Text

2008-11 - Draft - Written Examination (RO and SRO)
	ML083360252
Person / Time
Site:	Palo Verde
Issue date:	11/14/2008
From:	Mckernon T; NRC Region 4
To:	; Arizona Public Service Co
References
	50-528/08-301, 50-529/08-301, 50-530/08-301, ES-401, ES-401-5 50-528/08-301, 50-529/08-301, 50-530/08-301
	Download: ML083360252 (115)
	v • d • e

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 1

This Exam Level RO Apears on:

K/A # 42008AK2.03 Importance Rating:

Given the following conditions:

Unit 1 is at 100% power

Pzr level is 51.5 %

Pressurizer is in Boron Equalization

Pressurizer pressure is 2235 psia

PZR pressure controller, RCN-PIC-100, output is 40% and stable

PZR level controller, RCN-LIC-110, output is 40% and stable NOW

Letdown controller output 45% and INCREASING

Pressure controller output 25% and LOWERING Which one of the following events could cause the given CVCS controller responses?

A. Secondary steam leak B. Pressurizer steam space leak C. A full strength CEA has dropped D. A purification IX with new resin has been placed in service Answer: B Associated KA:

L10452 Given PZR Safety Valve tailpipe temperatures and the steam tables analyze the data to determine the status of the PZR safety valve Reference Id: Q10492 Difficulty: 4.00 Time to complete: 3 Cognitive Category: Not LINKED to a Cognitive Question Category Question Source: Not LINKED to a SOURCE Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

GFES, PPCS lesson plan K&A: Knowledge of the interrelations between the Pressurizer Vapor Space Accident and the following: Controllers and Positioners Justification:

A is Wrong - steam leak equals cooldown level output would lower pressure output would lower OPTRNG_EXAM Page: 1 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam B is Correct - vapor space leak causes Pzr level increase which causes letdown controller output to increase. Pzr pressure will drop causing pressure controller output to lower to prop heaters full on at 0 output C is Wrong - dropped CEA means colder water = level drop= letdown controller lowering and pressure controller lowering D is Wrong - this is a dilution causing an RCS heatup so letdown controller will increase and if anything a pressure increase which would cause controller output to increase OPTRNG_EXAM Page: 2 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 2

This Exam Level RO Apears on:

K/A # 41011EK1.01 Importance Rating:

Given the following conditions:

Unit 1 tripped from 100% power 30 minutes ago

RCPs were manually tripped 25 minutes ago due to CSAS actuation

RCS T-cold is 325 ºF and lowering

RCS T-hot is 450 ºF and lowering

Highest CET temperature is 490 ºF

RCS pressure is 565 psia Natural Circulation flow ...

A. is established ensure SG levels are 40 - 65% NR B. is established place the RCS on Shutdown Cooling C. is not established ensure SG levels are 40 - 65% NR D. is not established place the RCS on Shutdown Cooling Answer: C Associated KA:

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

Reference Id: Q10493 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: Steam Tables Technical

Reference:

40EP-9EO03, LOCA / 40DP-9AP08, LOCA Tech Guideline K&A: Knowledge of the operational implications of the following concepts as they apply to the Large Break LOCA: Natural circulation and cooling, including reflux boiling.

Justification:

A & B are Wrong - Natl Circ can not be verified delta T is to great, Delta between Thot and CET is to great and subcooling is not met for Thot but not the required CET temperatures C is correct Natl circ can not be verified and ensuring SG levels 45 - 60% NR is directed by LOCA D is Wrong - SDC is not permitted with inadequate subcooling OPTRNG_EXAM Page: 3 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 3

This Exam Level RO Apears on:

K/A # 42025AK3.03 Importance Rating:

The plant is currently exhibiting the following conditions during plant heatup in Mode 5 following refueling.

RCS - 205°F and 310 psia.

RCPs 1A and 1B are running.

Both S/G's at 30% WR Level.

LPSI 'A' had been running on Shutdown Cooling, but has recently tripped on overcurrent.

Which of the following actions should the Operator perform to restore RCS Heat Removal.

A. Start LPSI Pump 'B' on Shutdown Cooling.

B. Trip the 2 operating Reactor Coolant Pumps.

C. Start CS Pump 'A' on Shutdown Cooling.

D. Shift heat removal to the secondary using SBCS.

Answer: A Associated KA:

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) 100866 Active Question Bank 2004 Reference Id: Q5414 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-9EO11, LMFRP K&A: Knowledge of the reasons for the following responses as they apply to the Loss of Residual Heat Removal System: Immediate actions contained in EOP for Loss of RHRS Justification:

A is Correct - LPSI B is available and meets criteria B is Correct - CS RCS pressure is to high C is Wrong - this would slow the heat-up but is not procedurelly directed D is Wrong - SBCS requires a mode change OPTRNG_EXAM Page: 4 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam OPTRNG_EXAM Page: 5 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 4

This Exam Level RO Apears on:

K/A # 42027AA2.12 Importance Rating:

Given the following conditions:

Pressurizer pressure is 2250 psia

Pressurizer level is 52%

Pressurizer low level heater cutout switch (RCN-HS-100-3) is selected to Channel X

Pressurizer level control channel selector (RCN-HS-110) is selected to Channel X Which one of the following conditions is true regarding the Pressurizer Pressure Control System?

A. Backup heaters will energize if RCS pressure drops to 2225 psia B. All heaters will energize if PZR level transmitter RCN-LT-110X fails high C. All heaters will de-energize if PZR level transmitter RCN-LT-110Y fails low D. Proportional heaters will trip and must be reset if pressurizer pressure reaches 2275 psia Answer: B Associated KA:

L75234 Describe the function of Pressurizer Level Instruments (RCN-LT-110X and RCN-LT-110Y) inputs to the Pressurizer Pressure Control System.

Reference Id: Q10494 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: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

PPCS Lesson Plan K&A: Ability to determine and interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: PZR level Justification:

A is Wrong - backup heaters energize 2200 de-energize at 2225 psia B is Correct - all heaters energize on a +3% level deviation C is Wrong - channel Y has no effect if not in Y or both D is Wrong - Prop heaters have 0 output but do not trip or require reset at 2275 psia OPTRNG_EXAM Page: 6 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 5

This Exam Level RO Apears on:

K/A # 2.2.3 Importance Rating:

The minimum allowed switchyard voltage for Unit 1 is _______ than Unit 2 in addition Unit 1 will trip open the Water Reclamation Facility supply breakers on a simultaneous low switchyard voltage and _______

signal.

A. lower, LOP B. lower, SIAS C. higher, LOP D. higher, SIAS Answer: D Associated KA:

30264 Unit differences Reference Id: Q10495 Difficulty: 2.00 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: Memory Question Source: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

41AL-1RK1B, window 6B K&A: Equipment Control (multi-unit) Knowledge of the design, procedural, and operational differences between units.

Justification:

A & B are Wrong - Unit 1 has a higher minimum voltage requirement but examinee may think that U1 requirement is lower because it will shed loads on a SIAS C is Wrong - SIAS and voltage permissive is required D is Correct - see above OPTRNG_EXAM Page: 7 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 6

This Exam Level RO Apears on:

K/A # 41038EK3.08 Importance Rating:

Given the following conditions:

Unit 1 was manually tripped due to a SG tube rupture

RCS pressure 1100 psia

RCS Tcold is 531 ºF

RCS Thot is 536 ºF Which one of the following actions/conditions is correct?

A. Trip 2 RCPs, cooldown rate is limited to 30 ºF/hr B. Trip 2 RCPs, cooldown rate is limited to 100 ºF/hr C. Trip all 4 RCPs, cooldown rate is limited to 30 ºF/hr D. Trip all 4 RCPs, cooldown rate is limited to 100 ºF/hr Answer: C Associated KA:

L11239 Given the SGTR EOP is being performed and a cooldown to less than 550°F is required describe how and at what rate the cooldown will be performed Reference Id: Q10496 Difficulty: 4.00 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: Steam Tables Technical

Reference:

40EP-9EO04, LOCA K&A: Knowledge of the reasons for the following responses as the apply to the SGTR:

Criteria for securing RCP Justification:

A & B are wrong - Thot is less than 24 degrees subcooled all 4 RCPs must be tripped C is Wrong - with a loss of forced circulation the cooldown is limited to 30 degrees/hr D is Wrong - 100 is the TS limit and the limit with RCPs OPTRNG_EXAM Page: 8 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 7

This Exam Level RO Apears on:

K/A # 42040AK2.02 Importance Rating:

Given the following plant conditions:

The reactor has tripped.

PZR level is 25% and lowering.

RCS pressure is 1700 psia and dropping.

Containment pressure and temperature is rising.

RCS subcooling is 75°F and increasing.

SG 1 level is 45% WR and lowering

Loop 1 Tcold is 520°F and lowering

SG 2 level is 65% WR and lowering

Loop 2 Tcold is 555°F and lowering Which one of the following is the most likely response of the SG 1 steam flow transmitters?

A. SGN-FT-1011 flow > SGN-FT-1012 flow. SGN-FT-1011 and SGN-FT-1012 each indicate 0 (zero) flow when MSIS actuates.

B. SGN-FT-1011 flow equals SGN-FT-1012 flow. Both steam flow detectors approach no flow as dryout conditions are reached.

C. SGN-FT-1011 flow equals SGN-FT-1012 flow. Both steam flow detectors decrease to 0 (zero) flow when MSIS actuates.

D. SGN-FT-1011 flow > SGN-FT-1012 flow. SGN-FT-1011 flow approaches no flow as dryout conditions are reached. SGN-FT-1012 indicates 0 (zero) flow when MSIS actuates.

Answer: D Associated KA:

L11203 Given plant conditions analyze SG parameters to determine the presence and relative severity of an ESD Reference Id: Q10497 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: Comprehension / Anal Question Source: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

mechanical prints, 01-SGP-0002 OPTRNG_EXAM Page: 9 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam K&A: Knowledge of the interrelations between the Steam Line Rupture and the following:

Sensors and detectors Justification:

A is Wrong - 1 > 2 is correct but since the leak is in containment flow will degrade not go to 0 on MSIS B is Wrong - 1 = 2 is wrong but examinee may assume redundant indications as they are used in COLSS. Flow will trend to 0 as dryout conditions are reached C is Wrong - 1 = 2 is wrong and MSIS will not cause flow to go to zero D is Correct - 1 . 2 is correct and 1011 will go to 0 as dryout approaches and 1012 goes to 0 on MSIS. Flow detectors are on SG nozzle outlets OPTRNG_EXAM Page: 10 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 8

This Exam Level RO Apears on:

K/A # 41055EA1.01 Importance 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.

What is the condition of RCS and core heat removal?

A. Two phase natural circulation is maintaining heat removal.

B. Single phase natural circulation is maintaining heat removal.

C. All natural circulation has been lost, core uncovery has occurred.

D. All natural circulation has been lost, but the core still remains covered.

Answer: A Associated KA:

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.

100866 Active Question Bank 2004 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:

40EP-9EO08, BLACKOUT / 40DP-9AP13. BO Tech Guideline K&A: Ability to operate and monitor the following as they apply to a Station Blackout: In-core thermocouple temperatures Justification:

A is Correct - single phase nal circ has been lost. Provided that REP CET is maintained less than 50 degrees superheated than the core is covered and 2 phase natl circ flow is effective OPTRNG_EXAM Page: 11 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam OPTRNG_EXAM Page: 12 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 9

This Exam Level RO Apears on:

K/A # 42056AK1.04 Importance Rating:

Given the following conditions:

Main Spray valves 100E & 100F failed open

SIAS/CIAS/MSIS automatically initiated

Offsite power was lost when the reactor tripped

Offsite power has been restored

PZR level is 7% and slowly increasing

RCS Tcold temperature is 510ºF

RCS Thot temperature is 520ºF

REP CET temerature is 550ºF

RCS pressure is 1044 psia The RCS is currently ....

A. 24ºF subcooled. RCP restart is permitted at the current RCS conditions.

B. 24ºF subcooled. HPSI flow may be throttled at the current RCS conditions.

C. at saturation conditions. RCP restart is permitted if RCS pressure is raised to 1300 psia.

D. at saturation conditions. HPSI flow may be throttled if RCS pressure is raised to 1300 psia.

Answer: C Associated KA:

30267 RCP restart Reference Id: Q10498 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: Steam Tables /

Standard App. 2 (RCP curves)

Technical

Reference:

Standard appendixes 1 & 2, 40ep-9EO07, LOOP K&A: Knowledge of the operational implications of the following concepts as they apply to Loss of Offsite Power: Definition of saturation conditions, implication for the systems Justification:

A & B are Wrong - RCS is 24 degrees subcooled by Thot but must use CET temp when in Natl Circ OPTRNG_EXAM Page: 13 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam C is Correct - RCS is at saturation and minimum RCS pressure for 550 degrees is 1300 psia D is Wrong - RCS is at saturation but HPSI can not be throttled with < 10% PZR level OPTRNG_EXAM Page: 14 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 10 This Exam Level RO Apears on:

K/A # 42062AK3.03 Importance Rating:

Given the following conditions:

Unit 1 has tripped from rated power due to a Loss of Offsite Power event.

All systems have responded as designed

The crew has cross connected Essential Cooling Water (EW) system "A" to Nuclear Cooling Water per Standard Appendix 63.

