flow is > 2000 gpm to steam generator #1.

Auxiliary feedwater flow is 0 gpm to steam generator #2.

RCS Loop 1 Tc is 515 °F and dropping rapidly.

RCS Loop 2 Tc is 538 °F and dropping slowly.

RCS pressure is 1800 and stable.

Which ONE of the following actions correctly addresses the existing symptoms?

A. Stop all RCPs.

B. Maximize SI flow to the RCS.

C. Throttle and balance flow to each steam generator.

D. Stop feeding SG #1 and ensure feedwater flow is restoring level in SG #2.

Answer: D Learning Objective:

L11202 Given conditions of an ESD describe the mitigating strategy outlined in the ESD EOP L61351 Describe the mitigating strategy for an ESD.

L11202 Given conditions of an ESD describe the mitigating strategy outlined in the ESD EOP L62494 Given a ESD Event, Tailboard the guidance included in the ESD ORP.

Reference Id: Q8575 Difficulty: 3.00 Time to complete: 4 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40DP-9AP10, ESD Tech Guide, Step 11 & 20 Knowledge of the operational implications of the following concepts as they apply to Steam Line Rupture: RCS shrink and consequent depressurization OPTRNG_EXAM Page: 15 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam The mitigating strategy is to stop feeding the faulted SG and feed over steam on the non-faulted SG.

Distracters A, B, & C could lead to an uncontrolled cooldown.

OPTRNG_EXAM Page: 16 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 12 Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 42054AA102 Importance 4.40 4.40 Rating:

Given the following conditions:

The CRS has diagnosed a LOAF (Loss of all Feed) with an inadvertent SIAS.

The CRS directs you to start AFN-P01.

The SIAS load shed panels have been re-energized, valve line-ups are complete, and you have indicating lights for AFN-P01.

You have gone to "START" one time using its handswitch (AFN-HS-1).

Which ONE of the following is correct regarding AFN-P01:

A. running and feeding both Steam Generators.

B. running but not feeding either Steam Generator.

C. not running; AFN-P01 will start by going to "START" one more time.

D. not running; AFN-P01 can be started by going to "STOP" then "START".

Answer: D Learning Objective:

L10502 Given conditions of a LOAF and the status of plant equipment determine from where feed can be established L82097 Given conditions of a LOAF, Restore feedwater by Local Operation of AFN-P01 L6138 Analyze plant conditions to determine if feed can be established using AFN-P01 during a LOAF.

Reference Id: Q21227 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

10CFR Category: CFR 55.41 55.41 (10) Administrative, normal, abnormal, and emergency (10)CFR 55.41 (7) operating procedures for the facility.55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

P&ID 01-E-AFB-002 Ability to operate and / or monitor the following as they apply to the Loss of Main Feedwater (MFW): Manual startup of electric and steam-driven AFW pumps AFN-P01 can NOT be started after a SIAS occurs unless taken to override by going to STOP then to START.

OPTRNG_EXAM Page: 17 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 13 Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 41055EA202 Importance 4.40 4.60 Rating:

Given the following plant conditions:

Unit 1 has been in a blackout condition for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

QSPDS indicates 32 degrees superheat and has been stable for the last 15 minutes.

CET temperatures and RCS pressure have also been stable for the last 15 minutes.

Which ONE of the following describes the condition of RCS and core heat removal?

A. All natural circulation has been lost.

B. Only single phase natural circulation is maintaining heat removal.

C. Only two phase natural circulation only is maintaining heat removal.

D. Two phase natural circulation and reflux boiling are maintaining heat removal.

Answer: D Learning Objective:

L56411 Given conditions of a Blackout state the action necessary to maintain subcooling margin L75186 Maintain RCS temp L61432 State the action necessary to maintain subcooling margin during a blackout.

Reference Id: Q8927 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

None Ability to determine or interpret the following as they apply to a Station Blackout: RCS core cooling through natural circulation cooling to S/G cooling Adequate core cooling can be maintained after subcooling is lost via two-phase natural circulation (Including reflux). The plant will be cooled down, in this case, to ensure superheat, per REP CET, is constant or lowering and less than 50°F superheat.

Although the core must be uncovered to acquire superheat, natural circulation is not lost.

OPTRNG_EXAM Page: 18 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 14 Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 42056G2125 Importance 2.80 3.10 Rating:

Given the following plant conditions:

Reactor was tripped 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ago due to a small LOCA.

Engineering has asked Operations to remain in Mode 3 for piping evaluation

CST level is 30 feet.

RMWT level is 35 feet.

RWT level is 85%.

How long can the Unit be maintained in Hot Standby (i.e. when are we required to place Shutdown cooling in service)?

A. 7.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months B. 9.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months C. 11 Hours D. 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months Answer: C Learning Objective:

L10349 Given Appendix 4, Condensate vs. Time Remaining in Hot Standby and appropriate parameter values Identify the maximum time we can remain in hot standby Reference Id: Q10197 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: 40EP-9EO10, Standard Appendices, Appendix 4 Technical

Reference:

40EP-9EO10, Standard Appendices, Appendix 4 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data The "CST Level vs. Time to Shutdown Cooling" standard appendix 4 will be provided as part of the references for this question. Interpreting the curve yields 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months (Answer C).

OPTRNG_EXAM Page: 19 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 15 Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 42058AK301 Importance 3.40 3.70 Rating:

Given the following plant conditions:

Unit 2 is operating at rated power.

The 'A' D/G (Diesel Generator) output breaker is closed with the D/G carrying 5000 KW of load paralleled to offsite power.

A loss of PKA-M41 occurs due to a bus fault.

Which ONE of the following describes the impact (if any) this has on the D/G?

A. The D/G continues to run but its output breaker opens.

B. The D/G trips, its output breaker opens and PBA-S03 de-energizes.

C. The D/G continues to run at 5000 KW; however, output breaker control has been lost.

D. The D/G trips but its output breaker remains closed, causing the diesel to motorize.

Answer: D Learning Objective:

L11081 Given a loss of PKA or PKB with a DG that is connected to off-site power describe how a loss of its associated 125 Vdc control power impacts the DG operation, including operator action required to mitigate this impact L75077 Describe the effect of the following on the Diesel Generator:

Control Power Loss

Control Air Loss L58359 Given a loss of power in the simulator diagnose the class instrument power loss and review the mitigation steps in the procedure Reference Id: Q13050 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ13, Appendix A Knowledge of the reasons for the following responses as they apply to the Loss of DC Power: Use of dc control power by D/Gs If running when a loss of DC occurs, the DG trips but the breaker can not open. This results in motoring the D/G.

OPTRNG_EXAM Page: 20 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 16 Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 42062AA206 Importance 2.80 3.10 Rating:

Given the following plant conditions:

The plant is operating at 100% power.

Nuclear cooling water has been lost.

RCPs (Reactor Coolant Pumps) still have seal injection.

To prevent seal damage, which ONE of the following states how long you have by procedure to restore cooling flow to the reactor coolant pump?

A. 3 minutes B. 5 minutes C. 10 minutes D. 15 minutes Answer: C Learning Objective:

L10103 Given the status of NC and RCP seal injection describe the limitations on RCP operation without NC 100866 Active Question Bank 2004 Reference Id: Q9938 Difficulty: 3.00 Time to complete: 5 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ03, Loss of Component Cooling Water, Sect. 4.0 Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: The length of time after the loss of CCW flow to a component before that component may be damaged Answer C is correct based on Abnormal Operating Procedure guidance for the conditions given.

OPTRNG_EXAM Page: 21 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 17 Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 42065AK308 Importance 3.70 3.90 Rating:

Given the following plant conditions:

Instrument air pressure is 78 psig and stable.

All three air compressors have tripped.

Why are the operators directed to start a Fuel Building Essential AFU and align it to the Auxiliary Building?

A. Performing this action will restore operability of the PREACS system, LCO 3.7.13.

B. Performing this action will assist in reducing the nitrogen buildup in the lower levels of this building.

C. Performing the action will eliminate the requirement of monitoring the lower levels of the Auxiliary Building for nitrogen.

D. Performing this action is taken to ensure that at least one AFU has been aligned before there is not sufficient air pressure to reposition the required valves.

Answer: B Learning Objective:

100866 Active Question Bank 2004 L56779 Determine what actions will be taken if IAA-UV-2, Outside Containment Isolation Valve has failed closed.

L95425 As an operating crew mitigate a loss of Instrument Air to containment L58193 Determine what actions will be taken if IAA-UV-2, Outside Containment Isolation Valve has failed closed.

Reference Id: Q9836 Difficulty: 2.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ06, Loss of Instrument Air Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air: Actions contained in EOP for loss of instrument air Correct answer is B based on procedure 40AO-9ZZ06, Loss of Instrument Air.

OPTRNG_EXAM Page: 22 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 18 Appears on: RO EXAM SRO EXAM Tier 1 Group 1 K/A # 44E06EA22 Importance 3.00 4.20 Rating:

Given the following plant conditions:

A reactor trip from 100% power occurs due to an inadvertent MSIS "A".

PBA-S03 is de-energized due to a bus lockout.

AFB-P01 is out of service to repair a pump bearing and is disassembled.

AFA-P01 tripped on overspeed.

RCS pressure is 2150psig and slowly rising

RCS temperature is 545

SG levels are at 30% NR and slowly lowering

SG pressures are being maintained by ADVs The crew has completed the SPTA's and the CRS has entered the appropriate EOP.

Which ONE of the following operator actions should be performed first?

A. Stop all RCPs.

B. Start AFN locally at the breaker.

C. Ensure AFAS-1 and AFAS-2 are actuated.

D. Depressurize one S/G to less than condensate pump discharge pressure.

Answer: A Learning Objective:

100866 Active Question Bank 2004 L76768 Given a loss of all feedwater event perform required actions L90312 As an operating crew mitigate a loss of all feedwater using the condensate pumps L61371 Describe the major mitigating strategies used during a LOAF.

L61386 Describe how the RCPs are operated (including the bases for this action) during a LOAF.

L10494 Given a Loss of all Feed determine the major mitigating strategies contained in 40EP-9EO06 Reference Id: Q0878 Difficulty: 3.00 Time to complete: 2 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40DP-9EO06, Loss of all Feedwater OPTRNG_EXAM Page: 23 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam Ability to determine and interpret the following as they apply to the (Loss of Feedwater)

Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments Answer A is correct because the EOP strategy is to remove heat input to the SGs from the RCS. This will conserve water inventory. Ref 40EP-9EO06, step 4.0.

OPTRNG_EXAM Page: 24 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 19 Appears on: RO EXAM SRO EXAM Tier 1 Group 2 K/A # 42036AK201 Importance 2.90 3.50 Rating:

Given the following plant conditions:

Unit 1 is in Mode 6, core offload operations are in progress.

The Spent Fuel handling machine operator has grappled a fuel bundle from the upender and lifted it approximately 2 ft.

The operator inadvertently bumps the controller to move the SFHM North (forward) from the upender.

The Spent Fuel Handling Machine will...

A. bridge in fast or slow speed.

B. be limited to bridge in slow speed.

C. be locked out by a "Hoist Motion" interlock.

D. be locked out by a "Bridge/Trolley" interlock.

Answer: D Learning Objective:

L97323 Given count rate information State the required actions to take if count rate has increased.

Knowledge of the interrelations between the Fuel Handling Incidents and the following: Fuel handling equipment Reference Id: Q10267 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Memory Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

78OP-9FX03, SFHM Appendix D Knowledge of the interrelations between the Fuel Handling Incidents and the following: Fuel handling equipment D is correct. It is an interlock added because of a similar event at Palo Verde. The Bridge/Trolley interlock prevents the Bridge from moving. It was added to the up limit light circuit.

OPTRNG_EXAM Page: 25 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam SPENT FUEL HANDLING MACHINE 78OP-9FX03 Appendix D - Spent Fuel Handling Machine Interlocks INTERLOCK FUNCTION REMARKS Hoist Overload/Underload Stop hoisting on overload/underload Cleared by lowering or raising the hoist.

Cable Slack Stop hoisting to prevent damage due to winch drum over rotation. Also allows grappling or ungrappling operations.

Cleared by raising the hoist.

Travel Limits Reduces chance of fuel assembly being driven into pool walls.

Cleared by reversing travel of bridge or trolley.

Upender Vertical Prevent SFHM from entering the transfer canal unless the upender is vertical. (This interlock can be bypassed by turning the Upender Vertical Bypass Switch to the ON position.)

With the transfer tube closed, this interlock must be bypassed to allow the SFHM to enter the transfer canal.

Hoist Up/Down Limit Advise that maximum/minimum hoist travel limits have been reached.

Cleared by reversing hoist travel direction.

Hoist Bypass Advise that the interlock has been circumvented.

Cleared by reversing hoist travel direction.

New Fuel Elevator Prevents SFHM trolley from entering TRANSFER CANAL unless ELEVATOR is at the down limit. SFHM must be out of BEZ to lower elevator. Then elevator must be at down limit to allow TROLLEY entry into the Transfer Canal through gate.

BRIDGE/TROLLEY Control Bridge and trolley lockout if UP LIMIT not received and an assembly is on the handling tool.

OPTRNG_EXAM Page: 26 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 20 Appears on: RO EXAM SRO EXAM Tier 1 Group 2 K/A # 42060AK101 Importance 2.60 3.10 Rating:

Given the following plant conditions:

Unit 1 is at 100% power.

Due to a mispositioning of valves an accidental release of the Waste Gas Decay Tank System is in progress.

Which ONE of the following will cause an automatic isolation of the WGDT discharge?

A. Low flow rate in the discharge header.

B. High Oxygen concentration in the WGDT.

C. High humidity alarm in the WGDT discharge.

D. Gross Beta radiation levels at sufficient level to cause a HIGH alarm.

Answer: D Learning Objective:

L78946 Describe the automatic functions / interlocks associated with the following:

Gaseous Discharge Isolation Valves Gas Compressors (GRN-C01A, C01B)

Gaseous Discharge Header Isolation Valves (HS-34A and 34B)

Radiation Monitor (RU-12) 66731 Describe the interlocks associated with the Radiation Monitors at PVNGS Reference Id: Q10194 Difficulty: 3.00 Time to complete: 5 10CFR Category: CFR 55.41 (12) 55.41 (11) Purpose and operation of radiation monitoring systems, including alarms and survey equipment.

Cognitive Level: Memory Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

NONE Knowledge of the operational implications of the following concepts as they apply to Accidental Gaseous Radwaste Release: Types of radiation, their units of intensity and the location of sources of radiation in a nuclear reactor power plant Answer D is correct because the High alarm causes automatic isolation and the process detector is beta sensitive.

OPTRNG_EXAM Page: 27 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 21 Appears on: RO EXAM SRO EXAM Tier 1 Group 2 K/A # 42061AA205 Importance 3.50 4.20 Rating:

Based on the following plant conditions:

Unit 3 is in Mode 6

The core is being offloaded.

Irradiated fuel movement is in progress in the Fuel Building.

Fuel Building Essential Ventilation has automatically started

Fuel Building Area Rad Monitor, J-SQA-RU-31 is reading 30 mR/hr

Fuel Building Ventilation Monitor, J-SQB-RU-145 is not in alarm at this time but is beginning to show a gradual increase in its reading.

The action to be taken is to contact...

A. Radiation Protection and evaluate the need to evacuate personnel from the Fuel Building.

B. RP to verify the associated alarms in the Control Room are valid then initiate a CPIAS.

C. Radwaste to stop any and all gas discharges and then inform Radiation Protection to evacuate personnel from the Fuel Building.

D. Radwaste to verify that the associated alarms received in the control room are valid and to evacuate the Fuel Building once this has been confirmed.

Answer: A Learning Objective:

L64296 Describe the operator's responsibility when acknowledging RMS alarms Reference Id: Q10195 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (12) 55.41 (11) Purpose and operation of radiation monitoring systems, including alarms and survey equipment.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

74RM-9EF41 Ability to determine and interpret the following as they apply to the Area Radiation Monitoring (ARM) System Alarms: Need for area evacuation; check against existing limits.

A is correct based on action in 74RM-9EF41, Radiation Monitor Alarm Response.

OPTRNG_EXAM Page: 28 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 22 Appears on: RO EXAM SRO EXAM K/A # 42067G2120 Importance 4.30 4.20 Rating:

Given the following plant conditions:

You are responding to a fire in NAN-S01 as a member of the plants fire brigade team.

You have brought a Class B/C fire extinguisher to the scene.

Other members have rigged a fire hose with a solid-stream nozzle.

Which ONE of the following actions should be taken?

A. Do not use the Class B/C fire extinguisher. Put the fire out with a fire hose.

B. Do not use the fire hose. Put the fire out with the Class B/C fire extinguisher.

C. Use the fire hose first. If it does not put out the fire, use the Class B/C fire extinguisher.

D. Wait for the fire brigade member assigned to bring a Class D fire extinguisher, then use the Class D fire extinguisher.

Answer: B Learning Objective:

L57494 Describe the Control Room's initial response to a fire alarm, report of an emergency or a confirmed emergency.

100866 Active Question Bank 2004 Reference Id: Q10252 Difficulty: 2.00 Time to complete: 2 Cognitive Level: Memory Question Source: INPO Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

14DP-9FP32, Emergency Notification and Response Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.

INPO question 25691 OPTRNG_EXAM Page: 29 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 23 Appears on: RO EXAM SRO EXAM Tier 1 Group 2 K/A # 068G2110 Importance 2.70 3.90 Rating:

Given the following plant conditions:

The Control Room is evacuated due to a fire.

The operators prepare to perform a Natural Circulation cooldown from remote locations.

Which ONE of the following statements is correct with regards to why certain instrumentation at the Remote Shutdown Panel should be considered reliable for plant control during a Control Room fire?

Group 1 Indicators RCA-LI-110X-1 (Pressurizer Level)

RCA-PI-102A-1 (Pressurizer Pressure)

SGA-LI-1113A-1 (SG #1 and 2 levels)

SGA-PI-1013A-1 (SG #1 and 2 pressures)

Group 2 Indicators RCB-LI-110Y-1 (Pressurizer Level)

RCB-PI-102B-1 (Pressurizer Pressure)

SGB-LI-1113B-1 (SG #1 and 2 levels)

SGB-PI-1013B-1 (SG #1 and 2 pressures)

A. Only the group 1 indicators because these instruments have isolators in their circuits.

B. Only the group 2 indicators because these instruments have isolators in their circuits.

C. Only the group 1 indicators because these instruments have LOCAL/REMOTE disconnects in their power supplies.

D. Only the group 2 indicators because these instruments have LOCAL/REMOTE disconnects in their power supplies.

Answer: B Learning Objective:

L58909 Given a Control Room Fire identify which instruments located on the Remote Shutdown Panel are considered reliable Reference Id: Q10196 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Memory Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

NONE Conduct of Operations: Knowledge of conditions and limitations in the facility license, CR evacuation.

