ML023570388

CP - Init Exam -11/2002 - Draft Exam

ML023570388
Person / Time
Site:	Comanche Peak
Issue date:	01/04/2002
From:	Gody A NRC Region 4
To:	Terry C TXU Electric
References
50-445/02-301, 50-446/02-301, NUREG-1021 50-445/02-301, 50-446/02-301
Download: ML023570388 (383)

Text

ROA1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: A.1-1: Conduct of Operations JTA Task #: CPSES BANK: RO1803 Task

Title:

Perform QPTR Calculation KSA Ref: 2.1.20 Executing Procedures PEO: RO: 3.9 SRO: 4.0 Operator=s Name:

Performance Environment: ADMIN CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

References:

Tools, Equipment, Job Aids, etc:

OPT-302 Calculator Static Simulator OPT-302-1 Instructor Copy OPT-302-1 Working Copy Page 1 of 4 Rev Date: 01/24/99

ROA1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure TDM-101A-2 Working Copy Page 2 of 4 Rev Date: 01/24/99

ROA1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

The Unit Supervisor assigns you to manually perform OPT-302, Calculating Power Tilt Ratio.

Terminating Conditions:

OPT-302 is ready for Shift Manager review and signature.

Page 3 of 4 Rev Date: 01/24/99

ROA1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT

• 1 Operator locates all required Forms OPT-302-1 and TDM data forms to perform OPT. TDM101A-2 located. located in TDM Forms not TDM-101-A.

• 2 Operator competes the QPTR QPTR calculation within in OPT-302. tolerance listed on the Examiner Data Sheet and CUE: all Acceptance Criteria U L satisfied.

N41B 192.0 193.0 N42B 254.0 220.0 N43B 213.0 209.0 N44B 214.0 209.0 TASK COMPLETE Page 4 of 4 Rev Date: 01/24/99

ROA1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: The Unit Supervisor assigns you to manually perform OPT-302, Calculating Power Tilt Ratio.

Page 5 of 4 Rev Date: 01/24/99

SROA1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: A.1-1: Conduct of Operations JTA Task #: CPSES BANK: RO1010 Task

Title:

Perform Shutdown Margin Calculations KSA Ref: 2.1.23 Integrated Plant Procedures RO: 3.9 SRO: 4.0 Operator=s Name:

Performance Environment: ADMIN CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

References:

Tools, Equipment, Job Aids, etc:

OPT-301, AReactor Shutdown Margin OPT-301 Verification@ OPT-301-9 Technical Specifications SOR Startup and Operation Report COLR Page 1 of 5 Rev Date: 04/26/99

SROA1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Core Operating Limits Report Page 2 of 5 Rev Date: 04/26/99

SROA1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

The unit tripped from 100% power, equilibrium conditions 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ago. All rods are fully inserted, RCS Tave is 375°F, and the boron concentration is 1250 ppm from a sample taken 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the trip. Core burnup is 8000 MWD/MTU. The computer program is unavailable and you are to perform a manual Shutdown Margin Verification per OPT-301, A Reactor Shutdown Margin Verification@.

Terminating Conditions:

Shutdown Margin Verification has been completed per OPT-301 and OPT-301-9 filled out correctly.

Page 3 of 5 Rev Date: 04/26/99

SROA1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1 Obtains OPT-301 and a OPT-301 open for working copy of form OPT- reference 301-9 2 Completes top portion of OPT- Unit NO.; Cycle No:

301-9 use current cycle; Mode: 3; Current date and time.

3 Enters the RCS boron Enters 1250 ppm on concentration on line A.1 and line A.1 sample time.

4 Enters RCS Tave on line A.2 Enters 375°F on line A.2 5 Enters core burnup on line A.3 Enters 8000 and check and checks the appropriate box. MOL box.

6 Enters number of stuck RCCAs Enters 0 on line A.4 for on line A.4. no stuck RCCAs.

7 Refers to COLR and Enters 1300 on line Candidate may determines SDM reactivity A.5. know from requirement for present memory the MODE. Enters value in line requirement of A.5. 1.3%_K/K which is 1300 pcm.

8 Determines the uncorrected Refers to SOR table minimum boron concentration 5.13 and enters correct from SOR table 5.13 and enters value on line B.1.

on line B.1.

• 9 Determines A.1 _ B.1 and A.1 _ B.1. Must take credit must be taken for Xe and credit for Xe and Sm by Sm. performing section 8.1.4 and 8.1.5.

10 Enters data for C.1 and C.2. Data given in initiating cue.

11 Determine Xe worth using Enters value from SOR SOR, table 5.21 and enters on table 5.21 on line C.3.

line C.3 and checks box to indicate from SOR.

Page 4 of 5 Rev Date: 04/26/99

SROA1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure 12 Determines Sm worth using Enters value from SOR SOR, table 5.24 and enters on table 5.24 on line C.4.

line C.4 and checks box to indicate from SOR.

13 Determines the IBW using table Enters IBW from table 5.8 from SOR and enters value 5.8 of SOR on line D.1 on line D.1.

14 Determines value for most Enters value of most reactive RCCA from table 5.16 reactive RCCA from of SOR and enters value on table 5.16 of SOR and line D.2. enters on line D.2.

15 Performs calculation of OPT- Performs calculation of 301-9, line D.3 to determine OPT-301-9, line D.3, worth correction and enters using 0 for RCCAs and value on line D.3. enters value on line D.3.

16 Determines boron correction Enters value for boron factor from Figure 5.36 of SOR correction factor from and enters on line D.4. Figure 5.36 of SOR on line D.4.

17 Performs calculation of OPT- Performs calculation of 301-9, line D.5, to determine line D.5 to determine the IBW for minimum SDM and IBW for minimum SDM enters results on line D.5. and enters on line D.5

• 18 Determine if SDM Verifies boron requirements are met and concentration entered completes line F.1. on line A.1 _ line D.6 and circles YES on line F.1.

TASK COMPLETE Page 5 of 5 Rev Date: 04/26/99

SROA1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE:

The unit tripped from 100% power, equilibrium conditions 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ago. All rods are fully inserted, RCS Tave is 375°F and the boron concentration is 1250 ppm from a sample taken 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the trip. Core burnup is 8000 MWD/ MTU. The computer program is unavailable and you are to perform a manual Shutdown Margin Verification per OPT-301, A Reactor Shutdown Margin Verification@.

Page 6 of 5 Rev Date: 04/26/99

ROA2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: A.1-2: Conduct of Operations JTA Task #: ROA2 (NEW)

Task

Title:

Perform an RCS Inventory Balance KSA Ref: 2.1.23 Integrated Plant Procedures PEO: RO: 2.8 SRO: 3.1 Operator=s Name:

Performance Environment: ADMIN CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

References:

Tools, Equipment, Job Aids, etc:

OPT-303 Calculator Static Simulator OPT-303-1 (with initial and final data pre-recorded)

Page 1 of 4 Rev Date: 01/24/99

ROA2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

The Unit Supervisor assigns you to manually perform OPT-303, RCS Water Inventory calculation.

The data have already been collected over the previous two hours.

Terminating Conditions:

OPT-303 is ready for Shift Manager review and signature.

Page 2 of 4 Rev Date: 01/24/99

ROA2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT

• 1 Operator locates all required Form OPT-303-1.

forms to perform OPT.

• 2 Operator completes the calculations.

TASK COMPLETE Page 3 of 4 Rev Date: 01/24/99

ROA2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: The Unit Supervisor assigns you to manually perform OPT-303, RCS Water Inventory calculation. The data have already been collected over the previous two hours.