The procedure now directs that EWA-HCV-53, SDCHX A Outlet Isolation, be throttled closed to an EW system flow of 8500 gpm to ...

A. maintain Operability of the EW "A" system.

B. provide the NCW priority loads with adequate flow.

C. prevent EW pump damage due to operating in a runout condition.

D. ensure adequate flow to the Fuel Pool Heat Exchangers if aligned.

Answer: B Associated KA:

30268 X-tie EW to NC Reference Id: Q10499 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: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

SA-63 and Tech Guide/ 40DP-9AP12, LOOP Tech Guide /

K&A: Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: Guidance actions contained in EOP for Loss of nuclear service water Justification:

A is Wrong - EW is INOP when cross tied B is Correct - this is to ensure adequate flow to NCW priority loads C is Wrong - not for runout but examinee could believe this to be true when taking systems out of normal alignment D is Wrong - One train of EW not sized to provide both NCW and Fuel Pool cooling, this would require aligning the other train OPTRNG_EXAM Page: 15 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam OPTRNG_EXAM Page: 16 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 11 This Exam Level RO Apears on:

K/A # 42077AA1.03 Importance Rating:

Given the following conditions:

Unit 1 is operating at rated electrical power

A grid disturbance occurs

The Operator notes that LED 15 (V/HZ) is flashing This indicates that the Generrex has .....

A. overridden the AC regulator to maintain excitation at an acceptable level. AC regulator control can be restored by decreasing the AC regulator setpoint.

B. limited Main Generator output voltage. AC regulator control can be restored by decreasing the AC regulator setpoint.

C. overridden the AC regulator to increase excitation to an acceptable level. AC regulator control can be restored by increasing the AC regulator setpoint.

D. raised Main Generator output voltage. AC regulator control can be restored by increasing the AC regulator setpoint.

Answer: B Associated KA:

L75018 Explain the operation of the Volts/Hertz Regulator and Trip circuits under normal operating conditions.

Reference Id: Q10500 Difficulty: 4.00 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: Modified PV Bank Comment:

modified from Q21330 Proposed reference to be provided to applicant during examination: None Technical

Reference:

40OP-9MB01, Main Generation and Excitation / 40AL-9RK6B (6B08D), ARP / LOIT lesson plan K&A: Ability to operate and/or monitor the following as they apply to Generator Voltage and Electric Grid Disturbances: Voltage Regulator Controls Justification:

A is Correct - V/HZ is designed to limit generator voltage prior to a V/HZ trip and AC regulation is restored by lowering the AC reg setpoint B is Wrong - increase and raise are wrong OPTRNG_EXAM Page: 17 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam C & D are describing the URAL circuit which works to maintain excitation raising the AC regulator is how URAL is restored.

OPTRNG_EXAM Page: 18 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 12 This Exam Level RO Apears on:

K/A # 44E02EA2.2 Importance Rating:

Given the following plant conditions:

Unit 1 has manually tripped from 90% power for a scheduled refueling outage

SPTAs were entered at 0000

Reactor Trip ORP entered at 0015 The Boron Dilution Alarm System (BDAS) must be placed in service and channel check completed when Rx power is less than .....

A. 2x10-4% power but no later than 0100 B. 2x10-4% power but no later than 0115 C. 2x10-6% power but no later than 0100 D. 2x10-6% power but no later than 0115 Answer: C Associated KA:

L10354 Given conditions of a reactor trip describe the time limitation (including its bases) placed on aligning the BDAS L74318 Given the plant has been placed in Mode 3 apply the requirements for Boron Dilution Alarm System (BDAS) 100866 Active Question Bank 2004 Reference Id: Q9699 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: Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Rx trip, 40EP-9EO02 / Rx Trip tech guide 40DP-9AP07 / LCO 3.3.12 K&A: Ability to determine and interpret the following as they apply to the (Reactor Trip Recovery) Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

Justification:

A and B are wrong BDAS is not placed in service until 10 -6%, 10 -4 is verification of subcritical conditions following a rx trip and is used in CPCs log 1 & 2 bistables OPTRNG_EXAM Page: 19 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam C is Correct 6 and one hour from Rx trip (SPTAs) is the standard D is Wrong - waiting 15 minutes for start of EOP is not conservative OPTRNG_EXAM Page: 20 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 13 This Exam Level RO Apears on:

K/A # 44E06EK22 Importance Rating:

Given the following conditions:

Unit 1 tripped from rated power

Auxiliary Feedpump "B" is OOS

Auxiliary Feedpump "A" oversped tripped and won't reset

Main Feed Pump "A" tripped due to a control oil failure

SBCS valve 1004 sticks open and will not close

MSIS initiated on low SG pressure

SIAS initiated on low PZR pressure

PBA-S03 tripped on an 86 Lockout

NNN-D16 tripped

Both SGs are DRY The CRS should implement the (1) procedure and restore a maximum feedwater flow (2) .

A. (1) Functional Recovery (2) of 500 gpm to each SG B. (1) Loss of all Feedwater (2) of 500 gpm to each SG C. (1) Functional Recovery (2) of 1000 gpm to only one SG D. (1) Loss of all Feedwater (2) of 1000 gpm to only one SG Answer: C Associated KA:

L10502 Given conditions of a LOAF and the status of plant equipment determine from where feed can be established Reference Id: Q10307 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:

FRP, 40EP-9EO09 and SA 44 K&A: 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.

Justification:

A is Correct -

B is Correct -

OPTRNG_EXAM Page: 21 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam C is Wrong -

D is Wrong -

14 This Exam Level RO Apears on:

K/A # 34003KK5.02 Importance Rating:

Each RCP motor has a fly wheel which:

A. Reduces RCP coastdown time to prevent free-wheeling.

B. Increases RCP coastdown time to maximize decay heat removal.

C. Prevents an idle pump from turning due to flow from other running RCP's.

D. Provides shaft balancing to prevent excessive vibration on pump start and stops.

Answer: B Associated KA:

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

100866 Active Question Bank 2004 Reference Id: Q3571 Difficulty: 2.00 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: Memory Question Source: Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

LCO 3.9.3 K&A:

Justification:

A is Correct -

B is Correct -

C is Wrong -

D is Wrong -

OPTRNG_EXAM Page: 22 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 15 This Exam Level RO Apears on:

K/A # 3.4005K2.03 Importance Rating:

What are the power supplies to the Shutdown Cooling Isolation valves, SIA-HV-651 (A) and SIC-HV653 (B)?

A. (A) 480 VAC Class LC, PG (B) 480 VAC Class LC, PG B. (A) 480 VAC Class LC, PG (B) 125 VDC Class MCC, PK C. (A) 480 VAC Class MCC, PH (B) 480 VAC Class MCC, PH D. (A) 480 VAC Class MCC, PH (B) 125 VDC Class MCC, PK Answer: D Associated KA:

65136 Identify the power supplies to SI related equipment.

Reference Id: Q10504 Difficulty: 2.00 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: Memory Question Source: New Comment:

Proposed reference to be provided to applicant during examination:

Technical

Reference:

Electrical prints, 01-E-SIB-013 & 014 K&A: Knowledge of bus power supplies to the following: RCS pressure boundary motor-operated valves Justification:

A is wrong -

B is wrong -

C is wrong -

D is CORRECT - SI-651 is supplied be a class MCC (PH) and SI-653 is supplied by class DC (PK) thru an inverter N43 OPTRNG_EXAM Page: 23 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 16 This Exam Level RO Apears on:

K/A # 34005A4.03 Importance Rating:

Given the following conditions:

Unit 1 is in Mode 5

No RCPs are in operation

Shutdown Cooling train A is in service, flow is being provided by LPSI pump A

A plant heatup to Mode 4 is scheduled to begin later this shift

You have been directed to initiate performance of 40ST-9RC01 (RCS and Pressurizer Heatup and Cooldown Rates)

Which temperature instrument is required to be used to track the RCS heatup rate?

A. Loop 1 Thot B. Loop 1 Tcold C. SDC Heat Exchanger A inlet D. SDC Heat Exchanger A outlet Answer: D Associated KA:

65120 Describe the Control Room indications associated with the SDC system.

Reference Id: Q10505 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: Memory Question Source: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40ST-9RC01, RCS and Pressurizer heatup and cooldown rates K&A: Ability to manually operate and/or monitor in the control room: RHR temperature, PZR heaters and flow, and nitrogen Justification:

A is Wrong - this temp is used for isolating SG during SGTR and during verification of Natl Circ conditions B is Wrong - used if RCPs are running C is Wrong - examinee may have a misconception on which temperature is considered bulk RCS temp D is Correct - correct per ST OPTRNG_EXAM Page: 24 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam OPTRNG_EXAM Page: 25 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 17 This Exam Level RO Apears on:

K/A # 32006K6.13 Importance Rating:

Given the following plant conditions:

A LOCA has occurred on Unit 1.

RCS pressure is 750 psia and lowering.

One minute after the Train B Essential Chiller started, a fault locks out PBB-S04.

The expected Emergency Core Cooling System injection flow would be:

A. increasing HPSI flow into all reactor coolant loops.

B. increasing LPSI and HPSI flow into all reactor coolant loops.

C. increasing HPSI flow into reactor coolant loops 1A and 1B only.

D. increasing LPSI and HPSI flow into reactor coolant loops 1A and 1B only.

Answer: A Associated KA:

100866 Active Question Bank 2004 65106 Describe the design characteristics of the HPSI pumps.

Reference Id: Q8305 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:

Standard Appendix 2 K&A: Knowledge of the effect of a loss or malfunction on the following will have on the ECCS: Pumps Justification:

A is Correct - pressure is to high for LPSI pumps to inject and HPSI will inject into all 4 cold legs and increase flow rate as pressure continues to drop B is Wrong - examinee may not know LPSI shutoff head C is Wrong - examinee may not realize that HPSI inject to all cold legs D is Wrong - LPSI flow is loop specific and pressure is above shutoff head. HPSI flows to all cold legs OPTRNG_EXAM Page: 26 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam OPTRNG_EXAM Page: 27 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 18 This Exam Level RO Apears on:

K/A # 38008A2.04 Importance Rating:

Given the following conditions:

A failure of both Nuclear Cooling Water pumps has occurred.

The Operating Crew has cross connected "A" EW to NC from the control room.

A small leak into one of the High Pressure Seal Coolers occurs after the systems are crossconnected.

Based on these conditions, how will RMS respond?

A. RU-155D (Letdown) alarm ONLY. Take actions per 40AO-9ZZ05, Loss of Letdown AOP.

B. RU-2 (ECW "A") AND RU-6 (NCW) alarm. Take actions per 40AO-9ZZ03, Loss of Cooling Water AOP.

C. RU-6 (NCW) AND RU-155D (Letdown) alarm. Take actions per 40AO-9ZZ02, Excessive RCS Leakrate AOP.

D. RU-2 (ECW "A") alarm ONLY. Take actions per 74RM-9EF41, Radiation Monitoring System Alarm Response.

Answer: D Associated KA:

100866 Active Question Bank 2004 65002 Explain the operation of the NC Radiation Monitoring under normal operating conditions.

Reference Id: Q27523 Difficulty: 2.00 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: Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

74RM-9EF41, Radiation Monitoring System Alarm Response / 01-M-NCP-0001, mech print K&A: Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: PRMS alarm Justification:

OPTRNG_EXAM Page: 28 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam A is Wrong - When NC and EW are X-connected only RU-2 is in the system Letdown is isolated when NCV-99 is closed B is Wrong - RU-6 is a non vital load and is isolated when NCV-99 is closed C is Wrong - see above D is Correct - RU-2 still monitors EW and is in service during the cross connect OPTRNG_EXAM Page: 29 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 19 This Exam Level RO Apears on:

K/A # 33010K6.03 Importance Rating:

Given the following plant conditions:

Unit 1 is at 98% power.

Pressurizer Pressure Control System (PPCS) is in "Automatic" with a setpoint of 2252 psia

RCS pressure is 2252 psia and stable NOW

Main spray valve RC-100E red and green position indicator lights are lit.

Main spray valve RC-100F only the green position indicator light is lit.

Spray Valve Selection handswitch RCN-HS-100-10 is selected to BOTH

RCS pressure is 2220 psia and lowering Pressurizer Pressure Master controller output is currently in the percent range and the pressurizer backup heaters are .

A. 0 - 32, energized B. 33 - 50, energized C. 0 - 32, de-energized D. 33 - 50, de-energized Answer: C Associated KA:

100866 Active Question Bank 2004 L75344 Describe the response of the Pressurizer Pressure Control System to a failure of an input transmitter.

L88170 Describe the Control Room controls associated with the Pressurizer Pressure Master Controller including it's indications.

L75245 Describe the Control Room controls associated with the Pressurizer Spray Valve Controller including it's indications.