OPTRNG_EXAM Page: 30 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam Answer A is incorrect because A train does not have optical isolators. Answers C & D do not have Local/Remote disconnects for their power supplies. Only group 2 indicators are used in a CR fire evacuation.

OPTRNG_EXAM Page: 31 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 24 Appears on: RO EXAM SRO EXAM Tier 1 Group 2 K/A # 42069AK301 Importance 3.80 4.20 Rating:

Given the following initial plant conditions:

A large break LOCA has occurred.

RAS has actuated.

PBA-S03 is de-energized.

SI Flow is adequate.

RCS pressure is 160 psia.

Containment pressure is 10 psig.

The B Containment Spray pump trips.

Which ONE of the following describes the method available to control containment pressure and temperature?

A. Restore normal containment cooling.

B. Align LPSI B to spray the containment.

C. Align LPSI A to spray the containment.

D. Align the Containment Purge System for purging containment.

Answer: B Learning Objective:

56304 Given the FRP is being performed and given specific plant conditions determine if the selected CI success path safety function status checks are being met Reference Id: Q10114 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: PV Bank modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40EP-9EO02, LOCA 40EP-9EO09 FRP.

Knowledge of the reasons for the following responses as they apply to the Loss of Containment Integrity: Guidance contained in EOP for loss of containment integrity The problem is both cooling and pressure control. Answer A is not effective for pressure control. LPSI A is not available due to the loss of PBA-S03. Containment purge is not a preferred option with LPSI available.

OPTRNG_EXAM Page: 32 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam FUNCTIONAL RECOVERY 40EP-9EO09 Page 211 of 231 CTPC-2 INSTRUCTIONS

3. IF CSAS actuated, THEN check at least one CS header is delivering 4350 gpm or more.

CONTINGENCY ACTIONS

NOTE -------------------------

There is no indication of CS flow when using a LPSI pump for CS.

3.1 IF it is desired to use LPSI Pump A to supply CS A train, AND LPSI Pump A is NOT needed to support any RC, IC, or HR success

path, THEN perform the following:

a. Ensure that LPSI Pump A is running.

OPTRNG_EXAM Page: 33 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam Original question ID: Q10254 Points: 1.00 prior to modification Given the following initial plant conditions:

Unit 1 was operating at 100% power when a Steam Line Break occurred inside containment on Steam Generator #2.

Several Containment Spray and Cooling system failures have occurred.

The crew has entered the ESD (Excess Steam Demand) procedure upon completion of the SPTAs.

Which ONE of the following actions in ESD helps to limit the containment pressure transient?

A. Feed S/G #2 at only 50 gpm to minimize liquid inventory.

B. Start up the hydrogen recombiner to minimize the potential for hydrogen burn.

C. Manually isolate feedwater to S/G #2 to minimize the mass and energy release.

D. Perform a rapid cooldown of the RCS using S/G #1 to reduce the energy input to containment.

Answer: C OPTRNG_EXAM Page: 34 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 25 Appears on: RO EXAM SRO EXAM Tier 1 Group 2 K/A # 44A11AA11 Importance 3.30 3.50 Rating:

Given the following plant conditions for a specific point in time:

Unit 2

The reactor has tripped.

An MSSV (Main Steam Safety Valve) has stuck open on SG 1.

SG 1 is at 32% WR.

SG 1 is at 930 psia.

SG 2 is at 43% WR.

SG 2 is at 1060 psia.

LOOP 1 Tc 538°F, Th 559°F.

LOOP 2 Tc 556°F, Th 559°F.

With no operator action, which ONE of the following describes the status of SG feedwater?

A. MFW is feeding both SGs in RTO.

B. Neither SG is receiving feedwater.

C. AFA and AFB are feeding both SGs.

D. AFA and AFB are feeding SG #1 only.

Answer: B Learning Objective:

30074 As an operating crew Respond to Steam Line ESD event(s)

L11214 Given conditions of an ESD analyze RCS Heat Removal to determine if the SFSC acceptance criteria is satisfied 100866 Active Question Bank 2004 Reference Id: Q9113 Difficulty: 3.00 Time to complete: 2 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

AFAS Simplified Drawing Ability to operate and / or monitor the following as they apply to the (RCS Overcooling)

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Answer A is correct under the conditions because SG#1 is isolated and SG#2 level is greater than the AFAS setpoint. Ref 40EP-9EO05.

OPTRNG_EXAM Page: 35 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 26 Appears on: RO EXAM SRO EXAM Tier 1 Group 2 K/A # 44A13AA22 Importance 2.90 3.80 Rating:

Given the following plant conditions:

A LOOP (Loss of Offsite Power) has occurred on Unit 1, causing a reactor trip.

No actions have been taken to restore non class systems or components.

Pressurizer level is at 71% and trending up.

One charging pump is running.

The correct action to restore Pressurizer level is to...

A. increase letdown flow.

B. stop the running charging pump.

C. cooldown as needed to maintain level < 65%.

D. verify shutdown margin and start a cooldown to obtain T-hot < 550°F.

Answer: C Learning Objective:

L90347 As an operating crew mitigate a Loss of Forced Circ Reference Id: Q10199 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40EP-9EO07, LOOP Ability to determine and interpret the following as they apply to the (Natural Circulation Operations) Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

Answer C is correct because letdown is lost and with no NCW, charging should not be stopped. Stopping the charging pump has adverse impact on charging pump seals, SDM is not a concern at this point and 550 deg. F is for another event. Comprehense/Anal based on analysis required to determine the LOOP results in a loss of NCW.

OPTRNG_EXAM Page: 36 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 27 Appears on: RO EXAM SRO EXAM K/A # 44A16K22 Importance 3.00 3.30 Rating:

Given the following plant conditions:

Unit 2 is at 100% power.

No equipment is out of service.

All systems are aligned normally.

The crew detects a small RCS leak on ERFDADS and enters the Excess RCS Leakrate AOP.

The Area Operator informs the Control Room that Nuclear Cooling Water Surge Tank Level is slowly rising.

Which ONE of the following contains only components which must be considered as potential sources of leakage for the stated condition?

A. Letdown Heat Exchanger and RCP Seal Coolers.

B. Shutdown Cooling Heat Exchanger and RCP Seal Coolers.

C. RCP Seal Coolers and the Non-Nuclear Sample Coolers.

D. Letdown Heat Exchanger and the Shutdown Cooling Heat Exchangers.

Answer: A Learning Objective:

L10169 Given indications of RCS or a Steam Generator Tube Leak, describe the basic procedure methodology, including Reactor Trip is thresholds, Reference Id: Q10258 Difficulty: 2.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ02, Excess RCS Leakrate Knowledge of the interrelations between the (Excess RCS Leakage) and the following:

Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

A is correct because these two items would cause a leak into the NC system that would be indicated by an increase in the NC Surge Tank Level.

B, C, are incorrect because NC does not supply the SDCHX. D is incorrect because a leak at these locations would cause a decrease in Surge Tank Level (i.e. lower pressure systems)

OPTRNG_EXAM Page: 37 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 28 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 34003K201 Importance 3.10 3.10 Rating:

Given the following plant conditions:

Unit at 100% power.

All systems available.

A loss of __________ will result in the de-energization of the reactor coolant pump RCP 1A?

A. Bus PBB-S04 B. Bus NAN-S03 C. Bus NBN-S02 D. Bus NAN-S01 Answer: D Learning Objective:

L67246 Explain the operation of the Reactor Coolant Pumps under normal operating conditions.

Reference Id: Q7260 Difficulty: 2.00 Time to complete: 1 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

10CFR Category: CFR 55.41 55.41 (10) Administrative, normal, abnormal, and emergency (10)CFR 55.41 (4) operating procedures for the facility.55.41 (4) Secondary coolant and auxiliary systems that affect the facility.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ12, Degraded Electrical Knowledge of bus power supplies to the following: RCPS Answer D is correct because RCP power is non-class and is 13.8 KV.

OPTRNG_EXAM Page: 38 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 29 Appears on: RO Exam SRO EXAM Tier 2 Group 1 K/A # 32004K631 Importance 3.10 3.50 Rating:

Given the following plant indications:

Unit 1 is at 100% power in a normal lineup

All RCP seal injection controllers (CHN-FIC 241 through 244) are in automatic.

The output signal of CHN-FIC-244, 2B Seal Injection controller, begins rising.

Which ONE of the following could be the cause?

A. Decreased VCT pressure.

B. Stopping a running charging pump.

C. One of the other seal injection valves failed open.

D. Seal Injection flow has risen above the setpoint.

Answer: D Learning Objective:

L56822 Given an RCP with seal injection removed determine the temperature response when seal injection is secured to an RCP Reference Id: Q27608 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

P & IDs Knowledge of the effect of a loss or malfunction on the following CVCS components:

Seal injection system and methods of operation.

Answer D is correct due to these controllers being backward acting controllers. Seal injection flow rising causes controller output to rise to close down on the valve.

OPTRNG_EXAM Page: 39 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 30 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 32004A410 Importance 3.60 3.20 Rating:

Given the following conditions:

Boric Acid Makeup pump CHN-P02A was running to support boration.

The blue light on the handswitch is illuminated for CHN-P02A.

Discharge pressure on CHN-PI-206 reads 32 psig.

Which one of the following describes what happened and what action (if any) should be taken to support boration operations?

A. Low suction pressure; must manually start the standby pump.

B. Thermal overload; must manually start the standby pump.

C. Low discharge pressure; no action required because the standby pump will auto start in 15 seconds.

D. RWT level at 85%; no action required because the standby pump will auto start immediately.

Answer: C Learning Objective:

L68202 Describe the automatic functions associated with the Boric Acid Makeup Pumps (CHN-P02A AND P02B).

100866 Active Question Bank 2004 Reference Id: Q62121 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

41AL-1RK3A Ability to manually operate and/or monitor in the control room: Boric acid pumps.

Per drawing 01-E-CHB-041 & 042 and Alarm Response for window 3A06A, Group A, answer C is correct. Answer B thermal over load does not cause blue light. Answer A is associated with the charging pumps.

RWT level does not trip BAMPs but does provide suction.

OPTRNG_EXAM Page: 40 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 31 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 34005K503 Importance 2.90 3.10 Rating:

Given the following plant conditions:

Unit 2 is in Mode 5.

Shutdown Cooling has been initiated using LPSI 'A'.

Shutdown Cooling Train B is lined up for SDC but has not been recirculated.

LPSI Pump 'A' trips due to a fault condition.

RCS Pressure is 360#

RCS temperature is 150 °F.

What is the potential concern with swapping the SDC alignment to 'B' Train at this time?

A. The LTOP could lift when the "B" SDC Loop is exposed to the RCS.

B. The colder water in Loop B could cause the 19°F per minute heatup rate limit on SDC loop to be exceeded.

C. RWLIS has not been calibrated for LPSI B flow, therefore RCS level indication will not be accurate.

D. The addition of positive reactivity due to a difference in boron concentrations between B SDC and the RCS.

Answer: D Learning Objective:

L79915 Discuss the concerns with boron concentration associated with the Shutdown Cooling System.

Reference Id: Q10202 Difficulty: 3.00 Time to complete: 4 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40OP-9SI01, SDC Initiation Knowledge of the operational implications of the following concepts as they apply the RHRS: Reactivity effects of RHR fill water.

Answer D is correct based on the Precautions listed in the governing procedure, 40OP-9SI03.

OPTRNG_EXAM Page: 41 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 32 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 32006K301 Importance 4.10 4.20 Rating:

Given the following conditions:

The plant has experienced a LOCA

The RCS is at 1000 psig

Trends for all major parameters are improving

All equipment is operating normally THEN the B HPSI pump handswitch indicates brighter than normal green.

Which of the following is the result of this condition?

A. RCS subcooling worsens, RVUH level lowers, pressurizer level lowers.

B. RCS subcooling improves, RVUH level lowers, pressurizer level lowers.

C. RCS subcooling improves, RVUH level lowers, pressurizer level lowers.

D. RCS subcooling worsens, RVUH level increases, pressurizer level increases.

Answer: A Learning Objective:

93897 State the ECCS core flow assumed in the Large Break LOCA analysis 93805 State the 10CFR 50.46 design criteria for ECCS performance and explain the criteria bases.

Reference Id: Q10203 Difficulty: 2.00 Time to complete: 2 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

GFES and electrical prints for handswitches.

Knowledge of the effect that a loss or malfunction of the ECCS will have on the following:

RCS.

The loss of HPSI B is indicated by brighter than normal green indication on the handswitch.

Reducing HPSI flow in half produces worsening trends in subcooling, RVUH level, and Pzr level.

OPTRNG_EXAM Page: 42 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 33 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 35007K502 Importance 3.10 3.40 Rating:

Given the following plant conditions:

Unit 1 is in a heatup from MODE 5 to MODE 3.

The unit has commenced drawing a bubble in the Pressurizer.

The Pressurizer is being periodically vented to the RDT (Reactor Drain Tank).

The RDT is aligned to manually vent to the Waste Gas Surge Header.

During this procedure, the Reactor Drain Tank should be maintained at what pressure?

A. Less than 25 psig.

B. 25 psig to 75 psig.

C. 75 psig to 100 psig.

D. 100 psig to 125 psig.

Answer: A Learning Objective:

L97166 Describe how a steam bubble is drawn in the pressurizer.

Reference Id: Q10204 Difficulty: 3.00 Time to complete: 2 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Memory Question Source: INPO Bank NOT modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40OP-9ZZ01, Appendix H Knowledge of the operational implications of the following concepts as they apply to PRTS:

Method of forming a steam bubble in the PZR INPO Q#20980 Answer A is correct by procedure 40OP-9ZZ01. The other ranges of pressure are too high of this operation.

OPTRNG_EXAM Page: 43 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 34 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 35007K103 Importance 3.00 3.20 Rating:

Given the following plant conditions and a set of steam tables:

Unit 1 RCS pressure is at 2,000 psia

A Pressurizer safety/relief valve is leaking to the RDT

The RDT is at 10 psig.

What is the temperature of the fluid downstream of the relief valve?

A. 170°F B. 190°F C. 240°F D. 280°F Answer: C Learning Objective:

L10452 Given PZR Safety Valve tailpipe temperatures and the steam tables analyze the data to determine the status of the PZR safety valve 6193004G11 Determine the exit conditions of a fluid for a throttling process.

6193004K115 K1.15 Determine the exit conditions for a throttling process based on the use of steam and/or water Reference Id: 193004Q027 Difficulty: 4.00 Time to complete: 5 10CFR Category: CFR 55.41 (14) 55.41 (14) Principles of heat transfer thermodynamics and fluid mechanics.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: Steam Tables Technical

Reference:

Steam Tables Knowledge of the interrelations between the Pressurizer Vapor Space Accident and the following: Valves Answer C is correct: Steam Tables diagram for a RCS press of 2000 psia and RDT pressure at 10 psig is 240 deg F.

Distractors A, B, & D were taken from other RDT Pressures.

OPTRNG_EXAM Page: 44 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 35 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 38008K102 Importance 3.30 3.40 Rating:

Given the following conditions:

Unit 1 operating at 100% power

Main Generator stator temperatures are increasing

RCP motor temperatures are increasing Which ONE of the following describes what happened? A loss of the:

A. Normal Chilled Water System B. Turbine Cooling Water System C. Plant Cooling Water System D. Nuclear Cooling Water System Answer: C Learning Objective:

74240 Describe how the Plant Cooling Water System supports the operation of the following systems:

Turbine Cooling Water System

Nuclear Cooling Water System

Condenser Air Removal System Reference Id: Q7518 Difficulty: 2.00 Time to complete: 2 10CFR Category: CFR 55.41 (4) 55.41 (4) Secondary coolant and auxiliary systems that affect the facility.

Cognitive Level: Memory Question Source: PV Bank Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

NONE Knowledge of the physical connections and/or cause-effect relationships between the CCWS and the following systems: Loads cooled by CCWS.

Only Plant cooling water can impact these two components that are cooled by systems cooled by PCW.

OPTRNG_EXAM Page: 45 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam Original question ID: Q7518 Points: 1.00 prior to modification Which ONE of the following systems supplies cooling water to the Turbine Cooling Water heat exchangers?

A. Circulating Water B. Normal Chill Water C. Plant Cooling Water D. Nuclear Cooling Water Answer: C OPTRNG_EXAM Page: 46 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 36 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 38008A401 Importance 3.30 3.10 Rating:

What is the meaning of the AMBER lights associated with the Nuclear Cooling Water, NCN-P01A and NCN-P01B pump handswitches, on B07? The AMBER light...

A. informs the operator that the pump has automatically started.

B. informs the operator that the pump has tripped on overcurrent.

C. comes on when the pump has been started locally at the 4.16KV switchgear.

D. comes on when the pump is running but does not have adequate discharge pressure.

Answer: A Learning Objective:

100866 Active Question Bank 2004 65018 Describe the Control Room controls associated with the NC Pumps, including their indications.

Reference Id: Q72602 Difficulty: 2.00 Time to complete: 1 10CFR Category: CFR 55.41 (4) 55.41 (4) Secondary coolant and auxiliary systems that affect the facility.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

NONE Ability to manually operate and/or monitor in the control room: CCW indications and controls.

Answer A is correct because it is a standard function of the amber light at Palo Verde.

Overcurrent uses a green light. There is no light for local control. Alarms are used for performance monitoring.

OPTRNG_EXAM Page: 47 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 37 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 33010K601 Importance 2.70 3.10 Rating:

Given the following conditions:

The pressurizer pressure master controller is in AUTO

The RCN-HS-100 is selected to channel X

RCN-PT-100X fails low Assuming no operator action, which ONE of the following is correct?

A. The proportional heaters deenergize due to low pressure.

B. Backup heaters energize then trip when actual pressure increases above 2285.

C. All heaters energize and eventually cause a reactor trip on high pressurizer pressure.

D. All heaters energize and pressure increases until the spray valve opens to reduce pressure.

Answer: C Learning Objective:

L88177 Describe the response of the Pressurizer Pressure Control System to a failure of various power supplies.

L75356 Describe the response of the Pressurizer Pressure Control System to a failure of various power supplies.

100866 Active Question Bank 2004 Reference Id: Q2657 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (4) 55.41 (4) Secondary coolant and auxiliary systems that affect the facility.