Page 4 of 4 Rev Date: 01/24/99

SROA2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: A.1-2: Conduct of Operations JTA Task #: CPSES BANK: RO1804A Task

Title:

Perform Calorimetric Heat Balance Data Collection KSA Ref: 2.1.25 Obtain/Interp. Performance Data PEO: RO: 2.8 SRO: 3.1 Operator=s Name:

Performance Environment: ADMIN CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

Page 1 of 5 Rev Date: 01/05/00

SROA2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure

References:

Tools, Equipment, Job Aids, etc:

OPT-309, AUnit Calorimetric@, step 8.2 OPT-309, (Working Copy)

Calculator Page 2 of 5 Rev Date: 01/05/00

SROA2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

You have been directed to collect and record the data, on Unit 1, for a Unit Calorimetric, in accordance with OPT-309, step 8.2.1. The plant computer and the Leading Edge Flowmeter are unavailable for use. All prerequisites have been completed and steam generator blowdown is in service.

Terminating Conditions:

OPT-309, Form 11 is completed with one set of data.

Page 3 of 5 Rev Date: 01/05/00

SROA2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1 Enter the CPSES Unit number Unit 1, entered in the for which this test is being >Parameter= block of performed. form OPT-309-1.

• 2 Obtain the feedwater flow data Same as step using:

and enter the results in the FI-510A appropriate boxes of section C. FI-511A FI-520A CUE: Each indicator is 3.7 to FI-521A 3.8 FI-530A FI-531A FI-540A FI-541A

• 3 Obtain the feedwater Same as step using temperature for each steam instruments:

generator and enter the results TI-2177A in the appropriate column of TI-2178A section D. TI-2179A TI-2180A CUE: Each indicator is 438 to 440.

• 4 Obtain the feedwater pressure Same as step using for each steam generator and instruments:

enter results in appropriate PI-2138 column of Section E. PI-2139 CUE: Each indicator is _____ PI-2140 PI-2141

• 5 Obtain the steamline pressures Same as step using for each steam generator and instruments:

enter the results in the PI-514A appropriate column of section PI-515A F. PI-516A PI-524A CUE: Each indicator is 1000 PI-525A to 1010. PI-526A PI-534A PI-535A Page 4 of 5 Rev Date: 01/05/00

SROA2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure PI-536A PI-544A PI-545API-546A

• 6 Obtain the total steam generator Same as step using blowdown flow and instrument:

temperature and enter the result FI-5219A in the appropriate column of FI-5182A section G.

CUE: The indicator is 150 to 155 psig and 140°F.

• 7 Obtain the percent of rated Same as step using NIS thermal output from the power Instruments:

range NIS and enter the results N-41A in the appropriate column of N-42A section H. N-43A N-44A CUE: Each instrument is indicating 99.5 to 100.

8 Obtain the percent of Rated JI-411A Thermal Power for the N-16 JI-421A Power channels in the JI-431A appropriate column of Section JI-441A 1.

CUE: Each indicator is _____

9 Repeat the above steps to Same as step.

obtain a total of three data sets.

CUE: Continue with the procedure using only one set of data points.

10 Enter signature, the time data Same as step.

collection was completed and the date on which the data was collected into the appropriate spaces located at the bottom of Form OPT-309-11.

TASK COMPLETE Page 5 of 5 Rev Date: 01/05/00

SROA2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: You have been directed to collect and record the data, on Unit 1, for a Unit Calorimetric, in accordance with OPT-309, step 8.2.1. The plant computer and the Leading Edge Flowmeter are unavailable for use. All prerequisites have been completed and steam generator blowdown is in service.

Page 6 of 5 Rev Date: 01/05/00

ROA3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: A.2: Equipment Control JTA Task #: ROA3 (NEW)

Task

Title:

Identify Errors in a Faulted Clearance (Tagout)

KSA Ref: 2.2.13 Tagging and Clearance Proc. PEO: RO: 3.6 SRO: 3.8 Operator=s Name:

Performance Environment: ADMIN CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

References:

Tools, Equipment, Job Aids, etc:

STA-605, AClearance and Safety Tagging,@

Revision 14 OWI-110, AOperations Department Work Control and Clearance Guideline,@ Revision 11 Page 1 of 4 Rev Date: 01/24/99

ROA3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Dwg M1-206, Sheet 1 Page 2 of 4 Rev Date: 01/24/99

ROA3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

The clearance was prepared by an Atrainee@ and you have been asked by the Work Control Supervisor to review the prepared clearance as a qualified clearance preparer. Identify the three substantive errors associated with the clearance boundaries.

Terminating Conditions:

Finishes review of the clearance.

Page 3 of 4 Rev Date: 01/24/99

ROA3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1 Provide candidate with Candidate should review completed copy of Admin JPM and initiating the initiating cue cue 2* Identifies 3 errors Candidate identifies the Errors can be following 3 errors: found in ANY order.

1. IAF-0070 (AFW pump discharge to CST) is 3 of 3 errors REQUIRED to be tagged - must be not tagged identified for

2. Service Water Suction the JPM to be Supply Valve - tag number sat.

incorrect: Tag is for IAF-0018, but should be for IAF-0019

3. 1AF-0067-RO is NOT isolated (part of Aminimum@

clearance boundary)

TASK COMPLETE Page 4 of 4 Rev Date: 01/24/99

ROA3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: The clearance was prepared by an Atrainee@ and you have been asked by the Work Control Supervisor to review the prepared clearance as a qualified clearance preparer. Identify the three substantive errors associated with the clearance boundaries.

Page 5 of 4 Rev Date: 01/24/99

SROA3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: A.2: Equipment Control JTA Task #: SROA3 (NEW)

Task

Title:

Determine the End Time for an LCO KSA Ref: 2.2.23 Ability to Track LCO=s PEO: RO: 2.6 SRO: 3.8 Operator=s Name:

Performance Environment: ADMIN CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

Page 1 of 4 Rev Date: 01/05/00

SROA3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure

References:

Tools, Equipment, Job Aids, etc:

Technical Specifications Technical Specifications Page 2 of 4 Rev Date: 01/05/00

SROA3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

You are the Control Room Supervisor, the plant is stable in Mode 1.

--The AA@ train SI pump has been declared inoperable. The time of discovery is 1000 on 12/08/2001. The AB@ train SI is OPERABLE.

--Twelve (12) hours after the AA@ train SI is declared inoperable, the AB@ train RHR pump is declared inoperable.

--At 1000 on 12/09/2001, the AA@ train SI pump is restored to OPERABLE status.

When must the AB@ train RHR pump be restored to OPERABLE status to avoid commencing a unit shutdown, including any extensions permitted by Technical Specifications?

Terminating Conditions:

Upon Completion of this JPM, the operator will have determined that the extensions allowed by section 1.3, ACompletion Times@, would apply and that LCO 3.5.2 must be exited by 2200 on 12/11/2001.

Page 3 of 4 Rev Date: 01/05/00

SROA3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1 AA@ train SI pump declared Action A. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to inoperable1000 on 12/08/2001. restore. 100% capacity of The AB@ train SI is OPERABLE. ECCS is still available.

Enter LCO 3.5.2. Restore by 1000 12/11/2001.

• 2 AB@ train RHR pump is declared Still in LCO 3.5.2, Action A.

inoperable2200 12/08/2001. 100% capacity of ECCS is still available.

Restoration still 1000 12/11/2001.

• 3 At 1000 on 12/09/2001, the AA@ train SI Since the first component pump is restored to OPERABLE status. causing entry into LCO 3.5.2 was restored first, an extension to the completion time of 3.5.2 can be applied. Per Section 1.3, Extension is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the origional end of the time limit of the second component, whichever is less. Completion time would be extended 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to 2200 12/11/2001.