Reference Id: Q62087 Difficulty: 3.00 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: Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: None OPTRNG_EXAM Page: 30 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam Technical

Reference:

LOIT lesson plan K&A: Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: PZR sprays and heaters Justification:

A is Wrong - BU heaters do not energize till 2200 psia decreasing and turn off at 2225 increasing B is Wrong - BU heaters do not energize till 2200 psia decreasing and turn off at 2225 increasing C is Correct - Spray valves operate in the 33 - 55% master controller range, prop heaters 0

- 33%. These indications are for a failed open spray valve in both they are either both open or closed and the low pressure confirms a malfunction. the Controller would be calling for increasing output of the prop heaters therefore the range would be 0 - 33% output D is Wrong 55% is the full range of spray valve 2250 - 2275 psia OPTRNG_EXAM Page: 31 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 20 This Exam Level RO Apears on:

K/A # 37012K1.06 Importance Rating:

Unit 1 is operating at 100% power when the following events occur:

RCP 1A trips

All 4 RPS channels of CPCs DNBR & LPD pre-trips and trips have initiated

All 4 RPS channels SG-1 Lo Flow trips have initiated

DNBR LO is in fast flash on the Reactor Trip 1st Out Annunciator board

The Reactor has not tripped, phase current lights are still illuminated

An AO has been sent to open the Reactor Trip Switchgear breakers locally Under these conditions the Main Turbine ...

A. tripped when the Reactor trip signal was generated.

B. will trip when the Reactor trip undervoltage relays are actuated.

C. will trip following the Reactor trip when the Overspeed signal is generated.

D. will trip following the Reactor trip when the Reverse Power signal is generated.

Answer: B Reference Id: Q10506 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: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

01-E-MAB-0008 K&A: Knowledge of the physical connections and/or cause effect relationships between the RPS and the following systems: T/G Justification:

A is Wrong - Turbine trip is generated by the UVRX relays B is Correct - Turbine trip is generated by the UVRX relays which come from the RTSG breakers C is Wrong -

D is Wrong - This would be on a Sequential trip OPTRNG_EXAM Page: 32 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 21 This Exam Level RO Apears on:

K/A # 2.4.9 Importance Rating:

Unit 1 had been stable in Mode 4 but now the following conditions are observed:

RCS is at 284ºF and stable.

Pressurizer pressure is 250 psia and lowering.

Pressurizer level is 50% and lowering.

Containment sump levels are increasing.

Containment humidity is increasing.

SG 1 pressure is 55 psia and stable

RU-1, Containment Atmosphere is reading

RU-4, SG 1 Blowdown is reading

1A and 1B RCPs are running.

Shutdown cooling is not in service at this time.

SIA-UV-651, SIC-UV-653, SIB-UV-652 and SID-UV-654 are open.

A event is in progress and the CRS is required to enter ....

A. LOCA, -- 40EP-9EO03 (Loss of Coolant Accident).

B. Dual, -- 40EP-9EO09 (Functional Recovery Procedure).

C. SGTR, -- 40EP-9EO04 (Steam Generator Tube Rupture).

D. LOCA, -- 40EP-9EO11 (Lower Mode Functional Recovery).

Answer: D Associated KA:

L56421 Given plant conditions determine whether or not entry into or exit from the LMFRP is appropriate Reference Id: Q10508 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: Steam Tables Technical

Reference:

40EP-9EO11, LMFRP K&A: Emergency Procedures / Plan Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

Justification:

A is Wrong - indications of a LOCA event are correct but with LTOPs is service LMFRP is the correct procedure OPTRNG_EXAM Page: 33 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam B is Wrong - SG pressure is consistent with RCS temperature, RU-4 readings are normal =

NO dual event C is Wrong - SG pressure is consistent with RCS temperature, RU-4 readings are normal =

NO SGTR D is Correct - indications of a LOCA and LMFRP is required to be entered OPTRNG_EXAM Page: 34 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 22 This Exam Level RO Apears on:

K/A # 32013K4.06 Importance Rating:

Given the following conditions:

Inadvertant "A" train Recirculation Actuation Signal (RAS) has initiated

The initiating signal has been cleared In order to reset the RAS in the AUX relay cabinets the Operator, at a minimum, must press ....

A. either reset button.

B. both reset buttons, one at a time.

C. both reset buttons simultaneously.

D. and hold one reset button, for a minimum of 5 seconds.

Answer: A Associated KA:

L77239 Describe how an ESFAS subsystem can be manually actuated and manually reset from the Aux Relay Cabinets.

100866 Active Question Bank 2004 Reference Id: Q8248 Difficulty: 2.00 Time to complete: 1 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:

LOIT lesson plans K&A: Knowledge of ESFAS design feature(s) and/or interlocks(s) which provide for the following Recirculation actuation system reset Justification:

A is Correct - de-pressing either button will immediately power up the actuation relays energizing the lockout relay and repositions contact to rest the signal B, C & D will reset the RAS actuation but are not the minimum required actions OPTRNG_EXAM Page: 35 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 23 This Exam Level RO Apears on:

K/A # 35022k1.04 Importance Rating:

The Containment Normal ACUs are cooled by (1) and will isolate on a (2) .

A. (1) Normal Chilled Water (2) CSAS B. (1) Nuclear Cooling Water (2) CIAS C. (1) Normal Chilled Water (2) CIAS D. (1) Nuclear Cooling Water (2) CSAS Answer: C Associated KA:

74427 Describe how the Containment Building HVAC System is supported by the following systems:

Nuclear Cooling Water (NC)

Normal Chilled Water (WC)

Engineered Safety Features Actuation System (ESFAS)

Balance of Plant-Engineered Safety Features Actuation System (BOP-ESFAS)

Reference Id: Q10509 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:

LOIT lesson plan, 40OP-9HC01 (contmt HVAC), 01-M-WCP-0001 K&A: Knowledge of the physical connections and/or cause-effect relationships between the CCS and the following systems: Chilled water Justification:

A is Correct - WC supplies Cntmt normal HVAC and isolates on a CIAS B is Wrong - right supply but Nuclear Cooling water isolates on a CSAS C is Wrong - wrong supply but correct isolation signal / NCW supplies the CEDM coolers D is Wrong - wrong supply wrong signal OPTRNG_EXAM Page: 36 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 24 This Exam Level RO Apears on:

K/A # 34039a4.07 Importance Rating:

Proper operation of an ADV from the control room requires that the operator initially check the thumbwheel set at zero for the controller, and enable (a) then (b) .

A. (a) both of the permissives (b) set the controller for the desired demand, the valve should open immediately.

B. (a) either of the permissives (b) set the controller for the desired demand, the valve should open within 1 minute.

C. (a) either of the permissives (b) set the demand to 30%, the valve should open immediately, then adjust controller demand as desired.

D. (a) both of the permissives (b) set the demand to 30%, the valve should open within 1 minute, then adjust controller demand as desired.

Answer: D Associated KA:

L75014 Explain the operation of the Atmospheric Dump Valves under normal operating conditions.

Reference Id: Q3770 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: Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40OP-9SG01, Main Steam K&A: Ability to manually operate and/or monitor in the control room: Steam dump valves.

Justification:

A is Wrong - requires both permissives and initial opening requires the demand be set at 30% also requires a minute to open B is Wrong - initial opening requires the demand be set at 30% (PV event)

C is Wrong - requires both permissives requires a minute to open D is Correct - this is correct operation per PVNGS note in the procedure mentions valve opens within a minute after to apply force required to overcome bonnet pressure. This reflect back to the PVNGS event of the 80s when the CR operators were unable to operate ADVs from the CR due to setting demand to low (10%)

OPTRNG_EXAM Page: 37 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 25 This Exam Level RO Apears on:

K/A # 34059k4.16 Importance Rating:

Four conditions that will cause a Feedwater Pump Trip are Lo Vacuum, ...

A. Hi vibrations, Hi discharge pressure and Thrust Bearing Wear B. Lo bearing oil pressure, Loss of speed signal and Hi vibrations C. Thrust Bearing Wear, Lo suction pressure and Hi discharge pressure D. Lo suction pressure, Lo bearing oil pressure and Loss of speed signal Answer: C Associated KA:

100866 Active Question Bank 2004 L74627 Describe the conditions required to generate the following annunciators.

FWPT Trip

FWPT Trip Ckt Energized

FWPT Lube Oil Press Low

FWPT High Vibration

FWP Discharge Press High

FWPT Suction Pressure Low L82496 Explain the operation of the MFWP Turbine Trip subsystem under normal operating conditions.

Reference Id: Q3418 Difficulty: 3.00 Time to complete: 5 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: Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40AL-9RK6A windows 3B, 5A, 2A & 3C K&A: Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following: Automatic trips for MFW pumps Justification:

A is Wrong - Hi vibrations is alarm not trip B is Wrong - Loss of speed signal and Hi vibrations are is alarms not trip C is Correct - all trips not alarms D is Wrong - Loss of speed signal is alarm not trip OPTRNG_EXAM Page: 38 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 26 This Exam Level RO Apears on: SRO EXAM 2007 K/A # 34061a2.05 Importance 3.40 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 745 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.

Which ONE of the following actions correctly address the existing symptoms in accordance with the Excess Steam Demand procedure?

A. AFAS-2 has failed. Throttle and balance flow to each steam generator.

B. SG 2 > SG 1 lockout has failed. Stop feeding SG #1 and allow SG #2 to feed in RTO.

C. AFAS-2 has failed. Initiate maximum flow to SG #2, allow maximum flow to SG

1 until level is greater than 10%.

D. SG 2 > SG 1 lockout has failed. Stop feeding SG #1 and ensure auxiliary feedwater flow is restoring level in SG #2.

Answer: D Associated KA:

L11202 Given conditions of an ESD describe the mitigating strategy outlined in the ESD EOP Reference Id: Q10244 Difficulty: 3.00 Time to complete: 4 Cognitive Level: Comprehension / Anal Question Source: Modified PV Bank Comment:

Proposed reference to be provided to applicant during examination:

Technical

Reference:

40AL-9RK5B windows 5B08C/9C, ESD procedure K&A: Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Automatic control malfunction Justification:

OPTRNG_EXAM Page: 39 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam A is Wrong - SG 2 is > AFAS setpoint and flow and SG 1 flow needs to be stopped B is Wrong - delta-P lockout has failed but RCS is to cold to feed SG 2, 940# = 537 degrees which is prevents RTO flow C is Wrong - AFAS- 2 is fine. SG 2 doesn't not need max flow and SG 1 feed should be stopped D is Correct - DP lockout has failed setpoint is 185 psid, stop feeding SG 1 27 This Exam Level RO Apears on:

K/A # 36063k2.01 Importance Rating:

The Main Turbine Emergency Bearing Oil pump is powered from the system.

A. PK, 125 VDC Class B. PH, 480 VAC Class C. NK, 125 VDC Non-Class D. NH, 480 VAC Non-Class Answer: C Associated KA:

L68175 Describe the major Loads associated with the Non-Class 125 VDC Power System.

Reference Id: Q10511 Difficulty: 2.00 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: Memory Question Source: New Comment:

Proposed reference to be provided to applicant during examination:

Technical

Reference:

40OP-9LO01, MT Lube Oil system K&A: Knowledge of bus power supplies to the following: Major dc loads Justification:

A is Wrong -

B is Wrong -

C is Correct - any other answer in incorrect, NKN-M46 is the power supply D is Wrong -

OPTRNG_EXAM Page: 40 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 28 This Exam Level RO Apears on:

K/A # 36064k1.03 Importance Rating:

Per LCO 3.8.3, Diesel Generator Fuel OIl Storage Tank level must be maintained greater than (a) level in order to provide storage for (b) days of continuou 100% rated output operation.

A. (a) 71% (b) 7 B. (a) 80% (b) 7 C. (a) 71% (b) 10 D. (a) 80% (b) 10 Answer: B Associated KA:

L75054 Explain the operation of the Diesel Fuel Oil sub-system under normal operating conditions.

Reference Id: Q10512 Difficulty: 3.00 Time to complete: 2 10CFR Category: CFR 55.41 (8) 55.41 (8) Components, capacity, and functions of emergency systems.

Cognitive Level: Memory Question Source: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Tech Specs and Bases K&A: Knowledge of the physical connections and/or cause-effect relationships between the ED/G system and the following systems: Diesel fuel oil supply system Justification:

A is Wrong - 71% is mentioned in TS and is the level below which 3.0.3 would apply. 7 days is correct B is Correct - 80% and 7 days per LCO 3.8.3 C is Wrong - 10 days is the LCO limit per 3.8.1 D is Wrong - 10 days is the LCO limit per 3.8.1 OPTRNG_EXAM Page: 41 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 29 This Exam Level RO Apears on:

K/A # 37073a1.01 Importance Rating:

Given the following Unit 1 conditions:

The plant is in a normal full power alignment

Dry Cask storage and transfer operations are in progress

"A" train of Control Room Essential Filtration System (CREFAS) is is bypass

An event occurs causing Hi Radiation levels in the Fuel Building

RU-19, New fuel storage area monitor

RU-31, Fuel building ventilation monitor

RU-145, Fuel building ventilation monitor

RU-146, Fuel building ventilation monitor Which one of the following should occur if radiation levels continue to increase?