10CFR Category: CFR 55.41 55.41 (4) Secondary coolant and auxiliary systems that affect the (4)CFR 55.41 (7) facility.55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

PVNGS Operator Information Manual, pg 31 Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS:

Pressure detection system.

With instrument failed low the spray valves wont open but all heaters will energize.

System will not see the high pressure.

Comprehensive because operator must evaluate effect of instrument failure on the control system, then the effect on the plant.

OPTRNG_EXAM Page: 48 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 38 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 33010A402 Importance 3.2 3.6 Rating:

Given the following plant conditions:

An earthquake causes a loss of the switchyard which leads to a loss of offsite power.

A steam line break inside containment has also occurred.

SIAS, CIAS, CSAS, and MSIS have occurred

The operators have NOT touched the PZR heater controls.

Which ONE of the following is true?

A. No pressurizer heaters are operating.

B. Only the proportional heaters are operating.

C. Only the class backup heaters are operating.

D. Only the non-class backup heaters are operating.

Answer: A Learning Objective:

L75243 Describe the Control Room controls associated with the Pressurizer Backup Heaters including indications.

Reference Id: Q10205 Difficulty: 3.00 Time to complete: 2 10CFR Category: CFR 55.41 (3) 55.41 (3) Mechanical components and design features of the reactor primary system.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ17, Inadvertent PPS-ESFAS, Sect. 8.0 Ability to manually operate and/or monitor in the control room: PZR heaters.

Loss of power removes non-class power. The Safeguards signals remove class power until overridden. Answer A is correct.

OPTRNG_EXAM Page: 49 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 39 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 37012K406 Importance 3.20 3.60 Rating:

Given the following plant conditions:

The plant is at 100% power.

Channel D PPS bypassed due to failed high RCS pressure (Narrow Range) transmitter.

Channel B PPS SG-2 level low has tripped due to a failed transmitter.

Channel A RCS pressure (Narrow Range) transmitter now fails high.

Based on these conditions, which of the following is correct?

A. The operator can not bypass channel A RCS pressure transmitter.

B. The reactor would have tripped when the channel A pressure transmitter failed.

C. 2 Reactor Trip Circuit Breakers (RTCBs) would open when the channel A RCS pressure transmitter failed, but the reactor would not trip.

D. If the operator bypasses the channel A RCS pressure transmitter, that channel would go into bypass, while removing the channel D transmitter from bypass.

Answer: D Learning Objective:

100866 Active Question Bank 2004 L77084 Describe the RPS operating bypasses.

Reference Id: Q23178 Difficulty: 3.00 Time to complete: 2 10CFR Category: CFR 55.41 (6) 55.41 (6) Design, components, and functions of reactivity control mechanisms and instrumentation.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AL-9RK5B PANEL B05B ALARM RESPONSES Knowledge of RPS design feature(s) and/or interlock(s) which provide the following:

Automatic or manual enable/disable of RPS trips.

Channel A has highest priority for bypass and will remove all other channels from bypass.

The channel can be bypassed but there is a RPS Trip Channel Bypass Interlock that prevents two channels bypassed at the same time. Due to the RCS Press channel being bypassed, another failure will not cause a trip. No logic is activated for RTSG breakers.

OPTRNG_EXAM Page: 50 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 40AL-9RK5B PANEL B05B ALARM RESPONSES 0 Rev.

Page 136 of 161 RESPONSE SECTION PT ID POSSIBLE CAUSE SETPOINT SBYS25 Plant Protection System Channel A Bypass N/A SBYS26 Plant Protection System Channel B Bypass N/A SBYS27 Plant Protection System Channel C Bypass N/A SBYS28 Plant Protection System Channel D Bypass N/A AUTO ACTION None.

NOTE A PPS trip channel bypass places the bypassed channel in a two out of three trip logic condition.

FIRST PRIORITY OPERATOR ACTION

___ 1. None.

SECOND PRIORITY OPERATOR ACTION NOTE The following Technical Specifications may be impacted: 3.3.4, 3.3.6.

___ 1. Determine which channel caused the alarm, if not known, by observing the amber trip channel bypass indicators at the PPS remote panels, at B05.

___ 2. Investigate the cause of the alarm and initiate corrective action to clear the alarm condition as necessary. Possible causes of the alarm include:

____ 2.1 Trip channel bypassed at bistable control panel on plant protective system cabinet.

____ 2.2 Failed auxiliary relay in relay card rack portion of plant protective system cabinet.

End of Response OPTRNG_EXAM Page: 51 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 40 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 32013K502 Importance 2.90 3.30 Rating:

Given the following plant conditions:

Unit 1 is at 100% power.

A loss of PNA-D25 has occurred Which ONE of the following will occur to the Reactor Trip Switchgear Breakers (RTCBs)

A. Two RTCBs will open and the reactor will trip.

B. No RTCBs will open and the reactor will not trip.

C. All four RTCBs will open and the reactor will trip.

D. Two RTCBs will open and the reactor will not trip.

Answer: D Learning Objective:

L77073 Describe how matrix logic receives electrical power.

Reference Id: Q10206 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level: Memory Question Source: PV Bank Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ13, Loss of Class Instrument or Control Power Knowledge of the operational implications of the following concepts as they apply to the ESFAS: Safety system logic and reliability.

The loss of one power supply trips two RTCBs, but both are on the same side leaving two closed on the other side providing continuity of power.

OPTRNG_EXAM Page: 52 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam Original question ID: Q10206 Points: 1.00 prior to modification If one of the six RPS matrices loses one of its two matrix power supplies which ONE of the following will occur?

A. Two RTCBs will open and the reactor will trip.

B. No RTCBs will open and the reactor will not trip.

C. All four RTCBs will open and the reactor will trip.

D. Two RTCBs will open and the reactor will not trip.

Answer: D OPTRNG_EXAM Page: 53 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 40AO-9ZZ13 LOSS OF CLASS INSTRUMENTOR CONTROL POWER Appendix A, Effects of the Loss of Channel A RTSG Breaker A and C trip open due to loss of power to one leg of the RPS logic matrices AB, AC, AD.

RTSG Breaker A trips on a SPLA trip and loss of power to RPS Initiation path #1.

Lose power to all Channel A input parameter instruments resulting in Channel A trips on all parameters that have a low trip setpoint.

Unit 1 & 3 only - CEAC 1 becomes inop due to loss of power to RSPTs and may generate penalty factors when reenergized.

Unit 2 only - CEAC 1 in all CPC channels becomes inop due to loss of power to RSPTs and may generate penalty factors when reenergized.

OPTRNG_EXAM Page: 54 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 41 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 35022A203 Importance 2.60 3.00 Rating:

Given the following plant conditions:

Unit 3 is in mode 1 at 100% power.

CEDM ACU A is tagged out (both fans A and C).

The CEDM ACU COOL SYS TRBL alarm window is lit.

CEDM ACU B fans B and D electrical protection computer point HCYS50 appears on the alarm screen.

In accordance with 40AO-9ZZ20, Loss of HVAC, the appropriate action is to:

A. commence a rapid shutdown if cooling is not restored within 40 minutes.

B. trip the reactor and perform the SPTAs if cooling is not restored within 10 minutes.

C. minimize all CEA movement to only that required for ASI control and commence a rapid shutdown if cooling is not restored within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

D. commence a rapid shutdown if cooling is not restored within 10 minutes and have RTSG breakers opened 40 minutes after the initial cooling loss.

Answer: D Learning Objective:

L56879 Determine the required actions and time frames to protect plant equipment if a loss of CEDM Coolers exists.

Reference Id: Q10207 Difficulty: 3.00 Time to complete: 4 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: PV Bank NOT Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ20, Loss of HVAC Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Fan motor thermal overload.

Answer D is correct based on procedure 40AO-9ZZ20, section 1.0. The objective is to de-energize the CEDM coils within 40 minutes of the cooling loss.

OPTRNG_EXAM Page: 55 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 40AO-9ZZ20, Loss of HVAC 10.0 Loss of Containment Building HVAC - CEDM CAUTION If RCS temperature is 300°F or more, CEDM coils may be damaged if CEDM Cooling is not restored or if the coils are not de-energized within 40 minutes of the initial loss.

___1. IF any CEDM Fan is available, THEN start at least one CEDM Fan.

___2. PERFORM 40AO-9ZZ12, Degraded Electrical Power as needed to restore electrical power to any CEDM Fan.

___3. IF at least one CEDM Fan is NOT restored within 10 minutes, THEN PERFORM 40OP-9ZZ05, Power Operations, Section 8.0, Rapid Shutdown to ensure that the unit is shutdown within the next 30 minutes.

___4. Continue efforts to restore at least one CEDM Fan.

OPTRNG_EXAM Page: 56 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 42 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 35026K405 Importance 2.80 3.30 Rating:

What prevents clogging of the containment spray nozzles following a design Loss of Coolant Accident while on recirculation?

A. The screens in the recirculation sump will block any particles big enough to clog the nozzle.

B. Duplex filters on the discharge of the pumps remove particles large enough to clog the spray nozzles.

C. Anti-vortex blades create a centrifugal force to keep large particles and debris from entering the sump suctions.

D. Pump suctions are located at an elevation in the sump above where debris settles.

Answer: A Learning Objective:

L59383 Describe the Recirculation Sumps and Trisodium Phospate baskets.

Reference Id: Q10208 Difficulty: 2.00 Time to complete: 3 10CFR Category: CFR 55.41 (3) 55.41 (3) Mechanical components and design features of the reactor primary system.

Cognitive Level: Memory Question Source: INPO Bank NOT modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

NONE Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following:

Prevention of material from clogging nozzles during recirculation Taken from INPO Q#26454 Anti-vortex blades are present in the sump suction to improve flow conditions to the pumps, thus minimizing the potential for cavitation. There are no filters on the discharge of the pumps. Accident analysis assumes that particles and debris will be blocked from entering the spray pump suctions by the sump screens.

OPTRNG_EXAM Page: 57 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 43 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 34039K404 Importance 2.90 3.10 Rating:

Given the following plant conditions:

Unit 2 Reactor has tripped from 100% power.

Condenser Vacuum has been lost.

Steam bypass valves 7 & 8 are controlling steam header pressure in automatic.

Steam header pressure has just (1 second ago) dropped 40 psi below the SBCS setpoint due to an ADV being inadvertently opened.

Which ONE of the following is true?

SBCS valves will...

A. modulate closed.

B. "quick" close due to the loss of the condenser interlock.

C. remain as is until pressure drops approximately 50 psi below the setpoint.

D. remain as is until SG header pressure drops approximately 75 psi below setpoint.

Answer: A Learning Objective:

L65680 Explain the operation of SBCS permissive and demand logic.

Reference Id: Q10209 Difficulty: 3.00 Time to complete: 2 10CFR Category: CFR 55.41 (6) 55.41 (6) Design, components, and functions of reactivity control mechanisms and instrumentation.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

Simplified Drawing Knowledge of MRSS design feature(s) and/or interlock(s) which provide for the following:

Utilization of steam pressure program control when steam dumping through atmospheric relief/dump valves, including T-ave. limits.

Answer A is correct since modulation signal is based on the difference between setpoint and steam pressure. The quick close goes through a time delay of 15 seconds. The valves cannot remain as-is with the absence of a modulate signal.

OPTRNG_EXAM Page: 58 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 44 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 34059G211 Importance 3.70 3.80 Rating:

Given the following plant conditions:

Unit 1 is operating at 100% power.

An Instrument failure has occurred on feedwater control system #1.

Steam generator #1 level is 45% narrow range and dropping slowly.

The Secondary Operator believes taking MANUAL control of the master or economizer controllers will stabilize the plant.

Which ONE of the following describes the actions the control operator is to take for the observed indications?

A. Immediately take MANUAL control of the master controller and raise the output; inform the Control Room Staff of the results.

B. Immediately take MANUAL control of the economizer controller and raise the output; inform the Control Room Staff of the results.

C. Inform the Control Room Staff; obtain control room supervisor concurrence; take MANUAL control of the master controller and raise its output.

D. Inform the Control Room Staff; obtain control room supervisor concurrence; place the master controller in MANUAL and raise the output of the economizer controller.

Answer: C Learning Objective:

L12044 Describe the manual overriding of automatic systems.

100866 Active Question Bank 2004 Reference Id: Q6834 Difficulty: 2.00 Time to complete: 2 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40DP-9OP02, Conduct of Shift Operations.

The Master controller is preferred over any individual controller. CRS concurrence should be gained first and informing CR staff. Ref Conduct of Shift Operations procedure.

Candidate must know that raising the output of the Economizer without placing it in manual has no impact.

OPTRNG_EXAM Page: 59 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 40DP-9OP02 Page 43 of 52 12.0 MANUAL OVERRIDE OF AUTOMATIC SYSTEMS Detailed instructions for how to shift various controllers from auto to manual are addressed in system operating procedures. The following guidelines are provided to specify general considerations and controls for operation of automatic systems in a manual mode.

12.1 The preferred method of operation for plant systems which have automatic controllers is with controllers in the automatic mode.

12.2 The decision to operate a controller in manual must be made with consideration of potential impact on plant reliability and safety.

12.3 The following criteria should be used to evaluate the effect of manual controller operations:

By design, manual controller operation should not be required to assure plant safety.

Manual operation of automatic controllers may mitigate a transient that represents a challenge to systems which do protect the plant.

Manual operation may adversely affect a transient by defeating interlocks or designed control system response.

12.4 When a controller is to be placed in a manual mode, it should be done from the highest effective level available (i.e., Master Controller).

12.5 Concurrence shall be obtained from the CRS prior to placing any automatic controller in manual or returning any controller to automatic.

12.6 All Control Room personnel shall be informed of the status of the controller and changes in their expected actions in the event of a plant transient with the automatic controller in manual.

12.7 During equipment malfunctions which result in a transient, the Operator shall make a conscious decision on controller operation based on his understanding of the transient and what manual actions are likely to be effective in mitigating it.

1. If the operator believes he can control the transient by taking manual control, then he should do so immediately and inform the other control room personnel of his action. The CRS shall state his concurrence or direct alternate actions.

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ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 45 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 34061A102 Importance 3.30 3.60 Rating:

Given the following plant conditions:

Unit 1 is in a Blackout.

A Loss of all Feed event occurred.

Both SG's attained dryout conditions for a short period of time.

An AO has locally started AFW Pump "A" using EOP, Appendix 40.

AFW pump "A" has established feedflow to #1 SG.

AFW pump "A" discharge press is ~1150 psig.

#1SG wide range level is approximately 5% and steady at this time.

Feed flow is approximately 200 gpm to #1 SG.

#1 SG Pressure is 1100 psig.

The CRS wishes to increase the feed rate to #1 SG to ~ 600 gpm. To ensure additional feed flow at this time the next step is...

A. to align feedwater flow to the #2 SG in parallel with #1 SG.

B. to further open AFA-HV-54, AFW pump "A" steam throttle valve.

C. to open an ADV on #1 SG as necessary to lower pressure below the discharge head of AFW pump "A".

D. to further open AFA-HV-54, AFW Pump "A" steam throttle valve and at the same time open an ADV on #1 SG.

Answer: C Learning Objective:

L60485 Given a loss of all feedwater event restore feedwater using Local Operation of AFA-P01 Reference Id: Q10210 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (14) 55.41 (14) Principles of heat transfer thermodynamics and fluid mechanics.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

NONE Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the AFW controls including: S/G pressure.

Answer C is correct because it is the easiest and most effective way to create a greater DP to feed the SG.

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ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 46 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 34061K601 Importance 2.50 2.80 Rating:

Given the following plant conditions:

Reactor Trip.

Steam Generator (S/G) #1 Level 30% WR.

S/G #2 Level 26% WR.

S/G Pressure transmitter failures are causing the following annunciator to be locked in:

S/G #2 > S/G #1 Pressure Channel Trip If both S/G Levels decreased to < 25% WR, which one of the following statements would be correct?

Auxiliary feed would automatically feed...

A. both S/Gs because of low S/G levels.

B. only S/G #1 because of the S/G pressure difference.

C. only S/G #2 because of the S/G pressure difference.

D. only S/G #2 until S/G #2 pressure equals 950 psia, then both.

Answer: C Learning Objective:

78322 Describe the response of the Auxiliary Feedwater System to a failure of support systems.

Reference Id: Q10212 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level: Comprehension / Anal Question Source: PV Bank NOT Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

NONE Knowledge of the effect of a loss or malfunction of the following will have on the AFW components: Controllers and positioners.

Answer C is correct because there is a differential pressure lockout condition created in the question stem. Aux Feedwater Actuation (AFAS) will occur but only feed SG#2. The valves for SG#1 are closed.

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ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 47 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 36062K301 Importance 3.50 3.90 Rating:

Given the following plant conditions:

Unit 1 is operating in Mode 1.

All startup transformers are initially in a normal lineup.

NAN-X03, Startup XFRMR #3, experiences a fault causing it to lockout.

30 seconds later, which ONE of the following describes the condition of Unit 1?

A. PBA-S03 will be energized by its diesel generator.

B. PBB-S04 will be energized by its diesel generator.

C. PBA-S03 and PBB-S04 will be energized by off-site power.

D. PBA-S03 and PBB-S04 will be energized by the unit auxiliary transformers.

Answer: A Learning Objective:

L73676 Describe the response of the Non-Class AC Distribution System to a failure of power.

Reference Id: Q10257 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

Simplified Drawing Knowledge of the effect that a loss or malfunction of the ac distribution system will have on the following: Major system loads.

Answer A is correct because NAN-X03 supplies PBA-S03. Upon loss of power on PBA-S03 the DG will start and supply the bus. PBB-S04 is not affected. It does not lose off-site power. Startup transformers such as NAN-X03 can supply even numbered buses such as NAN-S05 and NAN-S06.

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ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 48 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 36062A101 Importance 3.40 3.80 Rating:

When unloading and stopping a diesel generator, the operator holds the speed adjust to the LOWER position. The operator observes the MW meter has lowered to zero and is currently increasing. This is not a desired condition because..

A. The generator is motoring.

B. The engine may overspeed if load is any LOWER.

C. The D/G trip circuit is energized at 25 KW and below.

D. The engine oil pressure will reduce below required pressure.

Answer: A Learning Objective:

L75050 Discuss the purpose and conditions under which the Diesel Generator System is designed to function.

Reference Id: Q10213 Difficulty: 2.00 Time to complete: 3 10CFR Category: CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level: Memory Question Source: INPO Bank modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40OP-9DG01, EDG Operation Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including: Significance of D/G load limits INPO Bank Q#20914 Generator motoring is occurring based on lowering speed adjust and Mw meter returning from zero.