TASK COMPLETE INITIATING CUE: You are the Control Room Supervisor, the plant is stable in Mode 1.

--The AA@ train SI pump has been declared inoperable. The time of discovery is 1000 on 12/08/2001. The AB@

train SI is OPERABLE.

Page 4 of 4 Rev Date: 01/05/00

SROA3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure

--Twelve (12) hours after the AA@ train SI is declared inoperable, the AB@ train RHR pump is declared inoperable.

--At 1000 on 12/09/2001, the AA@ train SI pump is restored to OPERABLE status.

When must the AB@ train RHR pump be restored to OPERABLE status to avoid commencing a unit shutdown, including any extensions permitted by Technical Specifications?

Page 5 of 4 Rev Date: 01/05/00

ROA4 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: A.3: Radiation Control JTA Task #: ROA4 (NEW)

Task

Title:

Interpret a Faulted Survey Map to Determine Entry Requirements KSA Ref: 2.3.10 Guard Against Pers. Exposure PEO: RO: 2.9 SRO: 3.3 Operator=s Name:

Performance Environment: ADMIN CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

Page 1 of 4 Rev Date: 01/05/00

ROA4 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure

References:

Tools, Equipment, Job Aids, etc:

RPI-602 Faulted Survey Map Page 2 of 4 Rev Date: 01/05/00

ROA4 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

Based on the survey map provided, determine the requirements to enter the are.

Terminating Conditions:

Page 3 of 4 Rev Date: 01/05/00

ROA4 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1

2 3

TASK COMPLETE Page 4 of 4 Rev Date: 01/05/00

ROA4 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: Based on the survey map provided, determine the requirements to enter the are.

Page 5 of 4 Rev Date: 01/05/00

SROA4 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: A.3: Radiation Control JTA Task #: SROA4 (NEW)

Task

Title:

Interpret a Faulted Survey Map to Determine Entry Requirements KSA Ref: 2.3.10 Guard Against Pers. Exposure PEO: RO: 2.9 SRO: 3.3 Operator=s Name:

Performance Environment: ADMIN CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

Page 1 of 4 Rev Date: 01/05/00

SROA4 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure

References:

Tools, Equipment, Job Aids, etc:

RPI-602 Faulted Survey Map Page 2 of 4 Rev Date: 01/05/00

SROA4 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

Based on the survey map provided, determine the requirements to enter the are.

Terminating Conditions:

Page 3 of 4 Rev Date: 01/05/00

SROA4 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1

2 3

TASK COMPLETE Page 4 of 4 Rev Date: 01/05/00

SROA4 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: Based on the survey map provided, determine the requirements to enter the are.

Page 5 of 4 Rev Date: 01/05/00

SROA5.1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: A.4: Emergency Plan JTA Task #: SROA5.1 (MOD)

Task

Title:

Event Classification KSA Ref: 2.4.41 EAL Classifications PEO: RO: 2.3 SRO: 4.1 Operator=s Name:

Performance Environment: ADMIN CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

Page 1 of 4 Rev Date: 01/05/00

SROA5.1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure

References:

Tools, Equipment, Job Aids, etc:

Procedure EPP-201, AAssessment of Emergency Static simulator - following Scenario Run Day 1 (the Action Levels, Emergency Classification and scenario is actually Scenario 1)

Plan Activation@

Page 2 of 4 Rev Date: 01/05/00

SROA5.1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

THIS NEEDS TO BE COMPLETED IN CONJUNCTION WITH SCENARIO 1. Scenario 1 should be run on Day 1 of simulator runs. Do this JPM after the scenario is completed with the simulator in Afreeze.@

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

The simulator is in freeze. Based upon the current plant conditions and events during the scenario, determine the emergency classification and make applicable Protective Action Recommendations.

Terminating Conditions:

Event is classified as an ALERT Page 3 of 4 Rev Date: 01/05/00

SROA5.1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1 Provide candidate with Candidate should completed copy of review Admin JPM and the initiating cue initiating cue 2 Candidate determines Candidate determines Candidate should emergency classification for that the classification evaluate both Loss of Offsite Power for Loss of Offsite events and then Power would be a based on the NOUE (EPP-201) individual classifications determine the Aoverall@

classification 3 Candidate determines Candidate determines emergency classification for that loss of electrical loss of electrical power power would be classified as an:

ALERT 4* Candidate determines the Candidate determines overall classification that the overall classification would be:

ALERT TASK COMPLETE Page 4 of 4 Rev Date: 01/05/00

SROA5.1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: The simulator is in freeze. Based upon the current plant conditions and events during the scenario, determine the emergency classification and make applicable Protective Action Recommendations.

Page 5 of 4 Rev Date: 01/05/00

SROA5.2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: A.4: Emergency Plan JTA Task #: SROA5.2 (MOD)

Task

Title:

Event Classification KSA Ref: 2.4.41 EAL Classifications PEO: RO: 2.3 SRO: 4.1 Operator=s Name:

Performance Environment: ADMIN CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

Page 1 of 4 Rev Date: 01/05/00

SROA5.2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure

References:

Tools, Equipment, Job Aids, etc:

Procedure EPP-201, AAssessment of Emergency Static simulator - following Scenario 2 Action Levels, Emergency Classification and Plan Activation@

Page 2 of 4 Rev Date: 01/05/00

SROA5.2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

THIS NEEDS TO BE COMPLETED IN CONJUNCTION WITH SCENARIO 2. Scenario 2 should be run on Day 2 of simulator runs. Do this JPM after the scenario is completed with the simulator in Afreeze.@

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

The simulator is in freeze. Based upon the current plant conditions and events during the scenario, determine the emergency classification and make applicable Protective Action Recommendations.

Terminating Conditions:

Event is classified as a SITE AREA EMERGENCY Page 3 of 4 Rev Date: 01/05/00

SROA5.2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1 Provide candidate with Candidate should completed copy of review Admin JPM and the initiating cue initiating cue 2 Candidate determines Candidate determines Candidate should emergency classification for that the classification evaluate both ATWT for ATWT would be a events and then SITE AREA based on the EMERGENCY individual classifications determine the Aoverall@

classification 3 Candidate determines Candidate determines emergency classification for that SGTR would be SGTR classified as an:

ALERT 4* Candidate determines the Candidate determines overall classification that the overall classification would be:

SITE AREA EMERGENCY TASK COMPLETE Page 4 of 4 Rev Date: 01/05/00

SROA5.2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: The simulator is in freeze. Based upon the current plant conditions and events during the scenario, determine the emergency classification and make applicable Protective Action Recommendations.

Page 5 of 4 Rev Date: 01/05/00

SROA5.3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: A.4: Emergency Plan JTA Task #: SROA5.3 (MOD)

Task

Title:

Event Classification KSA Ref: 2.4.41 EAL Classifications PEO: RO: 2.3 SRO: 4.1 Operator=s Name:

Performance Environment: ADMIN CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

Page 1 of 4 Rev Date: 01/05/00

SROA5.3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure

References:

Tools, Equipment, Job Aids, etc:

Procedure EPP-201, AAssessment of Emergency Static simulator - following Scenario 3 Action Levels, Emergency Classification and Plan Activation@

Page 2 of 4 Rev Date: 01/05/00

SROA5.3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

THIS NEEDS TO BE COMPLETED IN CONJUNCTION WITH SCENARIO 3. Scenario 3 should be run on Day 3 of simulator runs. Do this JPM after the scenario is completed with the simulator in Afreeze.@

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

The simulator is in freeze. Based upon the current plant conditions and events during the scenario, determine the emergency classification and make applicable Protective Action Recommendations.