A. RU-145 will shutdown, RU-146 comes on line B. RU-31 will shutdown, RU-146 will come on line C. RU -19 will initiate a full FBEVAS and CREVAS actuation D. RU-145 will initiate a full FBEVAS actuation, only B train CREFAS actuates Answer: A Associated KA:

66731 Describe the interlocks associated with the Radiation Monitors at PVNGS Reference Id: Q10513 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: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

LOIT lesson plan / 40OP-9SA01, BOP ESFAS operations / System Training Manuals K&A: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRM system controls including: Radiation levels Justification:

A is Correct - RU-145 (low range) will shutdown after FBEVAS due to the monitor becoming over saturated, RU-146 high range comes on line B is Wrong - RU-31does not shutdown OPTRNG_EXAM Page: 42 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam C is Wrong - RU-19 does not actuate either FBEVAS signal, RU-31/145 D is Wrong - Ru-145 will initiate a full FBEVAS signal and both trains of CREFAS sill initiate. X-trips are downstream of bypass OPTRNG_EXAM Page: 43 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 30 This Exam Level RO Apears on:

K/A # 34076a1.02 Importance Rating:

The following conditions exist:

The reactor is at 100% power

Plant Cooling water pump "A" discharge pressure is rapidly degrading

Plant Cooling water pump "B" trips on an 86 when it attempts to auto start

Plant Cooling water header pressure continues to degrade The CRS should direct ...

A. cross connecting EW to NC per 40AO-9ZZ03 B. an immediate Reactor trip and perform SPTAs C. a Turbine trip and perform 40AO-9ZZ08, Load Rejection D. one attempt to reset the 86 on the "B" PW pump per the Relay Resetting procedure Answer: B Associated KA:

L62235 Given the Loss of Cooling Water AOP is being performed determine the appropriate mitigating strategies for a loss of plant cooling water Reference Id: Q9937 Difficulty: 3.00 Time to complete: 4 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: Memory Question Source: PV Bank Not Modified Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40A0-9ZZ03, Loss of Cooling Water AOP / Relay resetting procedure, 40DP-9OP02 K&A: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including: Reactor and turbine building closed cooling water temperatures.

Justification:

A is Wrong - would be performed for a loss of NC only B is Correct - procedure directs Rx trip and SPTAs C is Wrong - Turbine Trip would reduce heat load but not directed by this procedure OPTRNG_EXAM Page: 44 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam D is Wrong - 86 relays can only be reset in emergency if the DG is tied to the bus OPTRNG_EXAM Page: 45 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 31 This Exam Level RO Apears on:

K/A # 34076k3.05 Importance Rating:

Given the following plant conditions:

Unit 1 is on Shutdown Cooling 'A' in a normal alignment.

RCS temperature is 240° F

RCS pressure is 195 psia

A tube leak has just begun in the 'A' SDC heat exchanger.

Which ONE of the following symptoms will occur?

A. RU-6, NC rad monitor alarm B. Decreasing spray pond level C. Increasing EW 'A' surge tank level D. Increasing rad levels in the west piping penetration room Answer: C Associated KA:

100866 Active Question Bank 2004 N76946 Describe the interface between the Essential Cooling Water system and its support/supported systems.

L65400 Describe how the Essential Cooling Water system is supported by the following systems:

Radiation Monitoring (SQ)

Service Gas (GA)

Demineralized Water (DW)

Chemical Waster (CM)

Fire Portection (FP)

Condensate Transfer (CT)

Spray Pond (SP)

Plant Protection System (SA)

Auxiliary Building HVAC (HA)

4160 Class Distribution (PB)

480 VAC Class Motor Control Centers (PH)

Essential Chilled Water (EC)

L65403 Describe how the Essential Cooling Water system supports the following systems:

Essential Chilled Water (EC)

Safety Injection (SI)

Nuclear Cooling Water (NC)

Fuel Pool Cooling (PC)

Reference Id: Q20925 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.

OPTRNG_EXAM Page: 46 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam Cognitive Level: Comprehension / Anal Question Source: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

LOIT lesson plan K&A: Knowledge of the effect that a loss or malfunction of the SWS will have on the following: RHR components, controls, sensors, indicators, and alarms, including rad monitors Justification:

A is Wrong - SDC is cooled by EW system.

B is Wrong - SDC is at a higher pressure than EW C is Correct - EW is the cooling medium for SDC and is at a higher pressure than EW.

D is Wrong - the "bowling alley" pipe chase is a long distance from the SDC Room and is not an expected symptom for this type of event.

OPTRNG_EXAM Page: 47 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 32 This Exam Level RO Apears on:

K/A # 38078a3.01 Importance Rating:

Given the following conditions:

Unit 1 is operating in a normal full power alignment The normal Instrument Air pressure is (a) psig and the Nitrogen backup valve opens at (b) psig.

A. (a) 115 (b) 95 B. (a) 115 (b) 85 C. (a) 105 (b) 95 D. (a) 105 (b) 85 Answer: B Associated KA:

L76595 Describe the Control Room indications associated with the Instrument Air system.

Reference Id: Q10515 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: Memory Question Source: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40OP-9IA01, IA system / 40AL-9RK7B, 7B01B ARP K&A: Ability to monitor automatic operation of the IAS, including: Air pressure Justification:

A is Wrong - 115 is correct but 95 is the low pressure alarm B is Correct - 115 is correct and the N2 backup opens at 85 psig C is Wrong - 105 is when the 3rd compressor should start and 95 is the low pressure alarm D is Wrong - 105 is when the 3rd compressor should start but 85 is when the backup opens OPTRNG_EXAM Page: 48 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 33 This Exam Level RO Apears on:

K/A # 35103a3.01 Importance Rating:

Given the following plant conditions:

Containment pressure Channel A is 3.4 psig

Containment pressure Channel B is 2.7 psig

Containment pressure Channel C is 3.1 psig

Containment pressure Channel D is 2.6 psig

Pressurizer pressure Channel A is 1845 psia

Pressurizer pressure Channel B is 1830 psia

Pressurizer pressure Channel C is 1832 psia

Pressurizer pressure Channel D is 1840 psia

SG 1 pressure Channel A is 980 psia

SG 1 pressure Channel A is 950 psia

SG 1 pressure Channel A is 970 psia

SG 1 pressure Channel A is 970 psia

Any required ESFAS actuations have properly initiated

Assuming NO Operator actions, the SG sample valves are ....

A. closed due to SIAS & CIAS actuations only B. closed due to a CIAS, SIAS and MSIS actuations C. open, Hi containment trip setpoint (CIAS) has not been reached D. open, Lo SG pressure trip setpoint (MSIS) has not been reached Answer: B Associated KA:

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

Reference Id: Q10516 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:

41AL-9RK5B windows 5C, 6C and 7C K&A: Ability to monitor automatic operation of the containment system, including:

Containment isolation OPTRNG_EXAM Page: 49 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam Justification: 3.0 psig in cntmt will initiate CIAS, SIAS and MSIS signals A is Wrong - Valves will be closed, all 3 signals were generated not just SIAS/CIAS B is Correct - Valves will be closed due all 3 ESFAS actuations C is Wrong - open is wrong and CIAS initiates at 3 psig D is Wrong - open is wrong but it is true that Lo pressure MSIS has not initiate OPTRNG_EXAM Page: 50 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 34 This Exam Level RO Apears on:

K/A # 37012K502 Importance Rating:

Given the following conditions:

Unit 1 is operating at 100% output

RCP 1A experiences a failure causing it to slow down at 1% per minute Assuming that all other input parameters remained the same, the CPC calculated value of DNBR will ...

A. not change until RCP speed reaches 95% of rated speed, then a DNBR trip will occur.

B. not change until RCP speed reaches 95% of rated speed, then an Auxiliary trip will occur.

C. gradually decrease until RCP speed reaches 95% of rated speed, then a DNBR trip will occur.

D. gradually decrease until RCP speed reaches 95% of rated speed, then an Auxiliary trip will occur.

Answer: C Associated KA:

100866 Active Question Bank 2004 L78285 Explain how RCS Mass Flow rate is calculated in the Core Protection Calculators.

L98190 Describe the function of the Reactor Coolant Pump Speed inputs to the Core Protection Calculators.

L77427 Describe the function of the Reactor Coolant Pump Speed inputs to the Core Protection Calculators.

L98190 Describe the function of the Reactor Coolant Pump Speed inputs to the Core Protection Calculators.

Reference Id: Q3180 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:

OPTRNG_EXAM Page: 51 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 35 This Exam Level RO Apears on:

K/A # 35103k3.03 Importance Rating:

Given the following conditions:

Unit 1 is in Mode 6

Refueling Purge is in operation

Core alterations are in progress

RU-38, Power Access Purge B monitor has failed high and been placed in Bypass

Effluents Tech reports that RU-37, Power Access Purge Monitor A has failed a channel check and recommends that the monitor be declared Inoperable Which one of the following actions is required?

A. Containment must be evacuated B. Core alterations must be stopped C. RU-34, Containment Building Refueling Purge Monitor must be placed in service D. Both trains of Control Room Essential Venation Actuation System (CREVAS) must be placed in service Answer: B Associated KA:

75094 Describe LCO 3.9.3 and its basis.

Reference Id: Q10517 Difficulty: 4.00 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:

Technical

Reference:

LCO 3.9.3 K&A: Knowledge of the effect that a loss or malfunction of the containment system will have on the following: Loss of containment integrity under refueling operations.

Justification:

A is Wrong - there is no accident in progress just a monitor/setpoint failure B is Correct - LCO 3.9.3 requires that during core alterations contmt penetrations must be operable this would include CPIAS closure of refueling purge valves C is Wrong - RU-34 is required for refueling purge operations D is Wrong - CPIAS cross trips CREFAS but this action is not required OPTRNG_EXAM Page: 52 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam OPTRNG_EXAM Page: 53 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 36 This Exam Level RO Apears on:

K/A # 34045k5.23 Importance Rating:

Given the following conditions:

Reactor power is currently at 40%

Rod control (CEDMCS) is in Auto Sequential

Group 5 CEAs are at 120 inches withdrawn

A power accession to 60% is being performed

A 1 gpm dilution is in progress

NO Turbine load adjustments have been made

RK window 4A08B, T-avg / T-ref, is in alarm

CEA Auto Control Status has high a demand light illuminated Which one of the following conditions is occuring?

A. CEAs are inserting at 3 inches per minute B. CEAs are inserting at 30 inches per minute C. CEAs are withdrawing at 3 inches per minute D. CEAs are withdrawing at 30 inches per minute Answer: A Associated KA:

30269 Rod Control & Boron concentration relationship L78793 Describe the normal operation and any automatic functions / interlocks associated with CEDMCS.

Reference Id: Q10518 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: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40AL-9RK4A, window 4A08B / LOIT lesson plan / STM K&A: Knowledge of the operational implications of the following concepts as the apply to the MT/B System: Relationship between rod control and RCS boron concentration during T/G load increases Justification:

A is Correct - CEA will be inserting and AS is limited to 3 inches per minute OPTRNG_EXAM Page: 54 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam B is Wrong - same as above, 30 inches is available in manual only C & D are Wrong - CEAs will have an insertion demand signal OPTRNG_EXAM Page: 55 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 37 This Exam Level RO Apears on:

K/A # 34056k1.03 Importance Rating:

Given the following conditions:

Unit 1 is operating at rated power

The Secondary is in a normal full power alignment

Feedwater Pumps A & B low suction pressure alarms (white alarm lights) have annunciated Which one of the following conditions could have occrued?

A. Lo-Lo level in the A Low Pressure heater strings B. Instrument Air isolated to B condensate pump miniflow valve C. Condensate Demin Bypass valve CDN-PDV-195 output is 0%

D. Either of the B condensate suction valves CDN-HV-1 or 2 has closed Answer: B Associated KA:

L67439 Discuss the purpose and conditions under which the Condensate System is designed to function.

Reference Id: Q10519 Difficulty: 3.00 Time to complete: 2 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: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

LOIT lesson plan / 40AL-9RK6A, window 6A05D K&A: Knowledge of the physical connections and/or cause-effect relationships between the Condensate System and the following systems: MFW .

Justification:

A is Wrong - Hi-HI level will cause a LP string to isolate B is Wrong - miniflow fails open on loss of IA C is Correct - CDN-HV-195 is reverse acting 0% output means the valve is open = more pressure to suction D is Wrong - Both CDN_HV-1 & 2 have to close to cause the B condensate pump to trip OPTRNG_EXAM Page: 56 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 38 This Exam Level RO Apears on:

K/A # 2.1.4 Importance Rating:

Per Conduct of Shift Operations, 40DP-9OP02, the minimum requirements to maintain an active Reactor Operator license are...

A. 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of licensed watchstanding duties in the previous month B. 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months of licensed watchstanding duties in the previous month C. 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of licensed watchstanding duties in the previous calendar quarter D. 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months of licensed watchstanding duties in the previous calendar quarter Answer: D Associated KA:

L12030 State the minimum requirements for shift crew manning.

Reference Id: Q10520 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: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40DP-9OP02 K&A: Conduct of Operations: Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

Justification:

D is Correct - 60 HOURS PER QUARTER IS THE ONLY CORRECT ANSWER OPTRNG_EXAM Page: 57 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 39 This Exam Level RO Apears on:

K/A # 2.1.27 Importance Rating:

Why do the the Fuel Building Essential AFUs automatically align to the Auxiliary Building during a SIAS?

A. The essential AFU simply augment the normal AFUs, ensuring a negative pressure is maintained.

B. Due to the number of additional heat loads, such as motors and piping, additional air movement is necessary.

C. The essential AFUs are responsible for treating the air below the 100' elevation, which may contain contamination from a SI pump seal failure.

D. Since the normal AHUs and AFUs trip on a SIAS, the Fuel Building Essential AFUs will ensure a negative pressure is kept on the building.