INPO Q#20914 When unloading and stopping a diesel generator, the MINIMUM load allowed before opening the output breaker is approximately 50 kW. What is the reason for this load limitation?

Answer: generator may motor if load is any LOWER Distractor: D/G trip circuit is energized below 25 kW.

Distractor: engine may overspeed if load is any HIGHER.

Distractor: breaker has a manual interlock above 75 kW.

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ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Emergency Diesel Generator A 40OP-9DG01 3.3 Synchronization

After any instance in which an attempt was made to synch the Diesel Generator on a bus out of phase (i.e., 90o- 270o), Engineering should be contacted to perform an evaluation. The rotor pole fasteners for the Generator need to be examined to ensure they are within the specified torque values.

There is no sync-check protection on the Diesel Generator A output breaker PBA-S03B.

No provisions are made for synchronizing from the local station. Therefore, the Diesel Generator output breaker PBA-S03B shall only be closed in on a dead bus when DGA-HS-07, DG A Mode Control, is in the LOCAL position.

Two sync switches should not be placed in the on position at the same time, due to the potential to blow fuses associated with the synchroscope, resulting in DG inoperability.

3.4 Loading

The Diesel Generator Amperage and Megawatt meters are not direction sensitive.

A reverse power condition will indicate a positive value on both meters.

Operation of the Diesel Generator at loads less than 25% (1375 KW) should be minimized.

The Diesel Generator is designed to supply 5500 KW continuously, but can supply 6050 KW for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months within any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

Whenever possible, a gradual load application, as prescribed OPTRNG_EXAM Page: 65 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 49 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 36063K102 Importance 2.70 3.20 Rating:

A Deign Basis Accident has occurred.

One class 1E 4.16 KV bus has been lost due to a fault.

Based on this event the affected PK battery system will provide the power necessary to supply _____

loads for a minimum of _____ hours.

A. PK loads only, 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months B. PK loads only, 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. PK and PN loads, 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months D. PK and PN loads, 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Answer: C Learning Objective:

L74195 Describe the circuit paths to include these major components:

PK Control Centers

Batteries

Battery Chargers

Distribution Panels

RTSG Breaker Feed

PN Inverter Feed Reference Id: Q10214 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level: Memory Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

Technical Specification 3.8.4 Bases Knowledge of the physical connections and/or cause effect relationships between the DC electrical system and the following systems: AC electrical system By design, the battery supplies 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of power under full safeguards load, both DC and AC.

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ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam Palo Verde Technical Specifications DC Sources Operating B 3.8.4 BASES BACKGROUND The DC power distribution system is described in more detail in the Bases for LCO 3.8.9, "Distribution Systems- Operating," and for LCO 3.8.10, Distribution Systems Shutdown."

Each battery has adequate storage capacity to carry the required load continuously for at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months as discussed in the UFSAR, Chapter 8 (Ref. 4).

OPTRNG_EXAM Page: 67 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 50 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 36064K302 Importance 4.20 4.40 Rating:

Given the following plant conditions:

Unit 3 has suffered a loss of Non-Vital Bus NKN-D43 in conjunction with a loss of offsite power.

DG "B" Lo & Hi Priority Trouble alarms are locked in.

Which ONE of the following describes the expected response from "B" DG?

A. The "B" DG will auto start and tie to its respective bus.

B. The "B" DG will start but will not come up to speed automatically.

C. The "B" DG will not receive a start signal due to loss of control power.

D. The "B" DG will start and then immediately trip and shutdown with no cooldown cycle.

Answer: A Learning Objective:

L75077 Describe the effect of the following on the Diesel Generator:

Control Power Loss

Control Air Loss Reference Id: Q10215 Difficulty: 4.00 Time to complete: 4 10CFR Category: CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ14, Loss of Non-Class, Appendix A Knowledge of the effect that a loss or malfunction of the ED/G system will have on the following: ESFAS controlled or actuated systems.

The loss of non vital bus (NKN-D43) will not impact DG operation.

OPTRNG_EXAM Page: 68 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam LOSS OF NON-CLASS INSTRUMENT OR CONTROL POWER Appendix A, Effects of the Loss of Non-Class DC AR

Condenser Air Removal Pump D Suction Valves, ARN-UV-14/15/16, fail closed.

CD

CDN-LV-75, Condenser Draw-off Valve and Make-up Valves, CDN-LV-81/82 fail closed.

Condensate Pump A and B Miniflow Recirc Valves fail open.

Condensate Pump C Miniflow Recirc Valve fails open.

CE

Loss of Generator Hydrogen and Stator Cooling alarms and tripping functions.

CH

CHN-LC-227, VCT level controller auxiliary circuit deenergizes causing charging pump suction to swap to CHN-UV-514.

Letdown isolates, loss of power to NCN-FSL-613 auxiliary circuit closes CHN-UV-523.

DC Control Power has been lost to the VCT make-up control system. VCT make-up is not available.

CHN-FV-210X/Y fail closed.

The Charging Pump automatic control circuit deenergizes, all Charging Pumps stop.

Manual control is available.

RCP Seal Injection Flow Control Valves fail open

Loss of position indication for Letdown Control and Backpressure Control Valves.

DG

Loss of power to DGN-B01A, DG A Control Panel. DG A will trip if not in Emergency Run. Loss of alarm power.

Loss of power to DGN-B01B, DG B Control Panel. DG B will trip if not in Emergency Run. Loss of alarm power.

OPTRNG_EXAM Page: 69 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 51 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 064G2224 Importance 2.60 3.80 Rating:

Given the following plant conditions:

Unit 1 is at 100% power

The B DG is being tagged out to repair a lube oil leak.

The CRS has declared the B DG Inoperable.

Based on these conditions, what action is required to comply with LCO 3.8.1 (AC Sources - Operating)?

A. No action required for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

B. Perform 41ST-1ZZ02 (Inoperable Power Sources Action Statement) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

C. Start and fully load the A DG within 30 minutes.

D. Block fast bus transfer for NAN-S02 within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Answer: B Learning Objective:

L75083 State LCO 3.8.13, "AC Sources Operating," including bases.

Reference Id: Q10216 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level: Memory Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

Technical Specifications 3.8.1.B.

Emergency Diesel Generators: Ability to analyze the affect of maintenance activities on LCO status.

Answer B is correct based on Technical Specifications. The other distracters are not required per tech specs.

Technical Specifications 3.8.1 One DG inoperable:

Action B: Perform SR 3.8.1.1 for the OPERABLE required offsite circuit(s). within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

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ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 52 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 37073A202 Importance 2.70 3.20 Rating:

Given the following plant conditions:

A planned release of waste gas decay tank "B" is in progress.

The RU-12 reading is 1.60 E-04 uci/cc.

During the release the Effluent Tech informs the Control Room of a detector power supply failure on RU-12.

RU-12 now reads 1.00 E-07 uci/cc.

Which ONE of the following describes the expected plant response and any operator required actions due to the detector failure on RU-12? The detector failure alarm will...

A. NOT auto close Waste Gas Discharge Valves GRN-UV-34A and GRN-UV-34B.

The Control Room should verify locally that the release has been terminated.

B. NOT auto close Waste Gas Discharge Valves GRN-UV-34A and GRN-UV-34B.

The Control Room should ensure the release is secured by placing GRN-HS-34B in the close position.

C. automatically close Waste Gas Discharge Valves GRN-UV-34A and GRN-UV-34B. The Control Room should verify locally that the release has been terminated.

D. automatically close Waste Gas Discharge Valves GRN-UV-34A. The control room should ensure the release is terminated by placing GRN-HS-34B in the close position.

Answer: B Learning Objective:

16322 A2.02 Detector failure 2.7 3.2 Reference Id: Q10217 Difficulty: 4.00 Time to complete: 5 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Memory Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

74RM-9EF41, Rad Monitoring System Alarm Response Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure .

The detector failure does not automatically cause valve closure (output fails low). For this reason the Control Room must take action to close the valve.

OPTRNG_EXAM Page: 71 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam RADIATION MONITORING SYSTEM ALARM RESPONSE 74RM-9EF41 Rev. 17 Page 18 of 76 ALERT/HIGH ALARM AUTO ACTION HIGH alarm closes Waste Gas Discharge Valves GRN-UV-34A and GRN-UV-34B.

OPERATIONS RESPONSE:

1. If a waste gas system discharge is in progress, ensure that the release is secured by placing GRN-HS-34B in the Close position.

2. Notify the Radwaste Control Room and the Radiological Monitoring Technician of the alarm and that the release has been terminated.

3. If no waste gas system discharge is in progress, monitor RU-143's gas channel readings and trends to determine if an unplanned release from the waste gas system is in progress.

4. Evaluate the cause of the alarm prior to resuming any waste gas system discharge. If the alarm was caused by a malfunction of RU-12, ensure that ODCM requirements for an inoperable monitor are satisfied prior to resuming the release.

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ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 53 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 34076A302 Importance 3.70 3.70 Rating:

Given the following plant conditions:

The plant is operating at 100% power.

Essential cooling water train 'A' and Nuclear Cooling Water are cross-tied.

A low-low level in Essential Cooling Water surge tank is received.

Which ONE of the following would occur?

A. Cross-tie valves would close.

B. Essential cooling water pump would stop.

C. Demin Pump would auto start to supply makeup.

D. Standby essential cooling water pump would start.

Answer: A Learning Objective:

L56846 Describe the automatic features associated with the NC/EW Crosstie Isolation Valves.

Reference Id: Q7532 Difficulty: 2.00 Time to complete: 3 10CFR Category: CFR 55.41 (4) 55.41 (4) Secondary coolant and auxiliary systems that affect the facility.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ03, Loss of Cooling Water Ability to monitor automatic operation of the SWS, including: Emergency heat loads.

There are no auto actions for the pumps on low level and auto start on the demin pump for makeup. Answer A is correct. Ref 40OP-9EW01, section 8, step 8.1.

OPTRNG_EXAM Page: 73 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 40AO-9ZZ03, Loss of Cooling Water Appendix A, Cross-connect EW to NC INSTRUCTIONS CONTINGENCY ACTIONS

NOTE -----------------------------------------------

Cross-connecting EW and NC makes the EW Train inoperable per Tech Spec 3.7.7, Essential Cooling Water (EW) System, and the EC Train inoperable per Tech Spec 3.7.10, Essential Chilled Water (EC) System.

NOTE -----------------------------------------------

The cross-connect of Essential Cooling Water Train A with Nuclear Cooling Water will be lost on a SIAS or Essential Cooling Water surge tank A low level.

OPTRNG_EXAM Page: 74 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 54 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 38078G2411 Importance 3.40 3.60 Rating:

Given the following conditions:

The plant is at 100% power.

Instrument air header pressure is dropping.

The condensate Minimum Flow valves go to their fail positions Based on this failure, which ONE of the following describes the first impact on Main Feedwater Pump B?

A. FWP B SUCT PRESS LO alarm.

B. No impact on MFP suction pressure.

C. FWP B DISCHARGE PRESS HI alarm.

D. FWP B TRIP CKT ENERGIZED alarm.

Answer: A Learning Objective:

L56758 Predict the position of the condensate pump miniflow valve and describe the effect on main feed water flow.

Reference Id: Q10218 Difficulty: 3.00 Time to complete: 2 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ06, Loss of Instrument Air, Appendix A, page 2 of 3 provides the fail position of these valves as OPEN.

Knowledge of abnormal condition procedures Candidate must determine fail open condition of valves then assess impact on FW pumps.

They must know that the Low Suction Alarm comes in at a higher pressure than the trip circuit. Open valves decrease suction pressure on MFPs.

40SO-9ZZ06, Loss of Insturment Air Appendix A, Page 31 of 34

< 15 psig FWN-FV-1/ 2, SG Feedwater Pump A & B Miniflow Recirc Control Vlv (FO)

OPTRNG_EXAM Page: 75 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 55 Appears on: RO EXAM SRO EXAM Tier 2 Group 1 K/A # 35103A301 Importance 3.90 4.20 Rating:

Given the following plant conditions:

Containment pressure (NR) Channel A 3.1 psig

Containment pressure (NR) Channel B 2.7 psig

Containment pressure (NR) Channel C 3.1 psig

Containment pressure (NR) Channel D 2.6 psig Which ONE of the following ESFAS actuations would occur?

A. "A" Train only SIAS/CIAS.

B. "A" Train only SIAS/CIAS, and MSIS.

C. "A" and "B train SIAS/CIAS and MSIS.

D. "A" and "B train SIAS/CIAS only.

Answer: C Learning Objective:

L77167 Describe what automatically initiates the Containment Isolation Actuation System (CIAS) and its function.

Reference Id: Q10219 Difficulty: 3.00 Time to complete: 2 10CFR Category: CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

Simplified Drawing Ability to monitor automatic operation of the containment system, including: Containment isolation.

Any 2 of 4 detectors exceeding the 3 psig setpoint would cause both trains of SIAS, CIAS and MSIS to actuate. The CSAS setpoint is at a higher pressure. This question is comprehensive because the examinee must look at logic as well as setpoints.

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ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 56 Appears on: RO EXAM SRO EXAM Tier 2 Group 2 K/A # 31001K205 Importance 3.10 3.50 Rating:

The CEDM MG sets receive power directly from which ONE of the following systems?

A. NGN-L03 & NGN-L10 B. NAN-S01 & NAN-S02 C. NNN-D11 & NNN-D12 D. PKA-M41 & PKB-M42 Answer: A Learning Objective:

L80233 Explain the operation of the Motor Generator Set.

Reference Id: Q10221 Difficulty: 2.00 Time to complete: 3 10CFR Category: CFR 55.41 (3) 55.41 (3) Mechanical components and design features of the reactor primary system.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ12, Degraded Electrical Knowledge of bus power supplies to the following: M/G sets.

Procedure 40AO-9ZZ12, Degraded Electrical, section 70.0 shows the power supply as NGN-L03 and L10.

OPTRNG_EXAM Page: 77 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 57 Appears on: RO EXAM SRO EXAM Tier 2 Group 2 K/A # 32002K508 Importance 3.40 3.90 Rating:

All of the following are reasons to keep the Pressurizer within its program values of 33% to 53%

EXCEPT:

A. If Pressurizer level becomes too low, the heaters uncover and then RCS pressure can no longer be raised.

B. If water level becomes too high, the spray nozzles could become covered at which point they would no longer reduce pressure.

C. If Pressurizer level becomes too high, the steam space is reduced and the Pressurizer sprays become much less effective to reduce pressure.

D. If Pressurizer level becomes too low, a solid gas system exists, which then causes even small changes in RCS temperature to produce large variations in RCS pressure.

Answer: D Learning Objective:

L75079 Discuss the purpose and conditions under which the Pressurizer Level Control System is designed to function.

Reference Id: Q10222 Difficulty: 3.00 Time to complete: 4 10CFR Category: CFR 55.41 (2) 55.41 (2) General design features of the core, including core structure, fuel elements, control rods, core instrumentation, and coolant flow.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

NONE Knowledge of the operational implications of the following concepts as they apply to the RCS: Why PZR level should be kept within the programmed band.

Answers A, B, and C are design features of the system.

The effect of a gas system in the Pressurizer would provide more cushion to insurges caused by RCS temperature increases.

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ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 58 Appears on: RO EXAM SRO EXAM Tier 2 Group 2 K/A # 32011A102 Importance 3.30 3.50 Rating:

Given the following initial plant conditions:

U3 is at 98% power, in coastdown at EOL.

Plant parameters are normal.

The crew ensures that all three charging pumps are running.

Which ONE of the following statements correctly describes why the crew is running all three charging pumps?

A. Pre-outage operational run.

B. Provide Auxiliary Spray capability for pressure control.

C. Enhances cleanup of RCS via increased Letdown flow.

D. Maintains Pressurizer level to offset the effects of RCS average temperature drop in coastdown.

Answer: C Learning Objective:

L79585 Given the need to change pressurizer level operate the Pressurizer Level Control System Reference Id: Q10224 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (7) 55.41 (7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40OP-9ZZ10, Mode 3 to Mode 5 Ops Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR LCS controls including: Charging and letdown flows.

Answer C is correct based on procedural direction in 40OP-9ZZ10. There is no pre-op run of Charging pumps, there is no impact on inadvertent dilution and D is false.

OPTRNG_EXAM Page: 79 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 59 Appears on: RO EXAM SRO EXAM Tier 2 Group 2 K/A # 37015A401 Importance 3.60 3.60 Rating:

Given the following plant conditions:

A reactor startup is in progress

The SU AND CONT CH TRBL annunciator alarms.

Startup Control Channel counts are reading 2100 cps and increasing slowly.

Which ONE of the following statements correctly describes the first expected operator response to this?

A. Reset the Boron Dilution Alarm System.

B. Verify that the control channels are coming on scale.

C. After verifying overlap, turn off the high voltage supply to the startup channels.

D. Place CEDMCS mode selector to manual sequential in preparation for power range operations.

Answer: C Learning Objective:

L75657 Describe the conditions required to generate the following annunciators:

POSSIBLE INADVRTNT BORON DILUTION

SU AND CONT CH TRBL

HI RATE OF CHANGE OF POWER

NUC INST CH INOP

CALIB AND EX-CORE LIN PWR DEV

HI LOG PWR LVL BYP PERM

DNBR/LPD OPER BYP

LO DNBR CH PRE-TRIP/TRIP

HI LPD CH PRE-TRIP/TRIP

HI LOG PWR LVL CH PRE-TRIP/TRIP

VAR OVER PWR CH PRE-TRIP/TRIP 100866 Active Question Bank 2004 Reference Id: Q8274 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (2) 55.41 (2) General design features of the core, including core structure, fuel elements, control rods, core instrumentation, and coolant flow.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40OP-9ZZ03, Reactor Startup Ability to manually operate and/or monitor in the control room: Selection of controlling NIS channel.

OPTRNG_EXAM Page: 80 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam Original question ID: Q8274 Points: 1.00 prior to modification Given the following plant conditions:

A reactor startup is in progress

The SU AND CONT CH TRBL annunciator alarms.

Looking at the computer screen, you note that this alarm is caused by a high counts per second input.

Which ONE of the following statements correctly describes the expected operator response to this?

A. Bypass the high log power trips on B05.

B. Verify that the control channels are coming on scale.

C. Verify that the log safety channels are coming on scale.

D. After verifying overlap, turn off the high voltage supply to the startup channels.

Answer: D Answer C is correct because it is an expected alarm during a startup as the Startup channels reach the top of their range. Log channels are already on scale and Control channels are decades away from their range. The High Log Power trips are not in this range. Question is comprehensive because examinee must evaluate conditions to determine if count level and rate are appropriate, then determine what needs to be done.