Terminating Conditions:

Event is classified as a SITE AREA EMERGENCY Page 3 of 4 Rev Date: 01/05/00

SROA5.3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1 Provide candidate with Candidate should completed copy of review Admin JPM and the initiating cue initiating cue 2 Candidate determines Candidate determines Candidate should emergency classification for that the classification evaluate both the RCS Leak for the RCS Leak events and then would be a SITE based on the AREA EMERGENCY individual classifications determine the Aoverall@

classification 3 Candidate determines Candidate determines emergency classification for that ATWT would be ATWT classified as an: SITE AREA EMERGENCY 4* Candidate determines the Candidate determines overall classification that the overall classification would be:

SITE AREA EMERGENCY TASK COMPLETE Page 4 of 4 Rev Date: 01/05/00

SROA5.3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: The simulator is in freeze. Based upon the current plant conditions and events during the scenario, determine the emergency classification and make applicable Protective Action Recommendations.

Page 5 of 4 Rev Date: 01/05/00

ROA5 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: A.4: Emergency Plan JTA Task #: ROA5 (NEW)

Task

Title:

Initial EP Notifications to Offsite Agencies (TIME CRITICAL)

KSA Ref: 2.4.39 RO=s EP Responsibilities PEO: RO: 3.3 SRO: 3.1 Operator=s Name:

Performance Environment: ADMIN CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

Page 1 of 4 Rev Date: 01/05/00

ROA5 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure

References:

Tools, Equipment, Job Aids, etc:

Procedure EPP-203, AEP Manual: Notification@ EPP-203-8 ANotification Message Form@ (completed)

Page 2 of 4 Rev Date: 01/05/00

ROA5 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

1) The offsite agencies must be notified within 15 minutes and the NRC within 60 minutes of the EVENT declaration. The time critical portions of this JPM begin when EPP-203-8 is handed to the applicant.

2) The intent of this JPM is for the applicant to make the correct and timely notifications in accordance with EPP-203, EP: Notifications. The intent is NOT to have the applicant read the same forms over and over again. For time considerations acknowledge the notification promptly.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

An ALERT has just been declared in Unit 1. The Notification Message Form (EPP-203-8) has been filled out and approved by the Shift Supervisor. No offsite agencies have been notified of the event at this time.

You are directed to perform ALL OFFSITE notifications associated with the ALERT using the Form provided in accordance with EPP-203. Portions of this JPM are time critical.

Terminating Conditions:

The Applicant notifies State/County officials within 15 minutes, then notifies the NRC within 60 minutes of the event declaration (event declaration time shall been when the EPP-203-8 form is handed to the applicant).

Page 3 of 4 Rev Date: 01/05/00

ROA5 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1 Provide candidate with Candidate should Annotate the time completed copy of review Admin JPM and of Event the initiating cue initiating cue declaration as the time the Candidate receives EPP-203-8.

2* Candidate contacts DPS Waco, TIME CRITICAL Somervell County, and Hood STEP County within 15 minutes of event declaration and reads the information from EPP-203-8.

CUE: All agencies acknowledge the notification.

3 Notify the NRC Resident Not an Offsite Inspector. notification, but is in the EPP-203 at CUE: RI acknowledges. this step.

4* Candidate contacts NRC TIME CRITICAL Incident Response Center STEP within 60 minutes of event declaration and reads the information from EPP-203-8.

CUE: ENS is not functional, so candidate will have to use an alternate means. NRC acknowledges the notification.

TASK COMPLETE Page 4 of 4 Rev Date: 01/05/00

ROA5 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: An ALERT has just been declared in Unit 1. The Notification Message Form (EPP-203-8) has been filled out and approved by the Shift Supervisor. No offsite agencies have been notified of the event at this time.

You are directed to perform ALL OFFSITE notifications associated with the ALERT using the Form provided in accordance with EPP-203. Portions of this JPM are time critical.

Page 5 of 4 Rev Date: 01/05/00

JPMC1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: Loss of IRNI JTA Task #: CPSES BANK: RO1819 Task

Title:

Respond to IR NIS Malfunction (ALTERNATE PATH)

KSA Ref: APE.033.AK3.02 AO: RO: 3.6 _SRO: 3.9 Operator=s Name:

PLANT CONTROL ROOM SIMULATOR PERFORMED SIMULATED DISCUSSED Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

References:

Tools, Equipment, Job Aids, etc:

ABN-702, AIntermediate Range For simulator setup, initialize ~27% power IC, and go to Instrumentation@ RUN. Enter malfunction NI02A @ 1E-3.

7247D05, Sh.3 7247D05, Sh. 4 Page 1 of 5 Rev Date: 5/9/98

JPMC1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to Manipulate any plant components.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

You are the Reactor Operator.

The plant is at ~ 27% power and reducing load for a required outage. The IR NIS channel N35 failed high. Perform the actions required for the failed IR detector, as the shutdown continues.

Tech Spec concerns will be addressed by the Unit Supervisor.

Terminating Conditions:

After P-6 status is verified.

STEP #

• Critical STANDARD NOTES SAT ELEMENT UNSAT Verify Reactor NOT Load decrease in progress, Various indications of 1 tripped. performing plant shutdown. plant power could be used NI, N-16, Power L CUE: Reactor Shutdown in progress. Power level has been on PCS to verify power reduced to 20% as indicated on NI- level Page 2 of 5 Rev Date: 5/9/98

JPMC1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP #

• Critical STANDARD NOTES SAT ELEMENT UNSAT 41/44.

2 Verify Reactor power >P-6 Permissive window PCIP, 2.5, If I&C is contacted, then setpoint (1E-10 amps). SR RX TRIP BLK PERM P-6, inform that the P-6 checked. (should be LIT) NI- interlock will not be CUE: PCIP, 2.5, is LIT. 36 (u N-I-36B or N-36 meter corrected during this

-4 NI-36 reads (~ 1 x 10 at DR drawer) JPM.

amps) > 1-10-10 amps 3 Verify power level greater Checks power level on NI-that P-10 setpoint (10%). 41/44. (Could also check PCIP 1.6 Rx Window Lit CUE: Power level has and/or TSLB=s NC-41M, 42M, been reduced to 15% as 43M, and 44 M lit.

indicated on NI-41/44.

4 Verify Reactor power Load decrease in progress, reduction NOT in progress performing plant shutdown.

or required.

CUE: Reactor Shutdown in progress and required.

• 5 Bypass failed IR channel N35 LEVEL TRIP switch on At NIS rack (cabinet) high flux trip prior to NIS cabinets taken to BYPASS reducing power below P- (prior to reducing power On CB-07

10. below 10% as indicated on the PR NIS). The following are CUE: Switch is in checked:

BYPASS LEVEL TRIP LEVEL TRIP BYPASS light BYPASS light and ALB- on Intermediate Range drawer 6D, 4.1, both LIT. N35.

Annunciator window ALB-6D, CUE: Power level has 4.1, SR.IR TRIP BYP.

been reduced to 4 x 10-11 amps as indicated on NI-36.

SR Channels N-31 & N-32 indicates 3E3 cps.

Page 3 of 5 Rev Date: 5/9/98

JPMC1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP #

• Critical STANDARD NOTES SAT ELEMENT UNSAT 6 Verify P-6 interlock in Permissive window PCIP, 2.5, If I&C is contacted, then required state. SR RX TRIP BLK PERM inform that the P-6 P-6, checked. (should be interlock will not be CUE: PCIP, 2.5, is LIT. DARK) corrected during this NOTE: This step is N/A if JPM.

ran on the Simulator. TASK COMPLETE Page 4 of 5 Rev Date: 5/9/98

JPMC1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE:

You are the Reactor Operator.