Answer: C Associated KA:

67350 Discuss the purpose and conditions under which the Fuel Building HVAC System is designed to function.

N77019 Describe the normal operation of the Normal Exhaust AFUs.

L62455 Given that a SIAS has actuated Identify why the Fuel Building essentials AFU take a suctions on the AUX building below the 100' 100866 Active Question Bank 2004 Reference Id: Q8310 Difficulty: 2.00 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: Memory Question Source: PV Bank Not Modified Comment:

Proposed reference to be provided to applicant during examination:

Technical

Reference:

K&A: Conduct of Operations: Knowledge of system purpose and or function.

Justification:

A is Correct -

B is Correct -

C is Wrong -

D is Wrong -

OPTRNG_EXAM Page: 58 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 40 This Exam Level RO Apears on:

K/A # 2.1.34 Importance Rating:

Which one of the below listed conditions would require an immediate Reactor trip?

A. RCP 1A seal failure and Bleedoff flow is 7 gpm B. RCS leak with letdown is service, 3 charging pumps operating and lowering pressurizer level C. Main Generator sync'd to the grid with 1400 MW output and Condenser Vacuum is 5 inches HgA D. Steam Generator Chemistry, Chlorides are > 1 ppm with a corresponding rise in Cation Conductivity Answer: D Associated KA:

L10043 Determine if a reactor trip is necessary and if so, what actions are required after the trip Reference Id: Q22405 Difficulty: 4.00 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:

Conduct of Operations: Knowledge of primary and secondary plant chemistry limits Proposed reference to be provided to applicant during examination:

Technical

Reference:

K&A:

Justification:

A is Correct -

B is Correct -

C is Wrong -

D is Wrong -

OPTRNG_EXAM Page: 59 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 41 This Exam Level RO Apears on:

K/A # 2.2.21 Importance Rating:

Given the following conditions:

Unit 1 is in mode 1

The "A" Diesel Generator (DG) and Spray Pond pump were removed from service for scheduled maintenance on July 1st

The DG quarterly SR 100% date was July 1st

Today is July 3rd, all work and required retest of the "A" DG have been completed The minimum requirements to declare the "A" DG Operable is that the "A" Spray pond pump be ...

A. Functional. (only)

B. Operable. (only)

C. Functional and the quarterly Diesel SR is completed.

D. Operable and the quarterly Diesel SR is completed.

Answer: B Associated KA:

L79568 Given a copy of TS and the TRM Determine if a specific piece of equipment is required to be operable.

Reference Id: Q22406 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: New Comment:

Equipment Control Knowledge of pre- and post-maintenance operability requirements.

Proposed reference to be provided to applicant during examination:

Technical

Reference:

K&A:

Justification:

A is Correct -

B is Correct -

C is Wrong -

D is Wrong -

OPTRNG_EXAM Page: 60 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 42 This Exam Level RO Apears on:

K/A # 2.2.42 Importance Rating:

Given the following conditions:

Unit 1 is operating at rated power Which one of the following is an entry level condition for Tech Specs?

A. 610 psig in SIT 1A B. 60% Pressurizer level C. 86 lockout/trip of the "A" Fuel Pool Cooling pump D. 86 lockout/trip of a single DG "A" starting air compressor Answer: B Associated KA:

L89775 Given a set of plant conditions determine whether or not the LCOs of 3.4 are satisfied Reference Id: Q22407 Difficulty: 4.00 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:

Tech specs K&A: Equipment Control: Ability to recognize system parameters that are entry level conditions for Tech Specs Justification:

A is Wrong - 610 psig is the low alarm, TS is 600 psig B is Correct - LCO 3.4.9 27 band is 27 to 56% pzr level C is Wrong - "A" fuel pool cooling is a class powered pump but not TS, temp is the LCO D is Wrong - DG air pressure is TS not the compressors OPTRNG_EXAM Page: 61 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 43 This Exam Level RO Apears on:

K/A # 2.3.4 Importance Rating:

Which of the following is the 10 CFR20 annual exposure limit for Whole Body (TEDE) and Lens of the eyes (LDE)?

A. 1500 mrem TEDE, 15 Rem LDE B. 1500 mrem TEDE, 50 Rem LDE C. 5 Rem TEDE, 15 Rem LDE D. 5 Rem TEDE, 50 Rem LDE Answer: C Associated KA:

30226 exposure limits Reference Id: Q22408 Difficulty: 2.00 Time to complete: 2 10CFR Category: CFR 55.41 (12) 55.41 (12) Radiological safety principles and procedures.

Cognitive Level: Memory Question Source: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

General Employee Training / EPIP-99, appendix K K&A: Radiation Control: Knowledge of radiation exposure limits under normal or emergency conditions.

Justification:

A is Wrong - 1500mrem is the quarterly limit, 15 LDE is correct B is Wrong - 1500mrem is the quarterly limit, 50 is the extremities limit C is Correct - 5 Rem is the yearly TEDE limit and 15 is correct D is Wrong - 5 Rem is the yearly TEDE limit, 50 is the extremities limit OPTRNG_EXAM Page: 62 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 44 This Exam Level RO Apears on:

K/A # 2.3.13 Importance Rating:

Given the following conditions:

Unit 1 is operating at rated power

Unit 3 is supplying the Aux Steam Cross-Tie Header

ERFDADS leakrate has increased from .3 to 1.1 gpm

RU-139, Main Steam Line monitor shows an increasing trend

RU-141, Condenser Vacuum/Gland Seal Exhaust shows an increasing trend

RU-142, (all channels) Main Steam Line N-16 monitor show an increasing trend Which one of the following actions is NOT directed by the Excessive RCS Leakrate AOP for these conditions?

A. Select OFF on SGN-HS-1007 & 1008, Mode select switches B. Close the Unit 3 Aux Steam isolation valve to the x-tie header C. Place ARN-HS-19, Post Filter Mode Select Switch, in the "THRU FILTER MODE" D. Throttle open CDN-HV-275, Demin Water Feed to the Condensate Service Header Answer: B Associated KA:

L10174 Given indications of a Steam Generator Tube Leak, describe the possible adverse effects of SBCS and Aux. Stream operation, and the operator action to minimize these consequences.

Reference Id: Q22409 Difficulty: 4.00 Time to complete: 4 10CFR Category: CFR 55.41 (12) 55.41 (12) Radiological safety principles and procedures.

Cognitive Level: Memory Question Source: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40AO-9ZZ02, Excessive RCS Leakrate K&A: Radiation Control: Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Justification: all of these actions except isolating Unit 3 from the aux steam x-tie header can be found in appendix C of 40AO-9ZZ02 A is Wrong -

B is Correct -

OPTRNG_EXAM Page: 63 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam C is Wrong -

D is Wrong -

OPTRNG_EXAM Page: 64 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 45 This Exam Level RO Apears on:

K/A # 2.4.32 Importance Rating:

Given the following conditions:

Unit 1 is raising power to 100% following a SNOW outage

Current power is 80%

The Crew has confirmed a complete loss of annunciators

The Plant Computer (PC) has been verified as not reliable Which of the following auctions is directed by 40AO-9ZZ15, Loss of Annunciators?

A. Immediately trip the reactor, perform SPTAs B. Stabilize the plant at the current power level C. Continue the power increase to 100% with increased monitoring D. Perform a plant shutdown if annunciators are not restored within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Answer: B Associated KA:

L56949 Determine if the Loss of Annunciators AOP should be implemented.

Reference Id: Q22411 Difficulty: 4.00 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:

40AO-9ZZ15, Loss of Annunciators K&A: Emergency Procedures / Plan Knowledge of operator response to loss of all annunciators.

Justification:

A is Correct -

B is Correct -

C is Wrong -

D is Wrong -

OPTRNG_EXAM Page: 65 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam 46 This Exam Level RO Apears on:

K/A # 44E06ek1.1 Importance 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.

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?

Answer:

Associated KA:

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: 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:

40EP-99EO06, LOAF K&A: Knowledge of the operational implications of the following concepts as they apply to the (Loss of Feedwater) Normal, abnormal and emergency operating procedures associated with (Loss of Feedwater). facility's license and amendments.

Justification:

A is Correct - step 4 of LOAF B is Wrong - PBA-S03 is dead C is Wrong - no indication that AFAS is currently required and no AF pumps are available D is Wrong - Condensate pumps are performed in the FRP OPTRNG_EXAM Page: 66 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Reactor Operator Exam Cognitive Level Summary Number of questions linked: 45 Percentage Memory 23 23 Comprehension 0 0 Analysis 0 0 Question Source Summary Number of questions linked to source: 45 Percentage New New 28 28 Modified INPO Bank Modified 0 PV Bank Modified 8 Total Modified 8 8 Bank INPO Bank Not Modified 0 PV Bank Not Modified 9 PV NRC Exam Question Not Modified 0 Total BANK 9 9 OPTRNG_EXAM Page: 67 of 67 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 1

This Exam Level SRO Apears on: SRO EXAM 2008 Tier 1 Group 1 K/A # 2.4.44 Importance 4.40 Rating:

Given the following conditions:

Unit 1 was manually tripped due to lowering Pzr pressure and level

SIAS/CIAS/MSIS have properly initiated

SBCS is maintaining T-cold at 565ºF

RCS pressure is stable at 1750 psia

HPSI flow is adequate

Cntmt pressure which had been 4.5 psig is rapidly dropping

RU-148 is reading 2.2E +05 mrem/hr

RU-149 is reading 2.3E +05 mrem/hr

Wind is from 210º What (if any) Protective Action Recommendations (PARs) should be made for these conditions?

A. No PARs are required B. Shelter within a 2-mile radius C. Evacuation for a 2-mile radius and 5 miles in sectors A-B-C D. Evacuation for a 2-mile radius and 5 miles in sectors B-C-D Answer: B Associated KA:

L92708 Given the appropriate portions of EPIP-01 and either plant conditions or an EAL identify the prescribed Protective Action Recommendations.

Reference Id: Q10469 Difficulty: 3.00 Time to complete: 4 10CFR Category: CFR 55.43 (5) 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: EPIP-99, appendices A (table 1) & B Technical

Reference:

EPIP-99, appendices A & B K&A: Knowledge of emergency plan protective action recommendations.

Justification:

A is wrong - event is an SAE requiring PARs OPTRNG_EXAM Page: 1 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam B is correct - event is SAE requiring shelter for a 2-mile radius

1. potential loss of RCS (LOCA) with no loss of subcooling [1-6]

2. loss of containment [1-10]

C and D are wrong - Rad Monitor reading while elevated do not meet requirement for a LOSS of Fuel Clad Barrier which would elevate to a GE and require evacuation OPTRNG_EXAM Page: 2 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 2

This Exam Level SRO Apears on:

K/A # 2.4.20 Importance Rating:

The following plant conditions exist:

Unit 1 tripped from 100% power.

Pressurizer pressure is 1600 psia and lowering.

PZR level is 28% and lowering.

Containment pressure is 3.5 psig and increasing.

SG #1 pressure is 1090 psia and stable.

SG #2 pressure is1100 psia and stable.

SG #1 level is 70% WR and lowering.

SG #2 level is 70% WR and lowering.

RCS T-cold is 560°F and slowly lowering.

Containment temperature is 112°F and increasing.

Containment humidity is 42% and increasing.

HPSI flow is 150 gpm to each loop.

SIAS/CIAS/MSIS have initiated.

The CRS has come to the step in the Emergency Operating Procedure regarding throttling HPSI flow and finds the following:

CAUTION Throttling HPSI injection valves will cause erosion to downstream piping The correct mitigating EOP for these conditions is (A) and throttling HPSI injection valves to lower HPSI flow (B)

A. (A) LOCA (B) is not permitted B. (A) ESD (B) is not permitted C. (A) LOCA (B) is permitted but not preferred D. (A) ESD (B) is permitted but not preferred Answer: C Associated KA:

16350 Describe the use of cautions and notes in the EOPs.

Reference Id: Q10483 Difficulty: 0.00 Time to complete: 0 10CFR Category: CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

OPTRNG_EXAM Page: 3 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam Cognitive Level: Comprehension / Anal Question Source: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40DP-9AP16, EOP Users Guide 40DP-9AP15 EOP writers guide K&A: Knowledge of the operational implications of EOP warnings, cautions, and notes.

Justification:

A is Wrong - LOCA is correct but caution only warn of potential hazard not give direction B is Wrong - ESD is wrong C is Correct - LOCA is correct and the caution would prefer full valve stroke but it is not required D is Wrong - ESD is Wrong OPTRNG_EXAM Page: 4 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 3

This Exam Level SRO Apears on:

K/A # 2.1.25 Importance Rating:

Given the following conditions:

Unit-1 has been shutdown for five days and is currently in Mode 5

The RCS is being maintained at 102 ft 6 inches in preparation for installing Steam Generator Nozzle Dams

The Steam Generator primary manways are off

RCS temperature is 135 ºF Per the tables found in the Unit-1 Safety Analyses Operational Data (SAOD) during a sustained Loss of Shutdown Cooling the RCS ...