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ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 60 Appears on: RO EXAM SRO EXAM Tier 2 Group 2 K/A # 37017K401 Importance 3.40 3.70 Rating:

QSPDS uses________________ to determine RCS Saturation Margin.

A. the hottest Th or Tc value B. the average Th or Tc value C. the average of CETs, Th, and Tc values D. the hottest of the top three (3) unheated junction thermocouple temperatures Answer: A Learning Objective:

L76568 Describe how QSPDS is used to determine Subcooling Margin.

100866 Active Question Bank 2004 Reference Id: Q19145 Difficulty: 2.00 Time to complete: 2 10CFR Category: CFR 55.41 (2) 55.41 (2) General design features of the core, including core structure, fuel elements, control rods, core instrumentation, and coolant flow.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

NONE Knowledge of ITM system design feature(s) and/or interlock(s) which provide for the following: Input to subcooling monitors.

The QSPDS system description has the inputs as the highest Th or Tc value. It does not use average and does not use the top 3.

OPTRNG_EXAM Page: 82 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 61 Appears on: RO EXAM SRO EXAM Tier 2 Group 2 K/A # 38033K105 Importance 2.70 2.80 Rating:

Given the following plant conditions:

Unit 1 is at 100% power

The PC cleanup pump is aligned to the spent fuel pool.

The PC cooling pump is in operation.

Spent fuel pool temperature is 114°F.

Spent fuel pool level is 137' 10" and has been noted by the AO to be slowly losing level over the past several shifts.

The AO is investigating the loss of level at this time.

Chemistry reports that the Spent Fuel Pool boron concentration is 2140 ppm.

You are directed by the CRS to add water to the SFP.

Which ONE of the following should be used to makeup to the Spent Fuel Pool?

A. RMT (Recycle Monitor Tank) Makeup to the SFP.

B. LRS (Liquid Radwaste System) Makeup to the SFP.

C. RWT (Refueling Water Tank) via Gravity Feed Makeup to the SFP.

D. RMWP (Reactor Makeup Water Pump) to the SFP via the Batch Tank Eductor.

Answer: C Learning Objective:

L77408 Explain the operation of the Spent Fuel Pool under normal operating conditions.

Reference Id: Q10225 Difficulty: 2.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ23, Loss of SFP Cooling or Level Knowledge of the physical connections and/or cause-effect relationships between the Spent Fuel Pool Cooling System and the following systems: RWST.

Procedure 40AO-9ZZ23, Loss of SFP Level or Cooling, section 3.0, lists the RWT of Answer C under borated water sources and not the others in answers A, B, and D.

Comprehensive because the examinee must recognize that due to SFP level and boron concentration that makeup must come from a borated water source.

OPTRNG_EXAM Page: 83 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 62 Appears on: RO EXAM SRO EXAM Tier 2 Group 2 K/A # 38034A301 Importance 2.50 3.10 Rating:

The "Upender Vertical Interlock" prevents...

A. driving the refueling machine over the transfer system when the Upender is vertical.

B. driving the refueling machine over the transfer system when the Upender is NOT vertical.

C. the Upender from moving IF the refueling machine is too close AND the Upender is vertical.

D. the Upender from moving IF the refueling machine is out of the RTZ (Refueling Transfer Zone) AND the Upender is NOT vertical.

Answer: B Learning Objective:

100866 Active Question Bank 2004 L97801 Identify the protective interlocks associated with the refueling machine.

Reference Id: Q67350 Difficulty: 3.00 Time to complete: 2 10CFR Category: 55.41 (13) 55.41 (13) Procedures and equipment available for handling and disposal of radioactive materials and effluents.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

78OP-9FX01, Refueling Machine Ops Ability to monitor automatic operation of the Fuel Handling System including: Travel limits.

Answer B is correct because the Upender Vertical Interlock is for the refueling machine and is a concern when the Upender is not vertical.

OPTRNG_EXAM Page: 84 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 63 Appears on: RO EXAM SRO EXAM Tier 2 Group 2 K/A # 34056A204 Importance 2.60 2.80 Rating:

Given the following plant conditions:

Unit 1 operating at 100% full power.

A fault occurs internally in NBN-S01, tripping the normal supply breaker on an 86 lockout.

Which ONE of the following describes the status of NBN-S01 and plant response to this event?

A. Deenergized, resulting in small transient on secondary plant.

B. Deenergized, resulting in a loss of main feedwater pump "B" and a reactor power cutback.

C. Energized from automatically transferring to NBN-S02, resulting in little or no transient.

D. Momentarily loses power until automatic transfer to NBN-X02, resulting in a loss of main feedwater pump "B" and reactor power cutback.

Answer: B Learning Objective:

L67448 Describe the interlocks associated with the condensate pumps.

L56805 Determine if the RPCB (LOFP) AOP should be executed.

Reference Id: Q9032 Difficulty: 3.00 Time to complete: 3 Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

NONE Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of condensate pumps.

Answer B is correct because a fault on NBN-S01 locks out any supply to it. This results in a loss of one feed pump which causes a Reactor Power Cutback.

OPTRNG_EXAM Page: 85 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 64 Appears on: RO EXAM SRO EXAM Tier 3 K/A # 39071K304 Importance 2.70 2.90 Rating:

Given that a release of gaseous decay tank GRN-X02B is in progress. Which ONE of the following will NOT cause an automatic termination of the release?

A. High waste gas discharge flow.

B. High waste gas discharge pressure.

C. High radiation level in the discharge line.

D. High radiation on the radwaste building ventilation exhaust filter inlet.

Answer: D Learning Objective:

L78943 Explain the operation of the following components under normal operating conditions:

Gas Surge Header

Gas Surge Header Containment Isolation Valve

Gas Surge Tank (GRN-X01)

Gas Compressor Pre-filters (GRN-F02A, F02B)

Gas Compressors (GRN-C01A, C01B)

Decay Tanks (GRN-X02A, X02B, X02C)

Decay Tank Disch Header Isolation Valves (GRN-UV-34A, 34B)

Gaseous Discharge Header Isolation Valves (HS-34A and 34B)

Radiation Monitor (RU-12)

Gaseous Discharge Flow Control Valve (GRN-FV33)

Reference Id: Q6739 Difficulty: 3.00 Time to complete: 5 10CFR Category: CFR 55.41 (4) 55.41 (4) Secondary coolant and auxiliary systems that affect the facility.

Cognitive Level: Memory Question Source: PV Bank Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

Simplified Drawing Knowledge of the effect that a loss or malfunction of the Waste Gas Disposal System will have on the following: Ventilation system.

WGDT isolates on A, B, & D but not on High Rad off the exhaust filter inlet.

OPTRNG_EXAM Page: 86 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam Original question ID: Q6739 Points: 1.00 prior to modification Given the following plant conditions:

The control room operator is venting the reactor drain tank to the gaseous surge header.

Suddenly the tank pressure stops decreasing.

Which ONE of the following auto actions would stop the flow, isolating the reactor drain tank from the gaseous radwaste system?

A. Radiation monitor RU-12 in alarm.

B. Radiation monitor RU-15 in alarm.

C. Containment isolation actuation signal occurs.

D. Containment recirculation actuation signal occurs.

Answer: C OPTRNG_EXAM Page: 87 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 65 Appears on: RO EXAM SRO EXAM Tier 3 K/A # 38086K604 Importance 2.60 2.90 Rating:

Which ONE of the following describes the effect a loss of essential lighting will have on the PVNGS Fire Protection System?

A. The In-plant communication system (QF) will become unavailable.

B. The on-site deep well pumps will not auto start to provide makeup to the fire water tanks.

C. The motor driven and diesel fire pumps will not auto start to maintain fire main header pressure.

D. Local control panels that provide power to fire, smoke and heat detectors will become unavailable.

Answer: D Learning Objective:

L75414 Describe the Fire Detection and Alarm Sub-system of the Fire Protection System.

Reference Id: Q10229 Difficulty: 3.00 Time to complete: 2 10CFR Category: CFR 55.41 (4) 55.41 (4) Secondary coolant and auxiliary systems that affect the facility.

Cognitive Level: Memory Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

NONE Knowledge of the effect of a loss or malfunction on the Fire Protection System following will have on the: Fire, smoke, and heat detectors.

A, B, C are incorrect because Essential Lighting does not impact the QF system, deep well pumps or fire pumps.

OPTRNG_EXAM Page: 88 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 66 Appears on: RO EXAM SRO EXAM Tier 2 Group 2 K/A # 2116 Importance 2.90 2.80 Rating:

You are walking through the Unit 1 Turbine Building and notice a seriously injured person on the floor near a scaffold.

Which ONE of the following should be the first person or group notified?

A. Security at extension 4444.

B. Fire Protection at extension 1612.

C. The Site Manager at extension 2219.

D. The Unit 1 Shift Manager at extension 1206.

Answer: A Learning Objective:

L59592 Provide accurate, clear and concise verbal communications.

Reference Id: Q10230 Difficulty: 2.00 Time to complete: 2 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Memory Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

GET, Conduct of Shift Operations 40EP-9OP02, 14DP-0FP32.

Conduct of Operations: Ability to operate plant phone, paging system, and two-way radio.

Answer A is correct in accordance with 14DP-0FP32, Emergency Notification and Response.

OPTRNG_EXAM Page: 89 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 14DP-0FP32 Page 3 of 41 1.0 PURPOSE AND SCOPE 1.1 The purpose of this procedure is to describe the actions of personnel upon discovering a fire, hazardous material incident, medical emergency or emergency rescue (special duty) within the boundary of PVNGS.

1.2 This procedure also defines actions to be taken after a fire, hazardous material incident, medical emergency, special duty or drill has been reported.

2.0 RESPONSIBILITIES 2.1 All Plant Personnel 2.1.1 All plant personnel are responsible to notify Security at extension 4444 of any fire, hazardous material, medical emergency or rescue emergency (special duty) onsite OPTRNG_EXAM Page: 90 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 67 Appears on: RO EXAM SRO EXAM Tier 2 Group 2 K/A # 2127 Importance 2.80 2.90 Rating:

Given the following conditions:

Unit 1 at 100% power COLSS is in service CPCs are in service CEACs are in service A 12 finger CEA drops to the bottom of the core and picks up the Dropped Rod Contact How will COLSS and CPCs respond to this event?

COLSS will A. Initiate a reactor trip, CPCs will initiate a single channel trip.

B. initiate a reactor trip, CPCs will initiate a reactor trip.

C. actuate various alarms, CPCs will generate a single channel trip.

D. actuate various alarms, CPC will initiate a reactor trip.

Answer: D Learning Objective:

L77046 Describe the purpose and conditions under which the Core Operating Limit Supervisory System is designed to function.

Reference Id: Q3304 Difficulty: 2.00 Time to complete: 3 10CFR Category: CFR 55.41 (8) 55.41 (8) Components, capacity, and functions of emergency systems.

Cognitive Level: Memory Question Source: PV Bank Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

NONE Conduct of Operations: Knowledge of system purpose and or function.

Answer D is correct because COLSS is a monitoring system only and provides no auto action, while CPC provides protection.

OPTRNG_EXAM Page: 91 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam Question prior to ID: Q3304 Points: 1.00 modification Which statement describes the functional relationship between COLSS and CPCs?

COLSS provides...

A. indication and alarms, while CPCs provide automatic protection.

B. automatic protection, while CPCs only provide indication and alarms.

C. automatic control functions, while CPCs provide automatic protection.

D. automatic protection, while CPCs provide automatic control functions.

Answer: A OPTRNG_EXAM Page: 92 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 68 Appears on: RO EXAM SRO EXAM Tier 3 K/A # 2128 Importance 3.20 3.30 Rating:

With the reactor at 100% power, what is the normal condition of the Safety Injection Tank (SIT) outlet valves and why are they in that condition?

A. The valves are open and downpowered to maintain it as a passive system.

B. The valves are open and powered up to provide for rapid closure after a SIAS.

C. The valves are closed and downpowered to prevent voiding the RCS with nitrogen after a SIAS.

D. The valves are closed and downpowered up to allow the SIAS to automatically open the valves.

Answer: A Learning Objective:

L74621 Describe how the FWFT System is supported by the following system interfaces:

RPCB

Main Turbine System

Auxiliary Steam System

Feedwater Control System

Feedwater Heater Extraction Steam and Drain System

Gland Steam System

Turbine Cooling Water System

Condensate System L82441 Explain the operation of the MFWP Turbine under normal operating conditions.

Reference Id: Q9776 Difficulty: 2.00 Time to complete: 2 10CFR Category: CFR 55.41 (4) 55.41 (4) Secondary coolant and auxiliary systems that affect the facility.

10CFR Category: CFR 55.41 55.41 (4) Secondary coolant and auxiliary systems that affect the (4)CFR 55.41 (8) facility.55.41 (8) Components, capacity, and functions of emergency systems.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

NONE Knowledge of the purpose and function of major system components and controls.

By procedure and design the SIT outlet valves must remain open and down powered because they are a totally passive system relying on gas pressure as a motive force for injection. Powering them up could lead to closure and the loss of an ESF system.

OPTRNG_EXAM Page: 93 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 69 Appears on: RO EXAM SRO EXAM Tier 3 K/A # 2.2.11 Importance 2.50 3.40 Rating:

A Temporary Modification can remain active...

A. a maximum of 3 months.

B. a maximum of 6 months.

C. as long as it is needed as verified by the performance of a Justification Review.

D. an indefinite period of time, as long as an initial 50.59 screening was performed.

Answer: C Learning Objective:

L57330 Describe the "Justification Review" of plant T-Mods.

Reference Id: Q10022 Difficulty: 3.00 Time to complete: 2 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

81DP-0DC17, Temporary Modification Control Knowledge of the process for controlling temporary changes Answer C is correct in accordance with 81DP-0DC17, Temporary Modifications, section 3.2.4.

OPTRNG_EXAM Page: 94 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 70 Appears on: RO EXAM SRO EXAM Tier 3 K/A # 2227 Importance 2.60 3.50 Rating:

Which ONE of the following is the Reactor Operator, located in the Control Room, responsible for during refueling operations?

A. The MBA transfer sheet status.

B. The Fuel Building and Core status board.

C. Subcritical multiplication status of the core.

D. Communications with the Refuel Machine and SFHM operators.

Answer: C Learning Objective:

100866 Active Question Bank 2004 10755 State the communication requirements during refueling.

L114367 Describe the refueling process.

Reference Id: Q9272 Difficulty: 2.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

T.S. 3.9.101 Knowledge of the refueling process Answer C is correct.

A, B, & D are accountable to the SRO and Rx Engineer.

OPTRNG_EXAM Page: 95 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 71 Appears on: RO EXAM SRO EXAM Tier 3 K/A # 234 Importance 2.50 3.10 Rating:

According to 10 CFR 20, which ONE of the following correctly lists the requirements which must be met if the whole body dose annual limit is to be exceeded?

A. You are NOT permitted to exceed the annual whole body dose limit.

B. Can NOT exceed 3 Rem/Qtr whole body, and you must have planned special exposures documented.

C. Can NOT exceed 25 Rem whole body lifetime dose, and you must have planned special exposures documented.

D. Planned special exposures need to be documented only if you might exceed your 5(N-18) Rem whole body lifetime dose.

Answer: C Learning Objective:

L59736 Given a set of plant conditions, identify the Emergency Coordinator's responsibilities associated with Emergency Exposure Reference Id: Q10255 Difficulty: 2.00 Time to complete: 2 10CFR Category: CFR 55.41 (13) 55.41 (12) Radiological safety principles and procedures.

Cognitive Level: Memory Question Source: INPO Bank NOT modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

10CFR20 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

INPO Q# 18497 OPTRNG_EXAM Page: 96 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 72 Appears on: RO EXAM SRO EXAM Tier 3 K/A # 2311 Importance 2.70 3.20 Rating:

Given the following plant conditions:

The Unit 2 control room operators are responding to a SGTR on #1 SG.

Condenser pressure is 3 inches Hg.

Aux Feedwater pump A is running.

RCPs 1A and 2A are running.

Both Main Feedwater pumps are tripped.

DG B is running, supplying its bus.

ESF transformer NBN-X04 has a sudden pressure trip.

Bus NNN-D15 is deenergized.

In order to cool down the RCS to isolate the affected SG, the operators dump steam to the____

using SG.

A. condenser, #2 B. atmosphere, #2 C. condenser, #1 and #2 D. atmosphere, #1 and #2 Answer: C Learning Objective:

L11218 Given that the SGTR EOP is being implemented describe the SGTR EOP mitigation strategy Reference Id: Q10233 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

10CFR Category: CFR 55.41 55.41 (10) Administrative, normal, abnormal, and emergency (10)CFR 55.41 operating procedures for the facility.55.41 (12) Radiological safety (13) principles and procedures.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40DP-9AP09, SG Tube Rupture Tech Guide Ability to control radiation releases.

Answer C is correct because with all equipment available the condenser is preferred and both SGs are used to dump steam in accordance with 40DP-9AP09, SGTR Tech Guide.

Question is comprehensive based on examinee must evaluate plant conditions to determine viable options for cooling down.

OPTRNG_EXAM Page: 97 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 73 Appears on: RO EXAM SRO EXAM Tier 3 K/A # 2413 Importance 3.30 3.90 Rating:

Given the following plant conditions:

A reactor trip has occurred

SPTAs are in the process of being performed.

Based on these conditions, alarm response procedures do not have to be used.

A. until the plant stabilizes.

B. until the EOPs are exited.

C. until directed by the EOPs.

D. until directed by the SPTAs.

Answer: A Learning Objective:

100866 Active Question Bank 2004 L10336 Given that an EOP is being implemented describe the process for performing a procedural step in another manner than the one listed 16298 Identify the process for performing a procedural step in another manner than the one listed.

Reference Id: Q9550 Difficulty: 2.00 Time to complete: 2 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40DP-9AP16, EOP Users Guide Knowledge of crew roles and responsibilities during EOP flowchart use.

Answer A is correct by EOP Users Guide.

Answer B conditions could take days.

Answers C and D are incorrect because the EOPs do not direct ARP use.

OPTRNG_EXAM Page: 98 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL EMERGENCY OPERATING PROCEDURE USERS GUIDE 40DP-9AP16 Page 24 of 25 28.0 USE OF ALARM RESPONSE PROCEDURES

1. Following reactor trip, there are so many alarms that it may not be practical to use Alarm Response procedures, but they can be directed by the CRS. The CRS should resume the use of alarm response procedures after the plant stabilizes.

2. The primary and secondary operators should observe, and acknowledge alarms.

3. Alarm response procedures in progress when the reactor trips and SPTAs are entered may be continued until the first priority actions are done.