The plant is at 27% power and reducing load for a required outage. The IR NIS channel N35 failed high. Perform the required action for the failed IR Detector as the shutdown continues.

Tech Spec concerns will be addressed by the Unit Supervisor.

Page 5 of 5 Rev Date: 5/9/98

JPMC2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: Emergency Core Cooling System JTA Task #: CPSES BANK (MOD): RO1501 Task

Title:

Fill the Accumulators (ALTERNATE PATH)

KSA Ref: SF2.006.A1.13 PEO: RO: 3.5 SRO: 3.7 Operator=s Name:

Performance Environment: PLANT CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated 20 min Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

References:

Tools, Equipment, Job Aids, etc:

SOP-202A(B), ASafety Injection Accumulators Simulator B 100%; use malfunction SI02D to drain accumulator 4 to 45%; remove malfunction and clear Page 1 of 7 Rev Date: 11/02/98

JPMC2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure SOP-201A(B), ASafety Injection System@ associated containment sump alarms; go to FREEZE; after initiating cue, go to run; after termination criteria met, go to freeze.

Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to Manipulate any plant components.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

Accumulator #4 level is 45% and pressure is near the lower limit. The Unit Supervisor has directed you to refill the accumulator to 52%

Terminating Conditions:

Accumulator #4 level has been adjusted to 52% and pressure is between 623 psig and 644 psig.

Page 2 of 7 Rev Date: 11/02/98

JPMC2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1 Verify the RCS cold leg Operator checks RCS Operator should temperature is greater than cold leg temperature use SOP-202A(B) 350°F. indication on CB-05. section 5.4.1 ARaising CUE: All temperatures Accumulator indicate greater than 350°F Level@ and start an SIP per SOP-201A(B), 5.4.1, AStarting an SIP in Recirculation@

2 Verify SIS is in standby. Unit Supervisor informs operator SIS is in CUE: SIS in standby per SOP- standby.

201A(B) Section 5.1.

3 Verify RCS pressure greater Operator checks RCS than 1700 psig. pressure indication on CB-05 CUE: RCS pressure indicates 2235 psig 4 Verify SIP recirculation The following valve flowpath. positions are checked:

CUE: When valve position is u-8806 OPEN checked, each green light DARK, red light LIT. u-8814 A & B OPEN u-8813 OPEN 5 Verify that lube oil level is PEO called to check Operator may use normal, for pump being started. lube oil level for the PCS points listed pump to be started. in SOP-201A(B)

CUE: When PEO is called, to monitor the SIP state: lube oil level is normal. being started.

6 Verify that lube oil cooler SSW return flow is normal for pump being started.

CUE: SSW flow is normal Page 3 of 7 Rev Date: 11/02/98

JPMC2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT

• 7 Start the desired SIP. Handswitch for selected SIP taken to CUE: The SIP red light LIT, START and indication pump disch. press. is normal checked: 1/u-APSI1 or 1/u-APSI2 8 Verify SIP recirculation flow PEO called to read of 38 to 50 gpm. flow on u-FI-968.

CUE: WHEN PEO is called state: u-FI-968 reads 43 gpm.

• 9 Open 1/u-8888, ACCUM FILL Handswitch for 1/u-ISOL VLV. 8888 held in OPEN position and position CUE: Valve 1/u-8888 red light checked .

LIT, green DARK

• 10 Open 1/u-8871, SI TEST HDR Handswitch for 1/u-RET ISOL VLV 8871 held in OPEN position and position CUE: Valve 1/u-8871, red checked.

light LIT, green DARK.

• 11 Open 1/u-8878D, ACCUM 4 Handswitch for 1/u-FILL VLV. 8878D placed in OPEN position and position CUE: Valve 1/u-8878D red checked.

light LIT, green DARK 12 Monitor accumulator 4 level The following meters If done on SIM are checked: operator should CUE: Accumulator 4 levels wait until level is are _ 52%. u-LI-956 ~52% before u-LI-957 continuing.

• 13 Close 1/u-8878D, ACCUM 4 Handswitch for 1/u- Independent FILL VLV. 8878D placed in closed verification is position and position necessary for the CUE: Valve 1/u-8878D green checked. completion of this light LIT, red DARK. When step either now or independent verification is at the completion requested, then inform that it of this procedure.

Page 4 of 7 Rev Date: 11/02/98

JPMC2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT has been done. of this procedure.

14 Ensure that accumulator 4 level The following meters is between 39% - 61% and are checked:

record level.

u-LI-956 CUE: Accumulator 4 level indicates _52%. u-LI-957 15 Close 1/u-8871 and 1/u-8888. The following valves CUE: Both valves indicate are closed:

green light LIT, red DARK. ____1/u-8871

____1/u-8888 16 Stop the SI Pump and place its Pump switched off and handswitch in AUTO. handswitch placed in CUE: SI Pump handswitch in AUTO.

AUTO.

17 Verify 1/1-8821A(B) SIP 1(2) Verify 1/1-8821A(B)

XTIE VLV open. SIP 1(2) XTIE VLV CUE: Valves indicates red open.

light LIT, green DARK.

• 18 Ensure Accumulator #4 Check Accum. 4 pressure is 623-644psig. pressure 623-644 psig:

CUE: 1-PI-966 and 1-PI-967 ____1-PI-966 indicate 655 psig. ____1-PI-967

• 19 Close 1/1-8880, SI/PORV Close 1/1-8880, ACCUM N2 ISOL VLV. SI/PORV ACCUM N2 CUE: Valves indicates green ISOL VLV.

light LIT, red DARK.

20 Cycle 1-HC-943, ACCUM 1-4 Cycle 1-HC-943, VENT CTRL, to vent N2 ACCUM 1-4 VENT header. CTRL, to vent N2 header.

CUE: Valve cycled.

• 21 Open 1/1-8875D, ACCUM 4 Open 1/1-8875D, N2 SPLY/VENT VLV. ACCUM 4 N2 SPLY/VENT VLV.

CUE: Valves indicates red light LIT, green DARK.

Page 5 of 7 Rev Date: 11/02/98

JPMC2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure

• 22 Throttle open 1-HC-943, Throttle open 1-HC-ACCUM 1-4 VENT CTRL and 943, ACCUM 1-4 shut when pressure 623-644 VENT CTRL and shut psig. when pressure 623-644 psig.

CUE: Valve cycled. 1-PI-966 and 1-PI-967 indicate 640 psig. ____1-PI-966

____1-PI-967 TASK COMPLETE Page 6 of 7 Rev Date: 11/02/98

JPMC2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: Accumulator #4 level is 45% and pressure is near the lower limit. The Unit Supervisor has directed you to refill the accumulator to 52%

Page 7 of 7 Rev Date: 11/02/98

JPMC3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: Reactor Protection System JTA Task #: CPSES BANK: RO1601 Task

Title:

Place Failed Pressurizer Pressure Channel in Trip Condition KSA Ref: SF7.012.A4.04 PEO: RO: 3.3 SRO: 3.4 Operator=s Name:

Performance Environment: PLANT CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated 10 Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

Page 1 of 6 Rev Date: 04/26/99

JPMC3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure

References:

Tools, Equipment, Job Aids, etc:

ABN-705, APressurizer Pressure Instrumentation Working copy of ABN-705, Att 2,3,4 Malfunction@

Page 2 of 6 Rev Date: 04/26/99

JPMC3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

A failure low of Pressurizer pressure channel PT-455 has occurred during full power operation.

The alternate channel has been selected for control and recording. You are directed to place the appropriate bistables in the tripped condition and verify the appropriate alarms and trip status lights.

Terminating Conditions:

The appropriate bistables have been placed in the tripped condition and verified utilizing the appropriate annunciator alarms and trip status lights.