A. time to boil is 18.9 minutes B. time to boil is 23.3 minutes C. makeup flowrate to compensate for boil off is 76.9 gpm D. makeup flowrate to compensate for boil off is 98.5 gpm Answer: D Associated KA:

L56598 Given the LMFRP HR-2 is being performed, and provided with Time to Boil curves determine time to core boiling using the TTB curves in the back of the core data book and describe what this value is used for 100866 Active Question Bank 2004 Reference Id: Q1187 Difficulty: 4.00 Time to complete: 5 10CFR Category: CFR 55.43 (5) 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: Unit-1 Safety Analysis Operational Data (SAOD)

Technical

Reference:

Unit-1 Safety Analysis Operational Data (SAOD)

K&A: Ability to interpret reference materials, such as graphs, curves, tables, etc.

Justification:

A is Wrong, time to boil at midloop is 14.7 minutes (18.9 comes from flange level after core reload)

B is Wrong, time to boil at midloop is 14.7 minutes (23.3 comes from flange level prior to core reload)

OPTRNG_EXAM Page: 5 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam C is Wrong, 76.9 gpm is the makeup requirement for midloop after core reload D is Correct, this is the makeup rate for midloop prior to core offload OPTRNG_EXAM Page: 6 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 4

This Exam Level SRO Apears on:

K/A # 42056AA209 Importance Rating:

Given the following plant conditions:

The plant is operating at 100% power

NAN-S02 Fast Bus Transfer is blocked due to SWYD maintenance

The "A" and "C" Containment Normal ACUs are running

The "B' and "D" Containment Normal ACUs are in standby.

The "A" and "B" Normal Chillers are running

NAN-S05 bus faults and de-energizes

All equipment actuates as expected The CRS should implement ...

A. 40EP-9EO02 (Reactor Trip), containment cooling can be restored by cross connecting Essential Cooling Water to Nuclear Cooling Water B. 40EP-9EO07 (LOOP), containment cooling will be restored when the A & C normal containment ACUs and the A normal chiller automatically restart after the "A" train LOP C. 40EP-9EO07 (LOOP), containment cooling can be restored by cross connecting Essential Cooling Water to Nuclear Cooling Water D. 40EP-9EO02 (Reactor Trip), containment cooling will be restored when the A &

C normal containment ACUs and the A normal chiller automatically restart after the "A" train LOP Answer: C Associated KA:

74452 Describe the automatic functions associated with the Containment Building Normal ACU Fans (HCN-A01-A, B, C, & D) .

Reference Id: Q10470 Difficulty: 4.00 Time to complete: 0 10CFR Category: CFR 55.43 (5) 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-0EO07(LOOP)

K&A: Ability to determine and interpret the following as they apply to the Loss of Offsite Power: Operational status of reactor building cooling unit OPTRNG_EXAM Page: 7 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam Justification:

A is Wrong, 40AO-9zz12 may be entered to supplement the EOP in use but the A/C ACUs will restart following the LOP not B/D in addition the fans will be running but normal chillers have lost power due to the LOOP B is Wrong, 40AO-9ZZ20 may be entered to supplement the EOP in use but there are normal chillers running due the loss of NA/NB buses (LOOP)

C is Correct, Although there is power available in the swyd the faulted S05 bus and the fast bus transfer block on the SO2 creates a loss of NA/NB buses requiring entry in to the LOOP procedure. LOOP has steps to x-tie EW to NC to restore cooling as needed.

D is Wrong, the event is LOOP/LOFC in addition there is no auto start of the "A" normal chiller although it is power from PBA-S03 OPTRNG_EXAM Page: 8 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 5

This Exam Level SRO Apears on:

K/A # 44E02EA22 Importance Rating:

Given the following conditions:

Unit - 1 tripped from 100%

RU-142 (N-16 Main steam Line Monitor) channel 1 was reading 92 cpm at the time of the trip

RU-142 (N-16 Main steam Line Monitor) channel 2 was reading 96 cpm at the time of the trip

RCS pressure 2150 psia and slowly lowering

Pressurizer level 31% and recovering

SG 1 level is 65% WR and lowering

SG 2 level is 60% WR and lowering

NAN-S01 is de-energized

PBA-S03 is de-energized

NNN-D11 is de-energized

RCS Thot is 565°F and slowly lowering

RCS Tcold is 562°F and slowly lowering

Main Feedwater flow is 0 gpm to each SG The CRS should enter ...

A. Reactor Trip and stabilize Tcold 560 to 570 ºF B. Loss of All Feedwater and restore SG levels to 45 to 60% NR C. Steam Generator Tube Rupture and lower Thot to less than 540 ºF D. Loss of Offsite Power/Loss of Forced Circulation and initiate MSIS Answer: A Associated KA:

L10350 Given conditions of a reactor trip analyze whether or not entry into the Reactor Trip EOP is appropriate Reference Id: Q10471 Difficulty: 2.00 Time to complete: 2 10CFR Category: CFR 55.43 (5) 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:

Reactor Trip (40EP-9EO02), 40AO-9ZZ14 (Loss of non class instrument power)

OPTRNG_EXAM Page: 9 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam K&A: Ability to determine and interpret the following as they apply to the (Reactor Trip Recovery) Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

Justification:

A is Correct, all indications are consistent with RT and RT directs the use of ADVs to stabilize RCS temerature with a loss of SBCS (NNN-D11)

B is Wrong, SG feed rate is 0 gpm due to low RCS temp < 564 which is the cut off for Reactor Trip Override (RTO). Additionally AF "A" and AF "B" are available C is Wrong, low RCS temperature and pressure could be indicative of SGTR but the SG RU readings are in the normal range D is wrong, NAN-S02 is still energized OPTRNG_EXAM Page: 10 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 6

This Exam Level SRO Apears on:

K/A # 44E06EA22 Importance Rating:

Given the following conditions:

Unit 1 tripped on Lo SG pressure caused by a steam line break

SG 1 pressure is currently 1170 psia being controlled by ADVs

SG 2 pressure is currently 1180 psia being controlled by ADVs

Offsite power was lost on the turbine trip

4160 bus PBA-S03 has faulted and is de-energized

Both SG levels are 20% WR and slowly lowering

AFA-P01 has tripped on overspeed

AFB-P01 has tripped due to an 86 lock-out

Feed rate to both SGs is 0 gpm.

All appropriate ESFAS actuations have initiated Which one of the following would be the appropriate procedurally directed action to restore the RCS Heat Removal Safety Function?

A. Reset AFA-P01 overspeed trip and establish feed after 40EP-9EO06 (LOAF) is entered B. Depressurize a SG and establish feedflow with a Condensate pump after 40EP-9EO09 (FRP) is entered C. Stop the RCPs and establish feed using a Main Feedwater pump after 40EP-9EO07 (LOOP) is entered D. Override the Downcomer isolation valves and establish feed using AFN-P01 prior to exiting the Standard Post Trip Actions Answer: A Associated KA:

L61371 Describe the major mitigating strategies used during a LOAF.

Reference Id: Q10472 Difficulty: 3.00 Time to complete: 4 10CFR Category: CFR 55.43 (5) 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:

EOP Operations Expectations, 40EP-9EO01 (SPTAs). 40EP-9EO06 (LOAF)

OPTRNG_EXAM Page: 11 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam K&A: 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.

Modified from Q10472 Justification:

A is Correct - LOAF allows the resetting of AFA per appendix 38 B is Wrong - Condensate pumps are not available due the LOOP C is Wrong - LOOP will not restore feedwater and MFPs are not available due to MSIS and LOOP causing a loss of vacuum D is Wrong - AFN-P01 has lost power, PBA-S03 OPTRNG_EXAM Page: 12 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 7

This Exam Level SRO Apears on:

K/A # 2.3.14 Importance Rating:

Given the following conditions:

Unit 1 manually tripped due to lowering Pressurizer level and pressure

SIAS/CIAS were manually initiated on trend

AFA-P01 (Steam Driven AFW pump) is OOS and under clearance

T-cold is 564 ºF controlled by SBCVs 1 & 4

RCS pressure is 1850 psia and lowering

Containment pressure is .3 psig and stable

SGs are being fed by Main Feed pumps in RTO

SG 1 level is 55% WR and increasing

SG 2 level is 47% WR and dropping Which one of the following events (occuring independently) would cause an increase the radioactive release rate to atmosphere (get worse)?

A. Offsite power de-energizes B. Both Main Feed pumps trip C. Increasing the RCS leakrate D. NOT stopping 2 RCPs when required Answer: A Associated KA:

L11218 Given that the SGTR EOP is being implemented describe the SGTR EOP mitigation strategy Reference Id: Q10473 Difficulty: 4.00 Time to complete: 3 10CFR Category: CFR 55.43 (4) 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: None Technical

Reference:

40EP-9EO04 K&A: Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

Justification: examinee has adequate information to determine that a SGTR on SG #1is occuring A is correct - a loss of Offsite power will cause a loss of vacuum leading to the use of ADVs or SBCVs 7 and 8 either one will cause a release to atmosphere OPTRNG_EXAM Page: 13 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam B is wrong - with AFA OOS starting any other AFW pump will not cause a release C is wrong - increasing the RCS leakrate with good vacuum will not increase the release to atmosphere D is wrong - with a SGTR not stopping RCPs will not cause a bigger leak as it would for a LOCA OPTRNG_EXAM Page: 14 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 8

This Exam Level SRO Apears on:

K/A # 42069AA201 Importance Rating:

Given the following:

Unit 1 is in Mode 3

NCB-UV-401 failed it's stroke time Surveillance Test and has been declared INOPERABLE Containment Isolation (LCO 3.6.3) ...

A. does not apply in Mode 3 B. does not apply, NCB-UV-401 closes on a Containment Spray signal C. can be complied with by closing and tagging NCN-HCV-491 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months D. can be complied with provided the system remains filled and check valve NCA-V118 remains Operable Answer: C Associated KA:

L89788 Given a set of plant conditions apply the one hour or less actions statements of T.S. 3.6 Reference Id: Q10474 Difficulty: 5.00 Time to complete: 3 10CFR Category: CFR 55.43 (1) 55.43 (1) Conditions and limitations in the facility license.

Cognitive Level: Memory Question Source: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Tech Specs 3.6.3 K&A: Ability to determine and interpret the following as they apply to the Loss of Containment Integrity:

Justification:

OPTRNG_EXAM Page: 15 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam A is wrong - 3.6.3 applies modes 1 - 4 B is wrong - the valve does close on CSAS but CIAS does apply C is correct - LCO 3.6.3 condition A allows the use of a check valve and slow thru the valve secured D is wrong - check valve can be given credit with flow secured OPTRNG_EXAM Page: 16 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 9

This Exam Level SRO Apears on:

K/A # 44A16AA22 Importance Rating:

Given the following conditions:

Letdown flow has lowered to maintain Pzr level constant.

RCS temperature is stable.

ERFDADS indicates a stable 12 gpm RCS leakrate

Equipment Drain Tank (EDT) level is increasing.

RU-1 (Containment Atmosphere) is reading 7.5 E - 02 µCi/cc

RU-6 (Nuclear Cooling Water) is reading 1.14 E - 06 µCi/cc

RU-141, ch 1 (Condenser Vacuum/Gland Steam Exhaust) is reading 4.61 E - 07 µCi/cc Based on these conditions the operating crew is required to implement the Excessive RCS Leakrate AOP A. section 5.0 due to SG Tube leakage. Take actions per condition B of LCO 3.4.14.

B. section 3.0 due to RCS identified leakage. Take actions per condition A of LCO 3.4.14.

C. section 3.0 due to RCS unidentified leakage. Take actions per condition A of LCO 3.4.14.

D. section 4.0 due to RCS to Nuclear Cooling Water leakage. Take actions per condition B of LCO 3.4.14.

Answer: B Associated KA:

L10169 Given indications of RCS or a Steam Generator Tube Leak, describe the basic procedure methodology, including Reactor Trip is thresholds, Reference Id: Q10475 Difficulty: 3.00 Time to complete: 4 10CFR Category: CFR 55.43 (1) 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: Tech Spec LCO 3.4.14 Technical

Reference:

LCO 3.4.14, 40AO-9ZZ03 (Excessive RCS Leakage)

K&A: Adherence to appropriate procedures and operation within the limitations in the facility*s license and amendments.

Justification:

A is Wrong. this is not a SGTL, RU 141 reading are normal OPTRNG_EXAM Page: 17 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam B is Correct. candidate has sufficient info to determine identified leakage exceeds limits (10 gpm) of LCO 3.4.14. EDT level increasing and normal RU-1 readings indicate identified leakage.

C is Wrong. this is not unidentified leakage it is going to the EDT D is wrong. this is not a leak in to NCW, RU-6 readings are normal OPTRNG_EXAM Page: 18 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 10 This Exam Level SRO Apears on:

K/A # 236 Importance 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. Effluents Supervisor.

C. Chemistry Supervisor.

D. Radiation Protection Supervisor.

Answer: A Associated KA:

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: CFR 55.43 (4) 55.43 (4) Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions.

Cognitive Level: Memory Question Source: PV Bank Not Modified Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

LOIT lesson plan / 74RM-9EF20, GR release permits and offsite dose assessments K&A: Knowledge of the requirements for reviewing and approving release permits.

Justification:

A is Correct - Only the Shift Manager or CRS allowed to approve emergency release's to stabilize the plant during EOP performance B is Wrong -

C is Wrong -

D is Wrong -

OPTRNG_EXAM Page: 19 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 20 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 11 This Exam Level SRO Apears on:

K/A # 37012A203 Importance Rating:

Given the following plant conditions:

Unit 1 is operating at rated power.