4. Use ANY of the following guidance during use of the LMFR:

OPTRNG_EXAM Page: 99 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 74 Appears on: RO EXAM SRO EXAM Tier 3 K/A # 2419 Importance 2.70 3.70 Rating:

An EOP step which may be performed out of sequence is designated with...

A. shading.

B. an asterisk.

C. an explanatory note.

D. a boxed outline around the step.

Answer: B Learning Objective:

100866 Active Question Bank 2004 L10330 Given that an ORP is being implemented describe the order in which procedural steps are performed during the performance of the EOP Reference Id: Q9417 Difficulty: 2.00 Time to complete: 2 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40DP-9AP16, EOP Users Guide Answer B is correct based on the EOP Users Guide, 40DP-9AP16, step 12.0. The asterisk is the designated means for this purpose.

OPTRNG_EXAM Page: 100 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam 75 Appears on: RO EXAM SRO EXAM Tier 3 K/A # 2443 Importance 2.80 3.50 Rating:

Following the initial declaration of a Notification of Unusual Event (NUE), the STSC (Satellite Technical Support Center) Communicator must commence notification of state and county agencies within...

A. 15 minutes on NAN Phone.

B. 30 minutes on PBX Phone.

C. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months NAN Phone.

D. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months on PBX Phone.

Answer: A Learning Objective:

L65140 Given an emergency event, direct emergency plan actions as the Emergency Coordinator Reference Id: Q10214 Difficulty: 2.00 Time to complete: 3 10CFR Category: CFR 55.41 (10) 55.41 (10) Administrative, normal, abnormal, and emergency operating procedures for the facility.

Cognitive Level: Memory Question Source: PV Bank NOT Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

EPIP-01, STSC Knowledge of emergency communications systems and techniques Only the NAN or radio is used for the communication. By EPIP-01, the notification must be within 15 minutes.

OPTRNG_EXAM Page: 101 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam EPIP-01, STSC Actions Page 4 of 54 2.0 EXPECTATIONS FOR EMERGENCY PLAN IMPLEMENTATION The on-duty Shift Manager is the senior licensed member with the ultimate responsibility to protect the health and safety of the public. This Shift Manager responsibility is of the highest priority and supersedes all other responsibilities, including event mitigation. When an event occurs, the Shift Manager should remain in, or return to the Control Room and perform emergency plan reviews and classifications as required. Qualified personnel at the scene of the problem will assess any situation and relay information to the control room. The Shift Manager is responsible to ensure the initial classification and proper notifications are completed. During emergency situations wherein the Shift Manager is physically prevented from fulfilling emergency plan requirements (e.g. unable to return to the control room, personnel injury), the following hierarchy shall be followed:

Plant Transient not in progress - The Control Room Supervisor (CRS) is responsible for emergency plan implementation until relieved by the Shift Manager. The CRS is responsible to make the initial classification prior to being relieved as EC.

Plant transient in progress - The CRS is responsible to assign an EC qualified individual to implement the Emergency Plan until relieved by the Shift Manager. The assigned individual should be in order of preference: Unaffected Unit Shift Manager or another qualified Emergency Coordinator (EC).

NUREG 0654 requires notification of State/Local officials and the NRC within 15 minutes and 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months respectively, following declaration of an emergency condition. Regulations do not specify a time limit for classifying an emergency. However, consistent with the NRC position published in Emergency Preparedness Position #2 dated 8/95, it is PVNGS management's expectation that 15 minutes is an appropriate limit for classification of an event once indications are available to the Control Room operators that an Emergency Action Level (EAL) has been met. Failure to recognize that an EAL has been met does not delay commencement of the 15 minute classification time-clock.

OPTRNG_EXAM Page: 102 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Reactor Operator NRC Exam Cognitive Level Summary Number of questions linked: 75 Percentage Memory 34 45%

Comprehension / Analysis 41 55%

Question Source Summary Number of questions linked to source: 75 Percentage New 25 33%

Modified INPO Bank Modified 1 PV Bank Modified 8 Total Modified 9 12%

Bank INPO Bank Not Modified 4 PV Bank Not Modified 37 Total BANK 41 55%

OPTRNG_EXAM Page: 103 of 103 06/14/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 1 Appears on: SRO EXAM K/A # 42015AA210 Importance 3.70 Rating:

Given the following plant conditions:

The unit is at 100% power and the following plant conditions exist for 1A RCP:

The following Board Annunciators are in alarm:

RCP RCP MULTIPOINT 1A 1A RECORDERS LO TRBL ABOVE NCW SETPOINT (4D01A) (4A02A) (7B06B)

Nuclear Cooling water flow (NCN FI 475) - 420 gpm

Upper Thrust bearing temperature - 256°F

Lower Journal bearing temperature - 205°F

Upper Journal bearing temperature - 195°F

Number 1 Seal inlet pressure - 2255 psig

Controlled bleedoff flow - 6 gpm.

Based on these indications the crew should A. manually trip the reactor, then trip RCP 1A.

B. perform a rapid plant S/D, then trip RCP 1A.

C. stop all but one normal chiller, ensure its NC valve is closed.

D. continue plant operations, increase monitoring of RCP1A parameters for trends.

Answer: A Learning Objective:

L10103 Given the status of NC and RCP seal injection describe the limitations on RCP operation without NC Reference Id: Q0693 Difficulty: 2.00 Time to complete: 3 10CFR Category: 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ04, RCP Emergencies.

Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): When to secure RCPs on loss of cooling or seal injection The RCP must be secured immediately based on High Upper Thrust brg temp @ 245 °F.

B, C, D incorrect, not IAW procedure.

OPTRNG_EXAM Page: 1 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions)

REACTOR COOLANT PUMP EMERGENCIES 40AO-9ZZ04 Page 5 of 31 3.0 ABNORMAL RCP MOTOR OR BEARING PARAMETERS INSTRUCTIONS CONTINGENCY ACTIONS

___ 1. IF ANY RCP NC low flow annunciators are in alarm, THEN PERFORM 40AO-9ZZ03 Loss of Cooling Water Section 4.0.

___ 2. IF ANY RCP Upper Thrust Bearing temperature is 245 °F or more, (RCN-TE-156/166/176/186)

OR motor amps is 520 amps or more, THEN perform the following:

a. Ensure the Reactor is tripped.

b. Stop the affected RCP.

c. GO TO the appropriate procedure for the current plant conditions.

___ 3. IF ANY RCP Upper Thrust Bearing (temperature is trending to 245 °F, THEN consider starting the Hydraulic Oil Lift Pump to slow the rate of temperature rise.

OPTRNG_EXAM Page: 2 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 2 Appears on: SRO EXAM K/A # 42025AA202 Importance 3.80 Rating:

Given the following plant conditions:

Unit 1 is in Mode 5.

RCS Pressure is 195 psia.

SDC Train A is in service using LPSI A pump.

RU-2, Essential Cooling Water Monitor, is in alarm.

RU-10, Auxiliary Building Ventilation Exhaust, is in alarm.

EW Surge Tank High/Low, is in alarm.

Which ONE of the following describes the plant condition and the appropriate procedure required to mitigate or correct the condition?

A leak exists in the A. LPSI A pump seal. Enter the Excess RCS leak rate Abnormal Operating Procedure.

B. LPSI A pump seal. Enter the Loss of Coolant Accident Emergency Operating Procedure.

C. SDC Heat Exchanger. Enter the LMFRP Emergency Operating Procedure.

D. SDC Heat Exchanger. Enter the Radiation Monitoring Alarm Response.

Answer: C Learning Objective:

L65400 Describe how the Essential Cooling Water system is supported by the following systems:

Radiation Monitoring (SQ)

Essential Chilled Water (EC)

Reference Id: Q10237 Difficulty: 3.00 Time to complete: 3 10CFR Category: 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

LMFRP pg 3 of 334 Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System: Leakage of reactor coolant from RHR into closed cooling water system or into reactor building atmosphere.

The EW surge tank is located on the 120 elevation. The Aux Bldg Rad monitor samples from different Aux Bldg elevations. The surge tank would overflow onto the 120. The LMFRP is appropriate for this condition.

A, B incorrect, no indication given to support leak from the LPSI seal D incorrect, the rad monitor alarm response by itself would not mitigate the condition.

OPTRNG_EXAM Page: 3 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions)

LOWER MODE FUNCTIONAL RECOVERY 40EP-9EO11 Page 3 of 334 1.0 ENTRY CONDITIONS The Lower Mode Functional Recovery Procedure may be entered when ALL of the following conditions exist:

1. The unit is in Mode 4, 5, or 6 with LTOP in service.

And

2. An Emergency Operating Procedure is NOT currently in use.

And

3. ANY of the following conditions exist:

The CRS directs entering the LMFR

Any Lower Mode Safety Function Status Check Acceptance Criteria are NOT met

An Abnormal Operating Procedure directs entering the LMFR

An Alarm Response Procedure directs entering the LMFR

Any condition, or pattern of symptoms that are not being mitigated by the procedure(s) in use (Abnormal, Alarm or Normal)

Any condition, or pattern of symptoms for which no procedural guidance can be identified OPTRNG_EXAM Page: 4 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 3 Appears on: SRO EXAM K/A # 42040AA205 Importance 4.50 Rating:

Given the following plant conditions:

Unit 1 has tripped.

Containment pressure is at 12 psig and slowly lowering.

Containment temperature is 186°F

Containment Spray Flow is 4400 gpm in both headers.

PZR level is 20% and rising.

RVUH is 100%.

RCS subcooling is 112°F

SG 1 is at 24% WR (increasing) and being fed from AFW at 505 gpm.

SG 2 is below the indicated level.

Both HPSI pumps are injecting into the RCS.

Based on these conditions, the CRS should direct the operator to...

A. maximize feed flow to SG 1.

B. start throttling HPSI discharge.

C. override and isolate Containment Spray flow.

D. lower pressure in both SGs until Thot is below 540 °F.

Answer: B Learning Objective:

L11202 Given conditions of an ESD describe the mitigating strategy outlined in the ESD EOP Reference Id: Q10238 Difficulty: 2.00 Time to complete: 3 10CFR Category: 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level: Comprehension / Anal Question Source: Modified PV Bank Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40EP-9EO05, ESD, step 16 Ability to determine and interpret the following as they apply to the Steam Line Rupture:

When ESFAS systems may be secured.

A incorrect, SG Level is recovering. Maximizing feed flow would compound the C/D rate.

B correct, conditions given meet SI throttle criteria for Harsh Containment C incorrect, NOT IAW procedure D incorrect, correct if examinee believed a SGTR occurred.

OPTRNG_EXAM Page: 5 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions)

Original PV Question prior to modifying ID: Q9037 Points: 1.00 Given the following plant conditions:

An ESD has occurred due to a steam line break inside containment.

The Operating crew has just entered in the ESD procedure.

Containment pressure peaked and is stable at 9 psig Containment temperature is 186°F.

PZR level is 12% and rising.

RVUH is 100%.

RCS subcooling is 112°F SG 1 is at 24% WR (increasing) and being fed from AFW at 505 gpm.

SG 2 is below the indicated level.

Both HPSI pumps are injecting into the RCS.

Based on these conditions, the operator should...

A. throttle HPSI immediately.

B. maximize feedflow to SG 1.

C. throttle HPSI when PZR level reaches 15%.

D. maximize feedflow to SG 1 and throttle HPSI when PZR level reaches 15%.

Answer: C OPTRNG_EXAM Page: 6 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions)

EXCESS STEAM DEMAND 40EP-9EO05 Page 14 of 47 CAUTION Throttling HPSI injection valves will cause erosion damage to downstream piping.

16. IF at least one HPSI Pump is operating, AND ALL of the following conditions exist:

RCS is 24°F [44°F] or more subcooled

Pressurizer level is greater than 10% [15%] and NOT lowering

The unisolated Steam Generator is available for RCS heat removal with level being maintained within or being restored to 45 - 60%

[45 - 60%] NR

RVLMS indicates RVUH level is 16% or more THEN throttle HPSI flow or stop the HPSI Pumps one pump at a time.

17. IF any of the Safety Injection throttlecriteria can NOT be maintained, THEN perform the following:

a. Raise HPSI flow.

b. Start HPSI pumps as needed.

OPTRNG_EXAM Page: 7 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 4 Appears on: SRO EXAM K/A # 42057AA214 Importance 3.60 Rating:

Given the following plant conditions:

Unit 3 is operating in Mode 1.

Voltmeter PKA-EI-M41 indicating zero volts.

125V IE CC M41 CHGR A/AC PNL D21 TRBL alarm (1A04A).

Based on these indications, the CRS should enter the __________ and ________.

A. Loss of Class Instrument Power AOP. Verify that PNA-D25 is energized.

B. Loss of Class Instrument Power AOP. Bypass all PPS Channel A and B trip bistables.

C. Degraded Electrical AOP. Align power for class instruments to its alternate power supply.

D. Degraded Electrical AOP. Restore power to affected instrumentation in parallel with performance of the Reactor Trip EOP.

Answer: A Learning Objective:

L74141 Explain the operation of the Static Transfer Switch which is provided on Inverters in Units 2 and 3.

Reference Id: Q10239 Difficulty: 3.00 Time to complete: 2 10CFR Category: 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ13, Loss of Class Inst or Control Power Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: That substitute power sources have come on line on a loss of initial AC.

C, D incorrect, PN system has a static transfer switch that on a loss of power to the inverter auto swaps power to the AC power supply, to which it remains aligned until manually transferred back to the inverter, RTSG Brkr A would open, i.e. 1/2 Rx Trip signal.

A is correct for Unit 2 & 3 only. PNA-D25 would auto realign its power supply and remain energized B would be a correct action for Unit 1 IAW Loss of class power.

LOSS OF CLASS INSTRUMENT OR CONTROL POWER Page 5 of 95 3.0 LOSS OF PKA-M41 OR PKA-D21

___ 5. Check that PNA-D25 is energized OPTRNG_EXAM Page: 8 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 5 Appears on: SRO EXAM K/A # 058G244 Importance 4.30 Rating:

Given the following plant conditions:

Unit 1 Reactor has tripped

The CRS is proceeding through the SPTAs.

Upon requesting the status of the electric plant, the RO informs him of the following:

PBB-S04 is energized from EDG B PNA-D25 is energized from Inverter PNA-N11 PKA-M41 is energized from it's battery PKC-M43 is energized from it's battery All other buses are DE-ENERGIZED Based on these conditions, upon completing the remaining steps of the SPTAs, the CRS should transition to which ONE of the following procedures?

A. Reactor Trip B. LOOP (Loss of Offsite Power)

C. FRP (Functional Recovery Procedure)

D. Stay in the SPTAs and perform the "Degraded Electrical" AOP Answer: C Learning Objective:

56297 Given the FRP is being performed and given specific plant conditions determine if the selected MVDC success path safety function status checks are being met Reference Id: Q10240 Difficulty: 3.00 Time to complete: 4 10CFR Category: 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40EP-9EO02, Rx Trip Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures The Reactor Trip procedure can not be entered because to meet the Maintenance of Vital Auxiliaries section at least one of the following trains of PK and PN is energized and is on the same train as the powered vital 4.16 kV AC bus. Therefore the only appropriate procedure to enter is the Functional Recovery Procedure. The other electrical AOP/EOP procedures do not handle a MVDC bus plus philosophy issue.

OPTRNG_EXAM Page: 9 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions)

REACTOR TRIP 40EP-9EO02 Revision 7 Page 9 of 13 SAFETY FUNCTION:

2. Maintenance of Vital Auxiliaries ACCEPTANCE CRITERIA:

a. At least one vital 4.16 kV AC bus energized.

b. At least one non-vital 13.8 kV AC bus energized.

c. At least one non-vital 4.16 kV AC bus energized.

d. At least one of the following trains of PK and PN is energized and is on the same train as the powered vital 4.16 kV AC bus.

PKA-M41, PKC-M43, and PNA-D25

PKB-M42, PKD-M44, and PNB-D26 OPTRNG_EXAM Page: 10 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 6 Appears on: SRO EXAM K/A # 42062AA202 Importance 3.60 Rating:

Given the following plant conditions:

Unit 2 is at 100% power

The Train A Essential Spray Pond System is running in support of maintenance testing on the A DG.

The A DG is running at full load.

The ESP SYS TRBL annunciator alarms.

SUPPLY FLOW as read on SPN-FI-5 indicates 16,500 gpm.

RETURN FLOW as read on SPN-FI-5 indicates 14,300 gpm.

Pump discharge pressure is 50 psig.

Which ONE of the following actions should be taken to mitigate or correct the above condition?

A. Do NOT stop the ESP pump, secure the DG to prevent overheating.

B. Stop the ESP pump, an indication of a pipe break in the system exists.

C. Do NOT stop the ESP pump or the DG. Dispatch an AO to throttle ESP flow.

D. Stop the DG and leave the ESP pump running for 30 minutes to allow for cooldown.

Answer: B Learning Objective:

L81986 During a loss of TC flow Start the standby TC pump Reference Id: Q5093 Difficulty: 2.00 Time to complete: 3 10CFR Category: 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

41AL-1RK2A, ESP SYS TRBL Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: The cause of possible SWS loss The examinee needs to ascertain a pipe break by the indications given. The Alarm Response directs securing the pump.

OPTRNG_EXAM Page: 11 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions)

Procedure Number 41AL-1RK2A 45 Page 106 of 130 Window Label ESP SYS TRBL Page 7 of 14 GROUP C RESPONSE SECTION PT. ID POSSIBLE CAUSE SETPOINT SPFS5 Essential Spray Pond Loop A Differential Flow Hi 1500 gpm SPFS6 Essential Spray Pond Loop B Differential Flow Hi 1500 gpm AUTO ACTION None FIRST PRIORITY OPERATOR ACTION NOTE A high differential flow is indicative of a piping rupture.

Check the alarm by monitoring essential spray pond A and B supply and return flow dual indicators gages SPN-FI-5 and SPN-FI-6 for normal flow of = 16,300 gpm.

OPTRNG_EXAM Page: 12 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 7 Appears on: SRO EXAM K/A # 42003AA204 Importance 3.60 Rating:

Given the following plant conditions:

Unit 1 is operating at 100% power.

A Regulating Group 4 CEA drops to the bottom of the core.

The crew responds in accordance with the abnormal operating procedure for a dropped rod.

The I&C technician contacts the control room and informs them that the dropped CEA can be recovered.

The CEDMCS control switch has been repositioned to "Manual Individual".

Group 4 is selected.

The dropped rod has been selected.