Page 3 of 6 Rev Date: 04/26/99

JPMC3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1 Locate the appropriate bistable Protection set 1, card test switches. frame 8.

• 2 Place SW-1 on Card 72 in the SW-1 is on card 72; 1st CLOSED position. row and 7th column from right of frame 8.

CUE: SW-1 is in the CLOSED Simulated placed in the (UP) position. CLOSED (UP) position.

• 3 Ensure BS-1 and BS-2 on card Top 2 bistable switches 21 in the NORM position. on card 21 (1st row and 6th column from right of CUE: The bistable switches frame 8) checked in the are in the NORM (UP) NORM (UP) position.

position.

• 4 Ensure BS-1, BS-2, BS-3 and All bistable switches BS-4 on card in the NORM on card 22 (top row (UP) position. and 2nd column from right of frame 8)

CUE: The bistable switches checked in the NORM are in the NORM (UP) (UP) position.

position.

• 5 Place SW-5 on card 74 in the The switch is on card CLOSED (UP) position. 74 (2nd row and 7th column from right of frame 8) simulated CUE: The bistable switch is in placed in the CLOSED the CLOSED (UP) position. (UP) position.

6 Ensure BS-1, BS-2, BS-3 and All bistable switches BS-4 on card 46 are in the on card 46 (2nd row and NORM (UP) position. 2nd column from right of frame 8) checked in the CUE: The bistable switches NORM (UP) position.

are in the NORM (UP) position.

Page 4 of 6 Rev Date: 04/26/99

JPMC3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure 7 Verify appropriate annunciator The following alarms on. annunciator windows are checked:

ALB-5B, 3.4, PRZR 1 of 4 PRESS LO ALB-5B, 4.4, PRZR 1 of 4 SI PRESS LO ALB-5C, 1.5, ANY N16 DEV HI/ LO ALB-5C, 2.5, 1of 4 OT N16 HI ALB-5C, 2.6, 1of 4 OP N16 HI ALB-5C, 3.1, PRZR 1 of 4 PRESS HI ALB-5C, 3.5, ANY TAVE DEV HI/LO ALB-6D, 2.13, 1of 4 OP N16 ROD STOP &

TURB RUNBACK ALB-6D, 3.10, 1of 4 TAVE LO-LO ALB-6D, 3.14, 1of 4 OT N16 ROD STOP &

CUE: Annunciator windows TURB RUNBACK ALB-5B, 3.4 and 4.4; ALB-5C, 1.5, 2.5, 2.6, 3.1 and 3.5 and ALB-6D, 2.13,3.10 and 3.14 are all lit.

Page 5 of 6 Rev Date: 04/26/99

JPMC3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure 8 Verify appropriate trip status The following trip lights ON. status lights are checked:

TSLB-1, 1.7, PRZR PRESS LO PB-455D TSLB-3,1.1, RC LOOP 1 TAVE LO TB-421G TSLB-5, 1.2, PRZR PRESS LO PB-455C TSLB-5, 1.3, PRZR PRESS HI PB-455A TSLB-5, 1.8, RC LOOP 1 OT N16 TB-411C TSLB-5, 1.9, RC LOOP 1 OP N16 JB-411D TSLB-9, 1.4, OT N16 ROD STOP & TURB RUNBACK TB-411D TSLB-9, 1.5, OP N16 ROD STOP & TURB RUNBACK TB-411D TSLB-9, 1.9, RC LOOP 1 TAVE LO-LO TB-412D CUE: Trip status lights TSLB-1, 1.7, TSLB-3. 1.1, TSLB-5, 1.2, 1.3, 1.8 and 1.9 and TSLB-9, 1.3, 1.4, 1.5, and 1.9 are LIT.

STUDENT INDICATES TASK COMPLETE.

Page 6 of 6 Rev Date: 04/26/99

JPMC3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE:

A failure low of Pressurizer pressure channel PT-455 has occurred during full power operation. The alternate channel has been selected for control and recording. You are directed to place the appropriate bistables in the tripped condition, and verify the appropriate annunciator alarms and trip status lights.

Page 7 of 6 Rev Date: 04/26/99

JPMCBU Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: Main Feedwater System JTA Task #: CPSES BANK: RO1833 Task

Title:

FW Flow Instrument Malfunction KSA Ref: SF4.059.A2.11 PEO: RO: 3.0 SRO: 3.3 Operator=s Name:

Performance Environment: PLANT CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated 10 min. Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

Page 1 of 4 Rev Date: 01/24/99

JPMCBU Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure

References:

Tools, Equipment, Job Aids, etc:

ABN-708, AFeedwater Flow Instrumentation Reset simulator to at power IC. Insert malfunction Malfunction@ RX01C at 0%. Go to RUN. After ALB-08A, 2.8 and 2.12 annunciate, go to FREEZE. After initiating cue given, go to RUN.

Page 2 of 4 Rev Date: 01/24/99

JPMCBU Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

ALB-08A windows 2.8, "SG 2 STM FLO/FW FLO MISMATCH", AND 2.12, "SG 2 LVL DEV",

have annunciated. You notice the controlling FW FLO channel to SG 2 (u-F1-520A) has failed low and inform the Unit Supervisor. The Unit Supervisor directs you to take the appropriate actions of ABN-708.

Terminating Conditions:

SG 2 Main Feed Regulating Valve is in Automatic Page 3 of 4 Rev Date: 01/24/99

JPMCBU Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT

• 1 Take manual control of u-FK- Manual pushbutton on 520, SG 2 FW FLO CTRL. u-FK-520 depressed and amber light on CUE: Amber light is LIT and manual pushbutton and white light is DARK. white light on Auto pushbutton checked.

2 Adjust feedwater flow to attain SG 2 level is checked.

approximately 67% in Affected FCV adjusted SG 2. to maintain SG level at program.

CUE: SG NR level indication for SG 2 is reading 76%. Downward output pushbutton on u-FK-CUE: SG NR level indication 520 is depressed as for SG 2 is approximately required to reduce SG 2 67%. (64%). level to 67% (64%).

• 3 Select the alternate feedwater Handswitch u-FS-520C flow channel. placed in FY-521B position.

CUE: SG NR level is 67%

(64%), STM FLO and FW FLO are matched.

CUE: u-FS-520C is in the FY-521B position.

• 4 Place SG Main Feedwater Auto pushbutton on u-Control Valve in Auto. FK-520 depressed and Auto pushbutton white CUE: u-FK-520 is properly light and manual amber controlling in Auto and whit light checked. Proper light is LIT and amber light is control is verified.

DARK.

TASK COMPLETE Page 4 of 4 Rev Date: 01/24/99

JPMCBU Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: ALB-08A windows 2.8, "SG 2 STM FLO/FW FLO MISMATCH", AND 2.12, "SG 2 LVL DEV", have annunciated. You notice the controlling FW FLO channel to SG 2 (u-F1-520A) has failed low and inform the Unit Supervisor. The Unit Supervisor directs you to take the appropriate actions of ABN-708.

Page 5 of 4 Rev Date: 01/24/99

JPMP1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: Emergency Plant Evolutions JTA Task #: CPSES BANK (M0D): AO5407A Task

Title:

In Response to a Fire in the Control Room or Cable Spreading Room, Perform PEO #1 Actions to Achieve Hot Shutdown (AB Actions Only)

KSA Ref: APE.068.AA1.22 PEO: X RO: 4.0 SRO: 4.3 Operator=s Name:

Performance Environment: PLANT CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated 15 minutes Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

Page 1 of 6 Rev Date: 4/06/01

JPMP1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure

References:

Tools, Equipment, Job Aids, etc:

ABN-803A(B), "Response to a Fire in the ABN-803A(B), Attachment 3 Gloves, flashlight, valve Control Room or Cable Spreading Room" operator, radio Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

For JPM=s which are to be APERFORMED@, cues for indications and controls need not be given.