Channel B "LO SG-1 PRESS" bistable is bypassed and tripped.

Time 1

Channel A "LO SG-1PRESS" bistable trips due to a transmitter failure.

Time 2

PNB-D26 de-energizes due to a ground fault

The CRS directs recovery actions per the Loss of Class Instrument or Control Power AOP Pressing the "B" Channel PPS bistable bypass button for "LO SG-1 PRESS" will result in a ...

A. reactor trip, implement the Reactor Trip procedure.

B. reactor trip, implement the Loss Of All Feed procedure.

C. full MSIS actuation, implement the Large Load Reject procedure.

D. half leg MSIS actuation, implement guidance per the alarm response procedure.

Answer: A Associated KA:

L77088 Describe the RPS Trip Channel bypass interlock.

Reference Id: Q10476 Difficulty: 0.00 Time to complete: 0 10CFR Category: CFR 55.43 (5) 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:

training material Modified from Q2596 K&A: 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: Incorrect channel bypassing Justification:

Pushing the B train Lo SG 2 pressure pushbutton will cause the B train to come out of Bypass initiating an MSIS and Rx trip OPTRNG_EXAM Page: 21 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam A is Correct - Rx trip will be implemented due to 2/4 Lo SG-1 pressure trip, AFW can be used to feed the SGs B is Wrong - LOAF will not be needed even though MFW will be locked out and require Override of FWIV to restore C is Wrong - examinee may not realize Rx trip (A & B channels) and opt for large load reject due to MSIVs closing D is Wrong - examinee may think the A & B channels or only SG 1 will initiate a half leg trip OPTRNG_EXAM Page: 22 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 12 This Exam Level SRO Apears on:

K/A # 2.4.38 Importance Rating:

Given the following conditions:

Unit 1 tripped 20 minutes ago from 100% power

Offsite power was lost on the trip

Pressurizer level is 0%

Pressurizer pressure is 950 psia and dropping

RCS T-hot is 564 ºF

QSPDS indicates 0º subcooling

PBB-S04 has faulted and is de-energized

AFA-P01 will not come up to speed

HPSI pump "A" is under clearance

RCS activity is 330 µCi/gm Dose Equivalent I-131

Containment pressure is 9.1 psig and increasing

RVLMS indicates 0% in the outlet plenum

All other equipment has functioned as required Which one of the following events would change the current Eplan classification level?

A. CS pump A trips B. AFN-P01 trips on an 86 lockout C. RVLMS indicated plenum level increases to 47%

D. RU-148, CNTMT Rad Monitor readings increase to 4.1 E +05 mrem/hr Answer: A Associated KA:

L58622 Given an Emergency Plan condition, use the EAL tables and basis document to determine the emergency plan classification Reference Id: Q10477 Difficulty: 2.00 Time to complete: 4 10CFR Category: CFR 55.43 (5) 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: Table 1 of EPIP-99 Technical

Reference:

Table 1 of EPIP-99 K&A: Ability to take actions called for in the facility emergency plan, including l supporting or acting as emergency coordinator if required.

OPTRNG_EXAM Page: 23 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam Justification:

A is Correct - loss of CS pump A [1-10] will upgrade classification to a GE, 2 lost barriers and an additional potential lost barrier of cntmt. B CS pump was lost due to PBB-S04 loss B is Wrong - a loss of AFN is a LOAF but this a potential [1-8] and will not cause upgrade already have [1-6] lost in the RCS Barrier C is Wrong - RVLMS increasing will not lower classification [1-2] is or has been below 21%

additionally RCS activity is a loss of Fuel Clad [1-3]

D is Wrong - RU-148 readings are another loss of Fuel Clad no upgrade [1-4] additionally readings do not meet the potential loss of cntmt requirements [1-11]

OPTRNG_EXAM Page: 24 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 13 This Exam Level SRO Apears on:

K/A # 34059A212 Importance Rating:

Given the following conditions:

Unit 1 is operating at 100% power

SG 2 Economizer Feed Regulating Valve SGN-HV-1122 has failed open

Area 2 reports that SGN-HV-1122 is mechanically seized

SG 2 level is 65% NR and RISING

RCS T-cold is 558ºF and LOWERING

The Crew initiates a manual Reactor Trip Assuming no other Operation actions, SG 2 level will continue to increase until a(n) (1) signal is generated and the CRS should implement the (2) procedure upon completing SPTAs.

A. (1) MSIS (2) Reactor Trip B. (1) MSIS (2) Excessive Steam Demand C. (1) High Level Override (2) Reactor Trip D. (1) High Level Override (2) Excessive Steam Demand Answer: B Associated KA:

L11200 Given conditions of an ESD analyze whether or not entry into the ESD EOP is appropriate Reference Id: Q10484 Difficulty: 3.00 Time to complete: 2 10CFR Category: CFR 55.43 (5) 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:

Reactor Trip and ESD procedures / Board 6 alarm response and 40AO-9ZZ17 inadvertant PPS-ESFAS actuations K&A: Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of feedwater regulating valves Justification:

A is Wrong - T-cold below 560 excludes Rx Trip procedure B is Correct - MSIS shuts Isolation valves to stop FW flow, ESD entry conditions include rise in FW flow until stopped by MSIS OPTRNG_EXAM Page: 25 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam C is Wrong - HLO only shuts reg valves not Isolation valves, Rx Trip is wrong D is Wrong - HLO only shuts reg valves not Isolation valves OPTRNG_EXAM Page: 26 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 14 This Exam Level SRO Apears on:

K/A # 2.4.45 Importance Rating:

Given the following conditions:

Unit 1 has tripped from rated power

Offsite power was lost following the reactor trip

DG "B" is under clearance and OOS

DG "A" is supplying power to PBA-S03

AFA-P01 is feeding each SG at 300 gpm

SPTAs have been completed

CRS has implemented the Loss of Offsite Power/ Loss of Forced Circulation

MSIS has been manually actuated NOW

Window 1A04A (125 1E CC M41 CHGR A/AC PNL D21 TRBL) is alarming

Point ID - PKYS3 125 VDC CC PKA-M41 Bus Undv/Ground/Breaker Trip is in alarm

The Reactor Operator reports that the PK "A" bus shows 0 volts The CRS should ...

A. remain in LOOP/LOFC and initiate feedwater flow with AFN-P01 by overriding and opening downcomer isolation valves B. transition to the Loss of All Feed procedure and initiate AFW flow per Standard Appendix 40, Local Operation of AFA-P01 C. transition to the Blackout procedure and restore power and feedwater flow by paralleling Blackout Turbine Generators to PBA-S03 D. transition to the Functional Recovery procedure and implement the appropriate MVAC appendix to restore power and feedwater flow.

Answer: D Associated KA:

L74204 Describe how the 125 VDC Class IE Power System supports the operation of the following systems:

Class IE 4.16 kV Switchgear and 480 Vac Load Centers (PB & PG)

Class IE Standby Generation System (PE)

Auxiliary Feed System (AF)

Safety Injection (SI)

Class IE 120 Vac Instrumentation Power (PN)

Steam Generators (SG)

Reference Id: Q10485 Difficulty: 5.00 Time to complete: 4 10CFR Category: CFR 55.43 (5) 55.43 (5) Assessment of facility conditions and selection of OPTRNG_EXAM Page: 27 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 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 Instrument or Control Power K&A: Emergency Procedures / Plan Ability to prioritize and interpret the significance of each annunciator or alarm.

Justification:

A is Wrong - the loss of PKA-M41 causes a DG trip = no AFN-P01, dual event requires entry into FRP B is Wrong - Dual event requires entry into FRP, LOAF will not address the loss of power although manual operation of AFA would restore AFW flow C is Wrong - dual event requires entry into the FRP. although Blackout would restore power and ultimately restore flow the Blackout assumes that AFA and ADVs are available D is Correct - Loss of PKA-M41 trips the A DG and loses Control Power to AFA-P01 it to shutdown. This is now a dual event Blackout and LOAF, FRP is mandated OPTRNG_EXAM Page: 28 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 15 This Exam Level SRO Apears on:

K/A # 38078A2.01 Importance Rating:

Given the following conditions

Unit 1 is operating at 100% power

Instrument Air System (IA) is aligned for normal operation

IA system pressure is 110 psia

Instrument Air Dryer IAN-M01D has failed and will not supply the IA system Which one of the following is correct?

A. The nitrogen backup valve will open and maintain normal IA header pressure B. The IA header pressure will decrease to ~ 85 psia. Implement 40AO-9ZZ06, Loss of Instrument Air, to valve in another air dryer C. IA dryers are normally aligned for parallel operation. IAN-M01C will maintain normal IA header pressure D. IAN-C02 Service Breathing Air compressor can be aligned to maintain IA pressure ~ 110 psia per 40OP-9IA02, Service/Breathing Air System.

Answer: B Associated KA:

L76601 Describe the flowpath of Service/Breathing Air, including the following:

Air Compressor

Air Receivers

Air Dryers Reference Id: Q10479 Difficulty: 2.00 Time to complete: 3 10CFR Category: CFR 55.43 (5) 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:

40OP-9IA01 (Instrument Air System), 40OP-9IA02 (Service/Breathing Air), 40AO-9ZZ06 (Loss of Instrument Air)

K&A: Ability to (a) predict the impacts of the following malfunctions or operations on the IAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunction Justification:

OPTRNG_EXAM Page: 29 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam A is Wrong - LP nitrogen will open but maintain ~ 85 psia B is Correct - Nitrogen maintains and ZZ06 should be implemented to mitigate effects C is Wrong - IA dryers are not normally aligned for parallel operation but it is an available option per section 4.6 of IA01 D is Wrong - Service Air and IA can not be x-tied, although in the past it was possible OPTRNG_EXAM Page: 30 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 16 This Exam Level SRO Apears on:

K/A # 37015A2.01 Importance Rating:

Given the following plant conditions:

Unit 1 is operating at 100% power

PNB-N12 (Inverter for 1-E-PNB-D26) fails to zero output Which ONE of the following describes the effect on the Nuclear Instrumentation system?

A. Control Channel 2 experiences a momentary CEA withdraw demand when the PN bus shifts to the Voltage Regulator B. B train Safety channel remains Operable. The "B" PN bus automatically shifts to the Voltage Regulator on a loss of Inverter power.

C. Control Channel 2 losses power. Manually select the unaffected instrument (channel 1) at the RRS Test Panel per 40A0-9ZZ16, RRS Malfunction AOP D. B train Safety channel is Inoperable. Power can be restored by manually shifting the "B" PN bus to the Voltage Regulator per 40OP-9PN02.

Answer: D Associated KA:

L75651 Describe how the Nuclear Instrumentation System is supported by the following systems:

Class IE Instrument 120 V AC Power System (PN)

Containment Building HVAC (HC)

Non-Class IE Instrument 120 V AC Power System (NN)

Reference Id: Q10480 Difficulty: 4.00 Time to complete: 3 10CFR Category: CFR 55.43 (5) 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-9ZZ13 (Loss of Class Instrument/Control Power), 40OP-9PN02 (120 AC Class Instrument Channel "B")

K&A: Ability to (a) predict the impacts of the following malfunctions or operations on the NIS; and (b based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Nuclear Instrumentation System (NIS)

Justification:

A is Wrong - Control channel 2 is fed by NNN-D12 not PNB-D12, may believe the make before break feature could cause a momentary WD demand OPTRNG_EXAM Page: 31 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam B is Wrong - bus would shift to VR in Units 2 & 3, this feature is not available in Unit-1 C is Correct - Power is lost in Unit 1 and can be restored by shifting to the VR D is Wrong - Control channel 2 is fed NNN-D12 not PNB-D12 OPTRNG_EXAM Page: 32 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 17 This Exam Level SRO Apears on:

K/A # 2.1.20 Importance Rating:

Given the following conditions:

Unit 1 is operating at 100% power

40AO-9ZZ02, Excessive RCS Leakrate was entered at 10:30

A SG tube leak has been confirmed

A 15 minute manual leakrate has been performed with the following results Initial (1130) Final (1145) Conversions PRZ level 51% 52% 66.49 gal/%

VCT level 36% 35% 40.5 gal/%

RCS Tave 571.0°F 570.8°F 123 gal/°F Assuming a stable leakrate, interpret the data to determine the required action(s) per appendix F of 40AO-9ZZ02 A. Commence an orderly plant shutdown B. Commence a plant shutdown and be in Mode 3 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C. Commence prompt and controlled shutdown to 50% power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in Mode 3 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months D. Commence shutdown and be in mode 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Answer: B Associated KA:

L56818 Given plant conditions related to a Steam Generator Tube leak and Appendix F of 40AO-9ZZ02 analyze these conditions to determine if continued operation is permitted Reference Id: Q10486 Difficulty: 3.00 Time to complete: 4 10CFR Category: CFR 55.43 (5) 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: Appendix F of 40AO-9ZZ02 Technical

Reference:

40AO-9ZZ02, Excessive RCS leakrate OPTRNG_EXAM Page: 33 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam K&A: Conduct of Operations: Ability to execute procedure steps.