The operator takes the shim switch to the withdrawal position.

No other operator action has been taken.

Based on these conditions, the operating crew can...

A. move the rod with no other operator action required.

B. move the rod by bypassing the CWP (CEA withdrawal prohibit).

C. NOT move the rod due to an AMI (Automatic Motion Inhibit).

D. NOT move the rod due to an AWP (Automatic Withdrawal Prohibit).

Answer: B Learning Objective:

L56642 Describe the required action if any CEA(s) is deviating by 6.6 inches or more from its group.

Reference Id: Q10242 Difficulty: 3.00 Time to complete: 4 10CFR Category: 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ11, CEA Malfunction Ability to determine and interpret the following as they apply to the Dropped Control Rod:

Rod motion stops due to dropped rod.

A incorrect, a CWP is in due to deviation.

C,D incorrect, a deviation causes a CWP not an AWP. No indication of AMI is present.

B correct, a CWP is generated due to deviation of > 5.5" w/i a subgroup. It may be bypassed to allow rod w/d.

OPTRNG_EXAM Page: 13 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions)

CEA MALFUNCTIONS 40AO-9ZZ11 Page 18 of 55 3.0 DROPPED OR SLIPPED CEA MODE 1 OR 2 INSTRUCTIONS

____28. Contact Operations Management to determine action to be taken prior to attempting to align the affected CEA.

____29. IF the affected CEA can be moved, AND Operations Management concurs, THEN perform the following:

a. Determine the minimum CEA withdrawal time.

REFER TO Appendix C, CEA Withdrawal Time Limits.

b. IF a CWP has occurred, AND the CEA(s) is to be withdrawn, THEN press and hold the CWP Bypass pushbutton during CEA withdrawals.

OPTRNG_EXAM Page: 14 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 8 Appears on: SRO EXAM K/A # 42028AA203 Importance 3.30 Rating:

Given the following plant conditions:

Unit 3 is operating at 100% power.

Pressurizer LEVEL SETPOINT CONTROL (RCN-LIC-110) is in Remote-Auto.

The LEVEL CONTROL SELECTOR (CHANNEL X/Y) switch is in CH-Y.

The HEATER CONTROL SELECTOR LEVEL TRIP (CHANNEL X/Y) switch is in "BOTH".

A leak develops on the reference leg of Level Transmitter 110Y. This leak exceeds the capacity of the condensing chamber's ability to keep the reference leg full.

Because of this, you should expect indicated level to...

A. increase leading to an increase in letdown flow.

B. increase leading to an increase in pressurizer pressure.

C. decrease leading to the auto-start of the standby charging pump.

D. decrease leading to a reduction in letdown flow and eventual trip of all heaters.

Answer: A Learning Objective:

L67961 Describe the Control Room indications and controls (including any automatic functions) associated with the CVCS Charging flowpath to include the following:

Charging Pump Discharge Header Pressure (CHA-PI-212)

Charging Pump Discharge Header Flow (CHB-FI-212)

Regen Heat Exchanger Temperature (CHN-TI-229)

Reference Id: Q8273 Difficulty: 3.00 Time to complete: 3 10CFR Category: 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

NONE Ability to determine and interpret the following as they apply to the Pressurizer Level Control Malfunctions: Charging subsystem flow indicator and controller.

A correct, Ref & Variable leg equalize, indicated level would increase causing an increase in letdown to maintain level.

B incorrect, actual press would decrease due to actual level decreasing.

C, D incorrect, indicated level increases not decreases.

OPTRNG_EXAM Page: 15 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 9 Appears on: SRO EXAM K/A # A11G2120 Importance 4.20 Rating:

Given the following plant conditions:

Unit 1 was operating at 50% power prior to a Reactor Trip.

SG 2 Level is 0% WR.

SG 2 Pressure is 350 psig and decreasing.

SG 1 Level is 40% WR and steady.

SG 1 Pressure is 1100 psig and steady.

RCS Loop 2 Tcold is at 500 °F and increasing.

RCS Loop 1 Tcold is at 550 °F and decreasing.

Pressurizer level is 9% and steady.

The CRS should direct the Secondary Operator at this time to...

A. stabilize RCS temperature by throttling HPSI flow.

B. equalize RCS temperature by lowering SG 2 Pressure.

C. reduce RCS loop 1 temperature by lowering SG 1 Pressure.

D. stabilize RCS temperature by controlling the non-affected SG Pressure.

Answer: D Learning Objective:

100866 Active Question Bank 2004 L11205 Given a set of plant parameters determine when and how RCS temperature is stabilized during an ESD ESEP026 Given SPTAs are being performed and containment pressure is 8.5 psig or more ensure CSAS initiation and flow, stop all RCPs, and isolate RCP bleedoff L61355 Determine when and how RCS temperature is stabilized during an ESD.

L61329 Given conditions of an ESD and appropriate reference material describe the mitigation strategy used during excessive steam demand accidents L89129 Given a set of plant parameters determine why, when and how RCS temperature is stabilized during an ESD Reference Id: Q6723 Difficulty: 2.00 Time to complete: 3 10CFR Category: 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40EP-9EO05, ESD RCS Overcooling: Ability to execute procedure steps.

A, B, C incorrect per ESD Emergency Operating Procedure and could possibly complicate the mitigating strategy.

OPTRNG_EXAM Page: 16 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions)

EXCESS STEAM DEMAND 40EP-9EO05 Page 13 of 47 INSTRUCTIONS

14. Stabilize RCS temperature using the lowest Tc by performing the following:

a. Maintain Tc within the P/T limits.

REFER TO Appendix 2, Figures.

b. Steam the least affected Steam Generator using ANY of the following:

SBCS

ADVs from the Control Room

Appendix 18, Local ADV Operation

c. Control feedwater to the least affected steam generator.

15. IF steaming to atmosphere, THEN inform Radiation Protection and the RMS Technician.

OPTRNG_EXAM Page: 17 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 10 Appears on: SRO EXAM K/A # 44A16AA22 Importance 3.70 Rating:

Given the following plant conditions:

Reactor Power is 98% JSCALOR

Three (3) charging pumps are operating.

Charging flow is 132 gpm.

Seal injection flow is 26.2 gpm.

Total seal bleedoff is 8.5 gpm.

Letdown flow is 72 gpm and lowering.

RCS temperature is stable.

PZR level is 41% and lowering.

No activity is indicated in the steam plant.

Based on these conditions, the operating crew is required to...

A. trip the reactor.

B. isolate letdown.

C. commence a rapid shutdown.

D. continue to monitor the leakrate while attempting to locate the leak.

Answer: B Learning Objective:

L10169 Given indications of RCS or a Steam Generator Tube Leak, describe the basic procedure methodology, including Reactor Trip is thresholds, Reference Id: Q8817 Difficulty: 4.00 Time to complete: 5 10CFR Category: 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ02, RCS Leakage Ability to determine and interpret the following as they apply to the (Excess RCS Leakage)

Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments The operator should analyze systems still operating and determine which action is still required to potentially isolate or slow the leak to maintain level. All makeup capability has been started; therefore the next step is to minimize losses by securing letdown, then trip the unit if still losing PZR level.

C is incorrect; a rapid shutdown would cause a PZR shrink and compound the situation.

D is incorrect, there is not enough volume left in the PZR to start a search for the leak prior to uncovering the heaters and losing PZR pressure control.

OPTRNG_EXAM Page: 18 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions)

EXCESSIVE RCS LEAKRATE 40AO-9ZZ02 Page 5 of 60 3.0 RCS LEAKAGE

____3. IF ALL of the following conditions exist:

All available Charging Pumps are operating,

Letdown is isolated,

Pressurizer level is lowering, THEN perform the following:

a. Ensure that the Reactor is tripped.

b. GO TO ONE of the following:

40EP-9EO01, Standard Post Trip Actions

40EP-9EO11, Lower Mode Functional Recovery OPTRNG_EXAM Page: 19 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 11 Appears on: SRO EXAM K/A # 2222 Importance 4.10 Rating:

Given the following plant conditions:

RCS fill and vent operations are in progress

The CRS desires to start a Reactor Coolant Pump.

RCS T-cold is 30°F lower than steam generator temperature.

An RCP start with a steam bubble in the Pressurizer is not allowed at this time because of which ONE of the following concerns?

A. Excessive core uplift.

B. Possible RCS pressure excursion causing LTOP lifting.

C. RCP motor starting and running current would be exceeded.

D. Possible cold water reactivity excursion reducing shutdown margin.

Answer: B Learning Objective:

L10199 Given that 40OP-9ZZ01 is in progress identify the consequences associated with starting RCPs when SG temperatures are greater than RCS cold leg temperature.

Reference Id: Q7895 Difficulty: 3.00 Time to complete: 2 10CFR Category: 55.43 (2) Facility operating limitations in the technical specifications and their bases.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40OP-9SI01, SDC Initiation; T.S. 3.4.7, NOTE 3 Knowledge of limiting conditions for operations and safety limits A, C, D incorrect, these are all correct fundamental relationships that would be impacted in the correct direction but are not the main concern.

OPTRNG_EXAM Page: 20 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Loops MODE 5, Loops Filled LCO 3.4.7 One Shutdown Cooling (SDC) train shall be OPERABLE and in operation, and either:

a. One additional SDC train shall be OPERABLE; or

b. The secondary side water level of each Steam Generator (SG) shall be = 25%.

NOTES---------------------------

1. The SDC pump of the train in operation may be de-energized for = 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a. No operations are permitted that would cause reduction of the RCS boron concentration; and

b. Core outlet temperature is maintained at least 10°F below saturation temperature.

2. One required SDC train may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided that the other SDC train is OPERABLE and in operation.

3. No Reactor Coolant Pump (RCP) shall be started with one or more of the RCS cold leg temperatures 214°F during cooldown, or 291°F during heatup unless the secondary side water temperature in each SG is < 100°F above each of the RCS cold leg temperatures.

OPTRNG_EXAM Page: 21 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 12 Appears on: SRO EXAM K/A # 34005A204 Importance 2.90 Rating:

Given the following plant conditions:

Unit 2 is in Mode 5.

LPSI 'B' is providing SDC flow.

LPSI 'B' Pump trips to a ground fault on the bus.

The 'A' LPSI Pump is started to recover SDC.

The ERFDAS Low SDC Flow alarm is received.

LPSI A Pump running amps is slightly above 0.

Which ONE of the following accurately describes the cause of the above condition and the actions that are required to protect the running LPSI pump?

A. The LPSI pump has exceeded its running voltage limit due to low motor amps and should be immediately secured.

B. A valve in the pump's discharge path is closed, the CRS has about an hour to correct the flowpath before overheating of the pump could occur.

C. The temperature limitations on the LPSI pump seal have been exceeded due to a lack of cooling flow and the pump should be immediately secured.

D. The LPSI pump is operating in the "rumble range" and should therefore be stopped within the next 5 minutes unless flow above the rumble range can be attained by then.

Answer: B Learning Objective:

L79916 Discuss the Shutdown Cooling Low Flow Alarms.

Reference Id: Q10246 Difficulty: 3.00 Time to complete: 4 10CFR Category: 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40OP-9SI01, SDC Initiation Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: RHR valve malfunction A incorrect, less power is required due to less discharge flow. Voltage and amps would both be lower.

B incorrect, cooling to the seals is not appreciably affected.

D incorrect, the rumble region is at a higher flow than indicated by amps.

C correct, per procedure with < min. flow, you have about an hour before the pump begins to overheat.

OPTRNG_EXAM Page: 22 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions)

Shutdown Cooling Initiation 40OP-9SI01 Page 10 of 180 3.3 Operating LPSI Pumps Motor starting limits. Frequent starting may result in serious damage to the motor on the LPSI pump. With the motor initially at ambient temperature (shutdown greater than one hour), do not attempt more than two consecutive starts. Allow the motor to coast to rest between starts. With the motor initially above ambient temperature, do not attempt more than one start. Anytime the motor windings are energized, this constitutes a start. If either of the above criteria have been met, an interval of 15 minutes with the motor running or 45 minutes with the motor shutdown must elapse prior to any additional starts.

Flow rate limits. Operating a LPSI pump without a flow path may cause pump damage due to overheating. The LPSI pump mini-flow recirculation provides 100 gpm flow and provides sufficient heat removal for only one hour of pump operation. Continuous operation of a LPSI pump requires a minimum of 2400 gpm flow. Exceeding a LPSI pump design flow rate of 5000 gpm may cause pump damage.

OPTRNG_EXAM Page: 23 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 13 Appears on: SRO EXAM K/A # 37012A201 Importance 3.60 Rating:

Given the following plant conditions:

Unit 3 is operating at 100% power.

Pressurizer Pressure NR RCA-PI-101A is reading offscale high.

Pressurizer Pressure WR RCA-PI-102A is reading 2250 psia.

Pressurizer Pressure NR RCB-PI-101B is reading 2240 psia.

Pressurizer Pressure WR RCB-PI-102B is reading 2250 psia.

Pressurizer Pressure NR RCD-PI-101D is reading 2240 psia.

Pressurizer Pressure WR RCD-PI-102D is reading 2240 psia.

Point ID SBTC06 Lo Pzr Press Ch C - Trip is in alarm.

Point ID SBTC05 Hi Pzr Press Ch C - Trip is in alarm.

Which ONE of the following would you expect to be a consequence of this and what action should be taken to mitigate the consequence?

A. The Reactor will trip, the CRS should enter the SPTAs.

B. No actuations should occur, the CRS should enter the appropriate alarm responses.

C. An 'A' SIAS and a CIAS should occur, the CRS should enter the AOP for "Inadvertent PPS-ESFAS".

D. The Reactor will trip with an 'A' SIAS and a CIAS only, the CRS should enter the SPTAs in conjunction with the AOP for "Inadvertent PPS-ESFAS".

Answer: A Learning Objective:

L11037 Determine whether or not the Inadvertent PPS-ESFAS Actuations AOP should be executed Reference Id: Q10247 Difficulty: 4.00 Time to complete: 5 10CFR Category: 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

Simplified Drawing Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Faulty bistable operation.

A correct, 2/4 channels reach trip condition.

B incorrect, a SIAS/CIAS would NOT occur, only 1 signal is present for the condition.

C incorrect, the CRS would not enter the AOP but would direct a Rx Trip.

D incorrect, SIAS/ CIAS not present.

OPTRNG_EXAM Page: 24 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 14 Appears on: SRO EXAM K/A # 34076A201 Importance 3.70 Rating:

Given the following plant conditions:

Unit 1 is 90% power.

'A' PCW (Plant Cooling Water) pump is out of service for maintenance.

The 'B' PCW pump is running but develops a rapid and continually degrading discharge flow.

Which ONE of the following action(s) should the CRS direct?

The CRS should direct...

A. the RO to minimize the heat loads on Turbine Cooling Water by performing the AOP for "Loss of Cooling Water".

B. a Reactor Trip, enter the SPTAs, and direct a RO to cross-tie EW to NC using Standard Appendix 63 to restore NC loads.

C. a Reactor Trip, enter the SPTAs, and direct a RO to perform "Loss of Cooling Water" AOP, to minimize cooling loads on Turbine Cooling Water.

D. the RO to minimize the heat loads on Essential Cooling Water by performing the AOP for "Loss of Cooling Water" and also enter the "Loss of Letdown" AOP.

Answer: C Learning Objective:

L10102 Given a sustained loss of the Plant or Turbine Cooling Water system(s) describe the required actions for a sustained loss of the Plant or Turbine Cooling Water System(s)

Reference Id: Q10248 Difficulty: 3.00 Time to complete: 4 10CFR Category: 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ03, Loss of Cooling Water Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SWS.

LO & EW temp will increase. Continued plant operations will be affected almost immediately therefore the procedure directs a Rx Trip for this condition if NOT restored.

The CRS is also expected to follow through in this condition with the AOP for loss of cooling on the secondary plant to protect equipment from overheating, crosstie EW to NC to restore NC loads and to enter the AOP for Loss of letdown.

B incorrect, the SPTAs will not correct or mitigate the loss of cooling.

A, D incorrect, Rx trip is required. Not enough time to prevent heat up to cause equipment overheating.

OPTRNG_EXAM Page: 25 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions)

LOSS OF COOLING WATER 40AO-9ZZ03 Page 6 of 36 3.0 PLANT COOLING WATER INSTRUCTIONS

___ 3. IF the PW system has been

restored, THEN GO TO the appropriate procedure for current plant conditions.

___ 4. IF the PW system is NOT

restored, AND the Reactor is at power, THEN perform the following:

a. Trip the Reactor.

b. PERFORM 40EP-9EO01, Standard Post Trip Actions.

OPTRNG_EXAM Page: 26 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 15 Appears on: SRO EXAM K/A # 35103A204 Importance 3.60 Rating:

Given the following plant conditions:

Unit 3 is in Mode 6.

Refueling operations are in progress.

RU-33, Refueling Machine Area, receives a HIGH alarm.

The LSRO reports a fuel bundle has dropped into the core and bubbles are coming from the area.

No BOP-ESFAS signals have actuated at this time.

RU-1, Containment Radiation monitor is slowly increasing.

Which ONE of the following actions should the control room take?

A. Manually actuate CPIAS and CREFAS and evacuate all unnecessary personnel from the containment.

B. Manually actuate a FBEVAS and CPIAS and evacuate all unnecessary personnel from the containment and Fuel Building.

C. Direct the RO to close essential dampers HFA-M01 through M06 and HFB-M01 through M06 and evacuate all personnel the containment.

D. Inform the LSRO to move the damaged fuel element to the intermediate storage rack and direct RP to evacuate all personnel from the containment.

Answer: A Learning Objective:

56433 Given the LMFR procedure is in progress and presented with specific plant parameters determine the need for containment evacuation Reference Id: Q10249 Difficulty: 3.00 Time to complete: 5 10CFR Category: 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ22, Fuel Damage Ability to (a) predict the impacts of the following malfunctions or operations on the containment system-and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations Containment evacuation (including recognition of the alarm).

A correct, procedure requires activation of both CPIAS and CREFAS to protect both the Control Room and Containment personnel.

B incorrect, while the fuel damage may eventually affect the Fuel Bldg also, based on the given information the procedure only directs actions for the Control Room and containment.

C incorrect, viable actions but not IAW procedure.

D incorrect, viable actions but not IAW procedure.