Instructions:

You may use any approved reference materials, including logs. Make or simulate all written/oral reports as if the evolution is actually being performed. You are expected to discuss all steps you would take, including identifying what switches/indications you would use.

Initiating Cue:

ABN-803A(B), "Response to a Fire in the Control Room or Cable Spreading Room", has been initiated. As PEO No. 1, you have obtained your radio for communications and have completed Attachment 3, through step h (g for Unit 2). Place charging in service and control seal injection per Attachment 3.

Terminating Conditions:

The operator reports seal injection flow is established.

Page 1 of 6 Rev Date: 4/06/01

JPMP1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT

• 1 Proceed to AB 810 outside the MANUALLY OPEN u- u-LCV-112E, Charging Pump Valve Room LCV-112E by RWST to CVCS and manually open u-LCV- DISENGAGING the Suction Valve is 112E, RWST to CVCS Suction. Motor Clutch and located in Aux.

rotating the Handwheel Bldg. 810' on the CUE: u-LCV-112E indicates counter clockwise Southside in the OPEN position. (left). Observe local (Northside) position indication Corridor.

(open).

The clutch disengage lever must be depressed until the LEVER is held in-place mechanically, after the handwheel has been rotated.

• 2 Proceed to AB 810, CCW Transfer CCWP AREA Transfer and start PUMP u-01 Room to: FAN COOLER 09 will be control to LOCAL and accomplished in the Transfer CCWP AREA FAN START CCWP AREA CCW PUMP u COOLER 09 CONTROL TO FAN COOLER 09, ROOM located on LOCAL AB 810' using TRANSFER SWITCH (u-HS- TRANSFER START CCWP AREA FAN 5800B) and CONTROL COOLER 09 SWITCH is a 2-SWITCH (u-HS- position maintain 5800C) switch. LOCAL CUE: When Transfer POSITION is to Switch, u-HS-5800B, is taken the right.

to Local, Green light is ON.

U1 switch in CCW CUE: When Control Switch, Pump 1-01 Room, u-HS-5800C, is taken to U2 switch in hall Start, Green light is OFF and outside CCW Pump Red light is ON. 2-01 room.

Page 3 of 6 Rev Date: 4/06/01

JPMP1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT If performing this JPM on Unit 1 then perform Step 3, then go to Step 6.

If performing this JPM on Unit 2 then go to Step 4 and Step 5, then Step 6

• 3 (Unit 1 only) Manually OPEN 1-8111 by 1-8111 is located in the Manually OPEN 1-8111 CCP 1 & 2 disengaging the motor clutch Charging Pump Valve MINI-FLOW VALVE and rotating the handwheel Room.

counter clock-wise (left).

CUE: 1-8111 indicates in the OPEN Observe local position position. indication.

• 4 (Unit 2 only) Manually OPEN 2-8512B by 2-8512B is located in disengaging the motor clutch the Unit 2 822 Blender and rotating the handwheel Room.

Manually OPEN 2-8512B, CCP 2-01 counter - clock-wise (left).

ALT MINIFLOW DNSTRM ISOL Observe local position VLV. indication (OPEN).

CUE: 2-8512B indicates in the OPEN position.

• 5 (Unit 2 only) Manually OPEN 2-8511A by 2-8511A is located in disengaging the motor clutch the Unit 2 822 Blender and rotating the hand-wheel Room.

Manually OPEN 2-8511A, CCP 2-01 counter clock-wise (left).

ALT MINIFLO UPSTRM ISOL VLV. Observe local position indication (OPEN).

CUE: 2-8511A indicates in the OPEN position.

• 6 (Units 1 & 2) Manually CLOSE u-LCV- u-LCV-112C is 112C by disengaging the motor located in each clutch and rotating the respective Unit's Manually CLOSE u-LCV-112C, VCT handwheel clock-wise (right). Charging Pump Valve OUTLET ISOLATION. Observe local position Room.

indication (CLOSED).

CUE: u-LCV-112C indicated in the CLOSED position.

• 7 Manually CLOSE u-8483B-RO, CCP u- CLOSE u-8483-R0 by u-8483 can be 01/ u-02 CHRG FLO CTRL VLV OUT rotating the handwheel clock- operated locally in each VLV RMT OPER wise (right). Observe local respective unit's position indication (CLOSED). Charging Pump Valve Room or Remotely in CUE: u-8483-R0 indicates in the each respective Unit's CLOSED position. Blender Room.

Page 4 of 6 Rev Date: 4/06/01

JPMP1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT CLOSED position.

8 Contact the RO and inform him that the The RO is contacted by either RO is located at the charging pump may be started. 2-way radio or gaitronics. RSP.

CUE: Charging Pump has been started.

CUE: RO directs opening u-8483B, CCP u-01/ u-02 CHRG FLO CTRL VLV OUT VLV RMT OPER, 2 full turns and report back.

• 9 Throttle OPEN u-8483B-R0, CCP u-01/ Throttle OPEN u-8483B RO 2 u-02 CHRG FLO CTRL VLV OUT VLV full turns by rotating the RMT OPER, is 2 turns open. RO handwheel or Remote contacted. Operator counter clock-wise (left) and reports back to the CUE:RO understands u-8483B is 2 turns RO at the RSP.

open.

TASK COMPLETE Page 5 of 6 Rev Date: 4/06/01

JPMP1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: ABN-803A(B), "Response to a Fire in the Control Room or Cable Spreading Room", has been initiated. As PEO No. 1, you have obtained your radio for communications and have completed Attachment 3, through step h (g for Unit 2). Place charging in service and control seal injection per Attachment 3.

Page 6 of 6 Rev Date: 4/06/01

JPMP2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: Steam Generator Tube Rupture JTA Task #: CPSES BANK: AO3528 Task

Title:

Locally Isolate Ruptured S/G KSA Ref: EPE.038.EA1.32 PEO: X RO: 4.6 SRO: 4.7 Operator=s Name:

Performance Environment: PLANT CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

Page 1 of 8 Rev Date: 01/24/99

JPMP2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure

References:

Tools, Equipment, Job Aids, etc:

EOP-3.0A(B), EOP-3.0A(B), Attachment 4 Steam Generator Tube Rupture Page 2 of 8 Rev Date: 01/24/99

JPMP2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

For JPM=s which are to be APERFORMED@, cues for indications and controls need not be given.

Instructions:

You may use any approved reference materials, including logs. Make or simulate all written/oral reports as if the evolution is actually being performed. You are expected to discuss all steps you would take, including identifying what switches/indications you would use.

Initiating Cue:

Procedure EOP-3.0A(B), "Steam Generator Tube Rupture" is in progress. The Control Room has directed you to perform attachment 4 as part of Step 3 (Isolate Flow From Ruptured SG(s))

Terminating Conditions:

All valves that require local isolation as per attachment 4, have been closed.

Page 3 of 8 Rev Date: 01/24/99

JPMP2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT

• 1 CUE: 1-HS-3228 will NOT Valve closed Located Unit 1 close from Control Room. TB 778= NE Corner Locally close 1SA-0005, U1 MS to AUX STM ISOL VLV

• 2 CUE: The Control Room All valves closed. All valves placed 41/2-SDA, STM DMP located in TB INTLK SELECT and 43/1- 803= South of SDB, STM DMP INTLK Main Condenser SELECT in OFF to close the Steam Dump Valves but the valves did NOT close.