Justification:

A is Wrong -

B is Correct - Leakrate is .092 gpm requiring plant shutdown and mode 3 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C is Wrong - Stable leak rate is given in stem -- Leakrate is not changing > .0208 gpm / hr D is Wrong -

OPTRNG_EXAM Page: 34 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 18 This Exam Level SRO Apears on:

K/A # 34041A2.02 Importance Rating:

Given the following conditions:

Unit 1 is stable at rated power

Steam Bypass Control Valve (SBCV) testing is in progress

Main Turbine load has been lowered approximately 11%

SBCS Master Controller SGN-PIC-1010 is in Local Auto

CEDMCS is in manual sequential

Reg Group 5 is 120 inches withdrawn

SBCV #1 is 40% open with a manual permissive

SBCV #4 is 40% open with a manual permissive

SBCV #6 fails full open

Tavg-Tref Hi-Lo window is in alarm (4A08B)

COLSS CMC (5B01C) & PC (5B01D) windows are in alarm

AWP, Auto Withdraw Prohibit (4A09A) alarm has cleared

CEA withdraw demand (green lights) are present on Board 5 SBCVs 1001 & 1004 will ...

A. modulate closed, withdraw CEAs to clear the Tavg - Tref alarm window B. modulate closed, reduce turbine load to clear the COLSS Master alarm window C. only close on loss of permissive signal, withdraw CEAs to clear the Tavg - Tref alarm window D. only close on loss of permissive signal, reduce turbine load to clear the COLSS Master alarm window Answer: B Associated KA:

L65679 Describe the Control Room controls associated with the indivdual SBCS valves including:

Emergency Off Reset

Valve Mode Select Reference Id: Q10487 Difficulty: 3.00 Time to complete: 3 10CFR Category: CFR 55.43 (5) 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:

40AL-9RK5B 40AL-9RK4A, ARPs OPTRNG_EXAM Page: 35 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam K&A: Ability to (a) predict the impacts of the following malfunctions or operations on the SDS; and (b) based on those predictions or mitigate the consequences of those malfunctions or operations: Steam valve stuck open Justification:

A is Wrong - Tavg/Tref is a low alarm due to 1006 coming open. CEA wd demand would be expected for turbine power > reactor power. AWP clears when modulate and permissive SBCS signals go away B is Correct - 1001/1004 will modulate closed. manual permissive and Local/Auto will not effect valve operation. COLSS alarms need to be cleared.

C is Wrong - SBCVx 1001 & 1004 will both modulate close as 1006 comes open D is Wrong - SBCVx 1001 & 1004 will both modulate close as 1006 comes open OPTRNG_EXAM Page: 36 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 19 This Exam Level SRO Apears on:

K/A # 2.1.7 Importance Rating:

Given the following Unit 1 conditions:

The Main Turbine tripped 60 minutes ago

Rx power was stabilized at 55%

Tave was stabilized at 576 ºF NOW

Pzr level is on program

Letdown flow is 72 gpm and lowering

Rx power is slowly dropping

Tave is slowly dropping

CEDMCS has a withdraw demand Which one of the following is the most likely event in progress?

A. A small RCS leak, implement 40AO-9ZZ02, Excessive RCS Leakage.

B. A small steam leak. Trip the Reactor and implement 40EP-9EO06, Excess Steam Demand.

C. Thot instrument RCN-TT-111X is failing low, implement 40AO-9ZZ16, RRS Malfunctions.

D. Normal xenon response following a Large Load Reject. Direct a dilution per 40OP-9CH01.

Answer: D Associated KA:

L569445 Given a TLI instrument failing low describe the impact this would have on various control systems that rely on this indication Reference Id: Q10481 Difficulty: 4.00 Time to complete: 3 10CFR Category: CFR 55.43 (5) 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-9ZZ16, RRS Malfunctions K&A: Conduct of Operations: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

OPTRNG_EXAM Page: 37 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam Justification:

A is Wrong - RCS leakage will not cause changes in anything other than Letdown flow decreasing B is Wrong - Steam leak will cause power increase and temperature decrease C is Wrong - Thot failing low causes Letdown flow to increase but not all the other changes D is Correct - Xenon will build in after trip causing power drop, temperature drop, WD demand and Letdown decrease trying to maintain Pzr level with decreasing RCS temp OPTRNG_EXAM Page: 38 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 20 This Exam Level SRO Apears on:

K/A # 2.1.37 Importance Rating:

Given the following conditions:

Unit 1 is planning a 15% downpower

The crew is about to start the Reactivity Brief Which one of the following statement is correct regarding the Reactivity Management guidance found in Operations Department Practices (ODP-01)?

A. The Shift Technical Advisor (STA) must attend the reactivity brief B. A Maneuvering Box gameplan must be used for this planned power reduction C. A peer check is required prior to each reactivity evolution performed during the downpower D. An additional reactivity brief is required for each turbine manipulation performed during the downpower Answer: C Associated KA:

30265 ODP-1 Reactivity Management Reference Id: Q10490 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:

ODP-01 K&A: Conduct of Operations: Knowledge of procedures, guidelines or limitations associated with Reactivity Management Justification:

A is Wrong - STA is required if available B is Wrong - Manv. Box should be used if it fits the situation C is Correct - CRS ensures the performance of peer checks for all reactivity evolutions D is Wrong - additional briefs are not required for each step of multiple manipulations within a specified reactivity evolution OPTRNG_EXAM Page: 39 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 21 This Exam Level SRO Apears on:

K/A # 2.2.37 Importance Rating:

Given the following conditions:

Unit 1 is operating at rated power

DG "A" is under clearance and OOS for planned maintenance

A low level alarm is received on the "B" Essential Chill water surge tank

Area 3 reports a leak on the HPSI pump room "B" Essential ACU, HAB-Z01

Chill Water (EC) is isolated to HAB-Z01 Which one of the following correctly reflects HPSI pump status?

A. HPSI pumps A/B are both Inoperable but functional B. HPSI pumps A/B are both Inoperable and non-functional C. HPSI pump A is Operable and functional provided offsite power is available to PBA-S03 D. HPSI pump B is Operable and functional provided room temperature is maintained < 104 ºF Answer: A Associated KA:

L89782 Given a set of plant conditions apply the one hour or less actions statements of T.S. 3.5 Reference Id: Q10482 Difficulty: 5.00 Time to complete: 4 10CFR Category: CFR 55.43 (2) 55.43 (2)Facility operating limitations in the technical specifications and their bases.

Cognitive Level: Memory Question Source: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

Tech Specs K&A: Ability to determine operability and/or availability of safety related equipment.

Justification:

A is Correct - Both HPSI are Inop per definition but both are also functional to use if needed B is Wrong - see above C is Wrong - Operable means emergency source of power is available D is Wrong - Operable requires attendant equipment available including room coolers OPTRNG_EXAM Page: 40 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 22 This Exam Level SRO Apears on:

K/A # 2.2.39 Importance Rating:

Given the following conditions:

Unit 1 is operating at rated power.

Diesel Generator "A" monthly Surveillance Testing is in progress.

Diesel Generator "A" trips during the cooldown cycle.

Diesel Generator "A" is declared Inoperable.

Which one of the following Tech Spec actions must be completed within one hour?

A. Restore DG "A" to Operable status.

B. Determine that DG "B" is not Inoperable due to a common cause failure.

C. Verify correct breaker alignment and indicated power availability for two offsite power circuits.

D. Declare required feature(s) supported by the Inoperable DG Inoperable when its redundant required feature(s) is inoperable.

Answer: C Associated KA:

L89756 Given a set of plant conditions apply the one hour or less actions statements of T.S. 3.8 100866 Active Question Bank 2004 Reference Id: Q8585 Difficulty: 2.00 Time to complete: 2 10CFR Category: CFR 55.43 (2) 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:

Tech Specs LCO 3.8.1 K&A: Knowledge of less than or equal to one hour Technical Specification action statements for systems.

Justification:

A is Wrong - This is a 10 day action per 3.8.1 B is Wrong - This is a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months actions C is Correct - 40ST-9ZZ02 must be completed within one hour and every 8 there after D is Wrong - 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months requirement with concurrent inoperability of redundant equip OPTRNG_EXAM Page: 41 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 42 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 23 This Exam Level SRO Apears on:

K/A # 2.3.4 Importance Rating:

Given the following conditions:

A General Emergency has been declared

Satellite Technical Support Center (STSC) has been activated

Operations Support Center (OSC) has been activated

It has been determined that in order to stabilize the plant repair activities are required to be performed in a high dose area Who can authorize a "Protecting Valuable Property" exposure and what is the Dose limit?

A. Emergency Coordinator ONLY, 25 Rem TEDE B. Emergency Coordinator ONLY, 10 Rem TEDE C. Emergency Coordinator or Radiation Protection Monitor, 10 Rem TEDE D. Emergency Coordinator or Radiation Protection Monitor, 25 Rem TEDE Answer: B Associated KA:

30226 exposure limits Reference Id: Q10491 Difficulty: 2.00 Time to complete: 3 10CFR Category: CFR 55.43 (4) 55.43 (4) Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions.

Cognitive Level: Memory Question Source: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

EPIP-99 Appendix K K&A: Radiation Control Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

Justification:

A is Wrong -

B is Correct - Per EPIP-99 appendix K, only the EC is authorized to allow any exposures >

5 REM TEDE for protecting valuable equipment or life saving activities C is Wrong -

D is Wrong -

OPTRNG_EXAM Page: 43 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 44 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 24 This Exam Level SRO Apears on:

K/A # 2.3.14 Importance Rating:

Given the following conditions:

Unit 1 is in Mode 5

RCS pressure is 200 psia

RCS temperature is 190ºF and stable

LPSI pump "A" is providing Shutdown Cooling (SDC) flow at 4100 gpm

Per the Outage schedule. SDC is to be swapped to Containment Spray pump "B" This activity will cause which one of the following conditions?

A. CS pump "B" seal pressure limits to be exceeded B. CS pump "B" seal temperature limits to be exceeded C. require entry in to LCO 3.6.6, Containment Spray System.

D. unknown radiation levels in "B" Containment Spray system Answer: D Associated KA:

L65102 Describe the purpose and conditions under which the Shut Down Cooling System is designed to function.

Reference Id: Q10489 Difficulty: 3.00 Time to complete: 2 10CFR Category: CFR 55.43 (4) 55.43 (4) Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions.

Cognitive Level: Memory Question Source: New Comment:

Proposed reference to be provided to applicant during examination: None Technical

Reference:

40OP-9SI01, Shutdown Cooling Initiation - Tech Specs, LCO 3.6.6 K&A: Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

Justification:

A is Wrong - seal pressure limit is 250 psia B is Wrong - seal temperature limit is 200 ºF C is Wrong - LCO 3.6.6 applies 1-4 D is Correct - rad levels are expected to increase significantly when initiating or swapping SDC trains. Limitations and Precautions OPTRNG_EXAM Page: 45 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam OPTRNG_EXAM Page: 46 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam 25 This Exam Level SRO Apears on:

K/A # 2.4.8 Importance Rating:

Given the following conditions:

Unit 1 is operating at 100% power

RU-6 (Nuclear Cooling Water) is in high alarm

The Crew is performing actions per the Excessive RCS Leakrate, 40AO-9ZZ02

Alarm window 4A02A (RCP 1A TRBL) is alarming

All available Charging Pumps are running

Letdown is isolated

PZR level is continuing to lower The CRS is expected to ....

A. trip the Reactor and continue performance of 40AO-9ZZ02 during SPTAs.

B. exit 40AO-9ZZ02 and initiate performance of 40AO-9ZZ04, RCP Motor Emergencies.

C. continue 40AO-9ZZ02. If Nuclear Cooling Water is isolated for 10 minutes then trip the Reactor.

D. trip the Reactor and perform SPTAs. AOP performance is not allowed until Safety Function assessment is complete.

Answer: A Associated KA:

L10343 Given that an ORP is being implemented describe the use of an AO or OP when the reactor trips or when performing an EOP Reference Id: Q10478 Difficulty: 2.00 Time to complete: 2 10CFR Category: CFR 55.43 (5) 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-9ZZ02 (Excessive RCS Leakrate), 40DP-9AP16 (EOP Users Guide)

K&A: Knowledge of how abnormal operating procedures are used in conjunction with l EOPs.

Justification:

OPTRNG_EXAM Page: 47 of 48 07/15/08

ES-401 Sample Written Examination Form ES 401 - 5 Question Worksheet 2008 Senior Reactor Operator Exam A is Correct - reactor trip criteria is met (ZZ02)and actions to isolate the seal cooler need to continue per ZZ02. EOP user guide allows performance of non EOP activities to for equipment protection safety and placing plant systems in a safe condition B is Wrong - the RCP trbl alarm requires performance of RCP Motor Emergencies, but not required to exit the current AOP also we still need to trip the reactor now C is Wrong - reactor needs to be tripped now not in 10 minutes if seal cooler is isolated D is Wrong - SEE A above Cognitive Level Summary Number of questions linked: 25 Percentage Memory 10 10 Comprehension 0 0 Analysis 0 0 Question Source Summary Number of questions linked to source: 25 Percentage New New 20 20 Modified INPO Bank Modified 0 PV Bank Modified 3 Total Modified 3 3 Bank INPO Bank Not Modified 0 PV Bank Not Modified 2 PV NRC Exam Question Not Modified 0 Total BANK 2 2 OPTRNG_EXAM Page: 48 of 48 07/15/08

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