OPTRNG_EXAM Page: 27 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 3.0 IRRADIATED FUEL DAMAGE INSTRUCTIONS

___ 2. Announce the following using the unit page system:

Attention all personnel, Attention all personnel, All non-essential personnel evacuate the following area(s) immediately:

(announce as necessary)

Containment Building

Fuel Building

___ 3. IF the damaged fuel is located in the Containment Bldg, THEN perform the following:

a. Ensure BOTH of the following BOP-ESFAS actuations:

CPIAS

CREFAS

b. Record the time of the CREFAS Actuation.

c. Direct personnel to ensure BOTH of the following:

The personnel air lock doors are closed

The equipment hatch is closed OPTRNG_EXAM Page: 28 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 16 Appears on: SRO EXAM K/A # 38034K105 Importance 3.40 Rating:

Given the following plant conditions:

Unit 1 is in Mode 6 with core off-load in progress.

Point ID SENS5 Startup Channel 1 Boron Dilution is in alarm.

SU monitor SEN-JR-5 on B04 indicates upscale for Channel 1.

The Audio Channel Select toggle switch in the Channel 2 position.

The audible count rate is ~ 1 count every 2 to 3 seconds and has not changed.

SEN-JI-5, SU channel 2 meter is reading 1.

Which ONE of the following states ALL the actions that should be taken?

A. Suspend positive reactivity additions immediately.

B. Restore RCS boron concentration to within limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

C. Suspend Core alterations AND positive reactivity additions immediately.

D. Determine the RCS Boron concentration immediately and at the monitoring frequency specified in the COLR.

Answer: C Learning Objective:

L97323 Given count rate information State the required actions to take if count rate has increased.

Knowledge of the interrelations between the Fuel Handling Incidents and the following: Fuel handling equipment Reference Id: Q10250 Difficulty: 3.00 Time to complete: 4 10CFR Category: 55.43 (1) Conditions and limitations in the facility license.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

T.S. 3.9.2 Knowledge of the physical connections and/or cause-effect relationships between the Fuel Handling System and the following systems: Shutdown monitor.

A, B incorrect, incomplete or inaccurate TS action statements.

D incorrect, this would be correct for the alarm circuit being INOP.

OPTRNG_EXAM Page: 29 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 3.9 REFUELING OPERATIONS 3.9.2 Nuclear Instrumentation LCO 3.9.2 Two startup range monitors (SRMs) shall be OPERABLE.

APPLICABILITY: MODE 6.

ACTIONS

NOTE----------------------

Enter applicable Conditions and Required Actions of LCO 3.3.12, "Boron Dilution Alarm System (BDAS)" for BDAS made inoperable by SRMs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required SRM inoperable.

A.1 Suspend CORE Immediately ALTERATIONS.

AND A.2 Suspend positive Immediately reactivity additions.

B. Two required SRMs inoperable.

B.1 Initiate action to Immediately restore one SRM to OPERABLE status.

OPTRNG_EXAM Page: 30 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 17 Appears on: SRO EXAM K/A # 34056A205 Importance 2.50 Rating:

Given the following plant conditions:

Unit 1 is at 40% power One train of Circulating Water is in operation The Hotwell sodium (Na) concentration is 35 ppm Hotwell cation conductivity is pegged high (flashing 19.99 mmho/cm).

Hotwell level is 45 inches.

Based on these conditions the CRS should A. enter the "Alarm Response" ARP and swap demineralizer beds.

B. enter the "Condenser Tube Rupture" AOP and direct a reactor trip.

C. enter the "Power Operations" GOP and perform a rapid downpower.

D. enter the "Load Reject" AOP then direct a manual initiation of RPCB.

Answer: B Learning Objective:

L95424 As an operating crew mitigate a Condenser Tube Rupture by performing actions Reference Id: Q6637 Difficulty: 2.00 Time to complete: 4 10CFR Category: 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level: Memory Question Source: New Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ10, Condenser Tube Rupture, Appendix O Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Condenser tube leakage.

D, C incorrect, this would lower power rapidly but is not IAW procedure and could adversely affect the leak.

A incorrect, this would be beneficial but would not alleviate the condition fast enough.

B correct per the procedure. NOTE: The hotwell drawoff valves isolate on high cation conductivity.

OPTRNG_EXAM Page: 31 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions)

Appendix O, Condenser Tube Rupture Trip Criteria

NOTE -----------------------------------------------------------

Using normal Circ Water concentration values, a leak rate of ~14 GPM is estimated to result in the affected hotwell sodium reaching 35 ppm. A double ended condenser tube break can result in an ingress of Circ Water in excess of 200 gpm.

IF ANY of the following exist:

TRIP VALUES reached or exceeded

A trend indicates that a Steam Generator TRIP VALUES may be exceeded prior to completing a rapid downpower THEN perform the following:

a. Ensure reactor tripped.

b. PERFORM 40EP-9EO01, Standard Post Trip Actions.

c. PERFORM Appendix M, Condenser Tube Rupture Post Trip Actions PARAMETER TRIP VALUE Steam Generator (In-Line Monitor or Sample)

Sodium 1.0 ppm (1000 ppb) or more with a corresponding rise in Cation Conductivity.

Cation Conductivity 15 mho/cm or more with a corresponding rise in Sodium.

(Applies also to Sulfates and Chlorides, however these indications will lag sodium).

Sulfates 1.0 ppm (1000 ppb) or more with a corresponding rise in Cation Conductivity. (Lags sodium)

Chloride 1.0 ppm (1000 ppb) or more with a corresponding rise in Cation Conductivity. (Lags sodium)

Condenser (Local Indication)

Hotwell sodium 35 ppm (35,000 ppb) or more End of Appendix OPTRNG_EXAM Page: 32 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 18 Appears on: SRO EXAM K/A # 37072G2429 Importance 4.00 Rating:

Given the following plant conditions:

A radiography source in the Aux Bldg becomes accidentally EXPOSED.

RU-18 in the control room goes into alarm and is confirmed to be reading 20 mR/hr.

Which ONE of the following Emergency Actions Levels is appropriate for this condition?

A. NUE B. ALERT C. SAE D. GE Answer: B Learning Objective:

L58622 Given an Emergency Plan condition, use the EAL tables and basis document to determine the emergency plan classification Reference Id: Q10251 Difficulty: 3.00 Time to complete: 3 10CFR Category: 55.43 (4) Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: EAL Tables Technical

Reference:

EPIP-99, Appendix A Knowledge of emergency plan OPTRNG_EXAM Page: 33 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 19 Appears on: SRO EXAM K/A # 216 Importance 4.30 Rating:

Given the following plant conditions:

A severe transient is in progress.

The Shift Manager is unavailable.

The EOPs are NOT mitigating the event.

The CRS desires to take reasonable actions that are significantly outside of the procedural guidance found in the EOPs as well as the license conditions.

There are no actions within the scope of our license that will address the condition of the plant.

The CRS believes that failing to take these actions will lead to adverse consequences to the public health and safety.

Based on these conditions, the CRS must...

A. receive the Emergency Coordinators permission to deviate from the EOP.

B. must wait for guidance from the TSC when the EOP fails to mitigate the event.

C. invoke 10CFR50.54 (x) and wait for TSC approval for the planned action.

D. invoke 10CFR50.54 (x) and direct the actions that the CRS feels are reasonable.

Answer: D Learning Objective:

L103040 Describe 10CFR50.54(x) how it is implemented.

L12043 Describe 10CFR50.54(x) and 10CFR72.32(d) and how they are implemented.

Reference Id: Q9907 Difficulty: 3.00 Time to complete: 3 10CFR Category: 55.43 (1) Conditions and limitations in the facility license.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40DP-9OP02, Conduct of Shift Ops Ability to supervise and assume a management role during plant transients and upset conditions.

A incorrect, actions are outside TS guidance and require more than just another SROs input.

B, C incorrect, not enough time to wait for the TSC to be manned.

OPTRNG_EXAM Page: 34 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions)

Conduct of Shift Operations 40DP-9OP02 Page 41 of 52 11.0 EMERGENCY OPERATIONS Detailed procedures for emergency conditions are contained in the Emergency Operating Procedures and PVNGS Emergency Plan Implementing Procedures. Additional guidance for use of Emergency Operating Procedures are contained in 40DP-9AP16, Emergency Operating Procedures Users Guide.

11.1 Certain situations may require deviation from the EOPs or other procedures in accordance with 10CFR50.54 (x) or 10CFR72.32(d). All the following criteria shall be met:

Immediate action is required to avert adverse consequences to the public health and safety.

There is no apparent equivalent protective action that is consistent with the license.

Action to be taken is reasonable.

Action to be taken serves to protect public health and safety.

There is insufficient time available for NRC approval for an amendment to the Operating License.

Use of 10CFR50.54(x) requires a one hour notification to the NRC Operations Center. Use of 10CFR72.32(d) requires a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months notification to the NRC Operations Center.

Action taken shall be approved by a currently Licensed Senior Reactor Operator.

Operations Management and the NRC should be notified prior to implementation, if practical.

OPTRNG_EXAM Page: 35 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 20 Appears on: SRO EXAM K/A # 2111 Importance 3.80 Rating:

Given the following conditions:

The unit is at 100% power.

A Regulating Group CEA slips 10 inches into the core.

Based on these conditions, the applicable COLR graph requires that the crew BEGIN reducing power within ______ minutes of the event.

A. 2 B. 10 C. 30 D. 45 Answer: B Learning Objective:

L89762 Given a set of plant conditions apply the one hour or less actions statements of T.S. 3.1 L11400 Concerning Technical Specifications state the legal requirements of the Tech Specs (and their bases)

Reference Id: Q27574 Difficulty: 3.00 Time to complete: 3 10CFR Category: 55.43 (2) Facility operating limitations in the technical specifications and their bases.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

40AO-9ZZ11, CEA Malfunctions Knowledge of less than one hour technical specification action statements for systems OPTRNG_EXAM Page: 36 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions)

CEA MALFUNCTIONS 40AO-9ZZ11 Page 8 of 55 3.0 DROPPED OR SLIPPED CEA MODE 1 OR 2 INSTRUCTIONS

NOTE -----------------------------------------------

The effects of a boration to the RCS may take 4 to 6 minutes to be seen, therefore initiating a boration (step 12.) should done as soon as possible.

____8. Perform the following to start a power reduction within 10 minutes of the initial CEA deviation:

a. Log the start time for power reduction.

__________ (time)

b. Lower the turbine load to raise Tave 3°F greater than Tref.

OPTRNG_EXAM Page: 37 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 21 Appears on: SRO EXAM K/A # 2225 Importance 3.70 Rating:

What is the basis of the Technical Specification requirement to open the Reactor Trip Breakers in the event that two CEAs are misaligned by greater than 9.9 inches?

A. Prevents challenge to ASI trip B. Minimizes the potential for fuel damage C. Minimizes the effect of a possible ejected CEA D. Minimizes the possibility of operating without required SDM Answer: B Learning Objective:

L89761 Identify the basis of Technical Specification LCOs for section 3.1 Reference Id: Q9672 Difficulty: 2.00 Time to complete: 2 10CFR Category: 55.43 (2) Facility operating limitations in the technical specifications and their bases.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

T.S. 3.1.5.D.1 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits A, C, D incorrect, these are impacted but are not the main concern.

CEA Alignment B 3.1.5.D.1 Continued operation is not allowed in the case of more than one CEA misaligned from any other CEA in its group by

> 9.9 inches. For example, two CEAs in a group misaligned from any other CEA in that group by > 9.9. inches, or more than one CEA group that has a least one CEA misaligned from any other CEA in that group by > 9.9 inches. This is indicative of a loss of power distribution and a loss of safety function, respectively. Multiple CEA misalignments should result in automatic protective action. Therefore, with two or more CEAs misaligned more than 9.9 inches, this could result in a situation outside the design basis and immediate action would be required to prevent any potential fuel damage. Immediately opening the reactor trip breakers minimizes these effects.

OPTRNG_EXAM Page: 38 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 22 Appears on: SRO EXAM K/A # 2234 Importance 3.20 Rating:

Given the following plant conditions:

A plant trip from 100% power has occurred.

Critical rod position has been calculated for an end of core startup 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months after a trip from 100%

power equilibrium conditions.

The ECRP is Group 5 @ 30 inches.

Upon subsequent startup, the Reactor goes critical at Group 5 @ 45 inches.

Which ONE of the following conditions would cause this condition?

A. RCS pressure is increased 25 psig.

B. The startup is delayed approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

C. The boron concentration is decreased by 10 ppm.

D. The steam bypass pressure control setpoint is raised by 100 psig.

Answer: D Learning Objective:

L11005 Given that a Reactor startup is to be performed describe the method used in calculating an Estimated Critical Condition 100866 Active Question Bank 2004 Reference Id: Q16222 Difficulty: 3.00 Time to complete: 3 10CFR Category: 55.43 (6) Procedures and limitations involved in initial core loading, alterations in core configuration, control rod programming, and determination of various internal and external effects on core reactivity.

Cognitive Level: Comprehension / Anal Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

Core Data Book Knowledge of the process for determining the internal and external effects on core reactivity A incorrect, no appreciable pressure reactivity coefficient.

B incorrect, delay of 2 hrs means less Xe 135, + reactivity, lower critical condition C incorrect, lower boron, + reactivity addition, lower critical position.

D correct, raising SBCS setpoint, raises RCS temperature, - reactivity addition at EOC, higher CEA position to go critical.

OPTRNG_EXAM Page: 39 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 23 Appears on: SRO EXAM K/A # 236 Importance 3.10 Rating:

Given the following plant conditions:

A large break LOCA has occurred.

Due to emergency conditions a gaseous radioactive release from Containment must be performed to relieve pressure in the containment and bring the plant to a safer condition.

Who may authorize this release without a release permit?

A. Shift Manager.

B. RMS Technician.

C. RMS Supervisor.

D. Chemistry Supervisor.

Answer: A Learning Objective:

L57256 Given that abnormal conditions require exceeding ODCM requirements describe whose authority is needed to exceed requirements and what reporting is necessary 100866 Active Question Bank 2004 Reference Id: Q6695 Difficulty: 3.00 Time to complete: 4 10CFR Category: 55.43 (3) Facility licensee procedures required to obtain authority for design and operating changes in the facility.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

74RM-9EF20, GASEOUS RADIOACTIVE RELEASE PERMITS AND OFFSITE DOSE ASSESSMENT.

Knowledge of the requirements for reviewing and approving release permits.

SM/CRS must approve releases >ODCM.

GASEOUS RADIOACTIVE RELEASE PERMITS AND OFFSITE DOSE ASSESSMENT 74RM-9EF20 Page 74 of 81 Appendix J - Release Permit Review And Approval Matrix

d. Under abnormal (emergency) conditions verbal approval for exceeding ODCM Requirement limits may be given by the CRS/Shift Manager when performing the release if it will bring the plant in to a safer condition. A notification to the NRC within one hour in accordance with 10CFR50.72 will be required after approval. If ODCM Requirement limits for dose are exceeded (ODCM sections 4.4a, 4.4b, 4.1a, 4.1b, 4.2a or 4.2b) comply with ODCM Requirement 5.1.

OPTRNG_EXAM Page: 40 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 24 Appears on: SRO EXAM K/A # 2120 Importance 3.30 Rating:

Which ONE of the following is the FIRST action to be completed by the Control Room Staff when announcing a fire in the unit?

A. Sound the emergency fire alarm for 15 to 20 seconds.

B. Press down on the Emergency PA microphone transmit key and announce the location of the fire.

C. Press down on the Evacuation transmit button and then announce for personnel to leave and stay clear of the affected area.

D. Sound the Unit Evacuation System and announce the following: "Attention All Plant Personnel. Attention All Plant Personnel. There is a Fire Emergency in the Unit".

Answer: A Learning Objective:

L57493 Describe the responsibilities of the Fire Team Advisor in regards to Emergency Notification And Response.

Reference Id: Q10252 Difficulty: 2.00 Time to complete: 3 10CFR Category: 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level: Memory Question Source: INPO Bank Not modified Comment: Proposed Reference to be provided to applicant during examination: NONE Technical

Reference:

14DP-19FP32, Emergency Notification & Response, App C Ability to execute procedure steps EMERGENCY NOTIFICATION AND RESPONSE 14DP-0FP32 Page 23 of 41 Appendix C - Emergency Message Forms NOTE Unit 1 Control Room will make the announcements for emergencies and drills that occur in Unit 1 as well as WRF and all "COMMON AREAS" of the site. Use the following text verbatim providing proper information on the form as appropriate.

FIRE EMERGENCY SOUND THE EMERGENCY FIRE ALARM FOR 15 TO 20 SECONDS NOTE Press down on the Emergency PA microphone transmit key and wait at least 3 seconds for the system to power up, then transmit the following message over the unit evacuation system.

Transmit the following message over the Unit Evacuation System:

"Attention All Plant Personnel. Attention All Plant Personnel. There is a Fire Emergency in Unit [ 1, 2, 3 ] in the OPTRNG_EXAM Page: 41 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions) 25 Appears on: SRO EXAM K/A # 2430 Importance 3.60 Rating:

Given the following plant conditions:

Unit 1 was in Mode 3, cooling down for a refueling outage.

Engineering personnel, who were performing a routine boric acid walkdown, discover a small accumulation of boric acid residue on a reactor coolant system loop 2 hot leg instrument nozzle.

The nozzle was visually inspected during the last refueling outage and no leakage was identified at that time.

Which ONE of the following identifies when the NRC is required to be notified of this event?

Notify the NRC within...

A. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months D. 30 days Answer: B Learning Objective:

11190 Utilize the event reporting manual to determine event reportability.

Reference Id: Q10262 Difficulty: 3.00 Time to complete: 5 10CFR Category: 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

Cognitive Level: Comprehension / Anal Question Source: New Comment: Proposed Reference to be provided to applicant during examination: Event Reporting Manual Technical

Reference:

Event Reporting Manual Knowledge of which events related to system operations/status should be reported to outside agencies.

This event is a pressure boundary leakage. Therefore requires shutdown.

PALO VERDE NUCLEAR GENERATING STATION EVENT REPORTING MANUAL 301 of 451 ID 20 INITIATION of any nuclear plant shutdown required by TS 04 hr.

OPTRNG_EXAM Page: 42 of 43 06/15/05

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2005 LOIT Senior Reactor Operator NRC Exam (SRO Only Questions)

Cognitive Level Summary Number of questions linked: 25 Percentage Memory 5 20%

Comprehension / Analysis 20 80%

Question Source Summary Number of questions linked to source: 25 Percentage New New 13 52%

Modified INPO Bank Modified 0 Modified PV Bank 1 Total Modified 1 4%

Bank INPO Bank Not Modified 1 PV Bank Not Modified 10 Total BANK 11 44%

OPTRNG_EXAM Page: 43 of 43 06/15/05

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