Locally close the following valves:

1MS-0185, STM DMP TO CNDSR 1-A VLV 2369A UPSTRM ISOL VLV 1MS-0186, STM DMP TO CNDSR 1-A VLV 2370B UPSTRM ISOL VLV 1MS-0187, STM DMP TO CNDSR 1-A VLV 2370F UPSTRM ISOL VLV 1MS-0188, STM DMP TO CNDSR 1-A VLV 2370G UPSTRM ISOL VLV 1MS-0189, STM DMP TO CNDSR 1-A VLV 2369B UPSTRM ISOL VLV Page 4 of 8 Rev Date: 01/24/99

JPMP2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure 1MS-0190, STM DMP TO CNDSR 1-A VLV 2370D UPSTRM ISOL VLV 1MS-0191, STM DMP TO CNDSR 1-B VLV 2369C UPSTRM ISOL VLV 1MS-0192, STM DMP TO CNDSR 1-B VLV 2370C UPSTRM ISOL VLV 1MS-0193, STM DMP TO CNDSR 1-B VLV 2370H UPSTRM ISOL VLV 1MS-0194, STM DMP TO CNDSR 1-B VLV 2370J UPSTRM ISOL VLV 1MS-0195, STM DMP TO CNDSR 1-B VLV 2370A UPSTRM ISOL VLV 1MS-0196, STM DMP TO CNDSR 1-B VLV 2370E UPSTRM ISOL VLV

• 3 LOCALLY CLOSE THE All valves closed. All valves FOLLOWING VALVES: located in TB 803= South of 1MS-0520, STM DMP STM Main Condenser TRAP 1-18 UPSTRM ISOL VLV 1MS-0522, STM DMP STM TRAP 1-19 UPSTRM ISOL VLV 1MS-0524, STM DMP STM TRAP 1-20 UPSTRM ISOL VLV Page 5 of 8 Rev Date: 01/24/99

JPMP2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure 1MS-0526, STM DMP STM TRAP 1-21 UPSTRM ISOL VLV 1MS-0528, STM DMP STM TRAP 1-22 UPSTRM ISOL VLV 1MS-0530, STM DMP STM TRAP 1-23 UPSTRM ISOL VLV 1MS-0532, STM DMP STM TRAP 1-24 UPSTRM ISOL VLV 1MS-0534, STM DMP STM TRAP 1-25 UPSTRM ISOL VLV 1MS-0536, STM DMP STM TRAP 1-26 UPSTRM ISOL VLV 1MS-0538, STM DMP STM TRAP 1-27 UPSTRM ISOL VLV 1MS-0540, STM DMP STM TRAP 1-28 UPSTRM ISOL VLV 1MS-0542, STM DMP STM TRAP 1-29 UPSTRM ISOL VLV

• 4 CUE: The Main Feedwater Both valves closed. Valve located on Pumps are NOT being used to North side of each supply the Steam Generators FWP skid On the North side of the MFW Page 6 of 8 Rev Date: 01/24/99

JPMP2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure pump skids, close the following valves._

1MS-0254, FWPT 1-A HP STM SPLY ISOL VLV 1MS-0253, FWPT 1-B HP STM SPLY ISOL VLV

• 5 Locally close the following All valve closed All valves valves: accessible from operating deck 1VD-0421, MS D/POT 1-03 located in the TO CNDSR 1-A DRN HDR A Vent and Drain ISOL VLV Valve Alley above the EHC 1VD-0424, MS D/POT 1-04 Skid center TO CNDSR 1-A DRN HDR A section.

ISOL VLV 1VD-0425, MS D/POT 1-09 TO CNDSR 1-A DRN HDR A ISOL VLV 1VD-0426, MS D/POT 1-02 TO CNDSR 1-A DRN HDR A ISOL VLV 1VD-0427, MS D/POT 1-28 TO CNDSR 1-A DRN HDR A ISOL VLV 1VD-0428, MS D/POT 1-10 TO CNDSR 1-A DRN A ISOL VLV 1VD-0429, MS D/POT 1-20 TO CNDSR 1-A DRN HDR A ISOL VLV 1VD-0431, MS D/POT 1-13 TO CNDSR 1-A DRN HDR A ISOL VLV Page 7 of 8 Rev Date: 01/24/99

JPMP2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure 1VD-0432, MS D/POT 1-19 TO CNDSR 1-A DRN HDR A ISOL VLV 1VD-0433, MS D/POT 1-12 TO CNDSR 1-A DRN HDR A ISOL VLV 1VD-0437, MS D/POT 1-11 TO CNDSR 1-A DRN HDR A ISOL VLV

• 6 LOCALLY CLOSE THE All valves closed. All 4 valves FOLLOWING VALVES: located at Unit 1 TB 778= East 1MS-0028, SG 1-01 SMPL Wall behind Vent VLV chiller #5, 10 up 1MS-0065, SG 1-02 SMPL VLV 1MS-0136, SG 1-04 SMPL VLV 1MS-0291, SG 1-03 SMPL VLV TASK COMPLETE Page 8 of 8 Rev Date: 01/24/99

JPMP2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: Procedure EOP-3.0A(B), ASteam Generator Tube Rupture@ is in progress. The Control Room has directed you to perform attachment 4 as part of Step 3 (Isolate Flow From Ruptured SG(s).

Page 9 of 8 Rev Date: 01/24/99

JPMP3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: Emergency Diesel Generator JTA Task #: CPSES BANK: AO6311A Task

Title:

Perform a Local Emergency Start of a DG (RCA ENTRY REQUIRED)

KSA Ref: SF6.064.A4.01 PEO: X RO: 4.0 SRO: 4.3 Operator=s Name:

Performance Environment: PLANT CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

Page 1 of 6 Rev Date: 02/01/00

JPMP3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure

References:

Tools, Equipment, Job Aids, etc:

SOP-609A(B), Diesel Generator System SOP-609A(B) Section 1 through 4 and Section 5.2 of SOP-609A(B).

Page 2 of 6 Rev Date: 02/01/00

JPMP3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

For JPM=s which are to be APERFORMED@, cues for indications and controls need not be given.

NOTE: Step 9 (checking operating parameters) does NOT need to be performed for a RO and SRO because all are in spec. and no action is required.

Instructions:

You may use any approved reference materials, including logs. Make or simulate all written/oral reports as if the evolution is actually being performed. You are expected to discuss all steps you would take, including identifying what switches/indications you would use Initiating Cue:

You have been directed to perform a Local Emergency Start of Train A(B) DG for testing. An Engine Water Roll Check, all prerequisites and all Maintenance Department pre-start activities have been performed. The Prompt Team and Chemistry have been informed. The Aslow start@ is NOT being performed. The DG is an auto-start status. This test does not meet the Surveillance Test requirements.

Terminating Conditions:

Train A(B) DG is running.

Page 3 of 6 Rev Date: 02/01/00

JPMP3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1 Notify Control Room Starting the Local Emergency

• 2 Start auxiliary lube oil pump by Handswitch in HAND Do not run placing handswitch (u-HS- position and the lube auxiliary lube oil 3411-1 Train A or u-HS-3412- oil pump running. Lube pump in HAND 1 Train B) in HAND. oil pressure should be for more than 1 40-60 psig. minute per shift CUE: Auxiliary lube oil pump without running RED (ON) light is LIT and the DG.

GREEN (OFF and AUTO) lights are DARK. Pressure on Auxiliary lube oil lube oil pressure gauge (u-PI- pump handswitch 3411B-1B Train A or u-PI- is located on the 3412B Train B) is 56 psig. Local Engine Control Panel.

• 3 Stop auxiliary lube oil pump by Auxiliary lube oil pump Diesel must be placing handswitch (u-HS- NOT running and started within 60 34111 Train A or u-HS-3412-1 handswitch in AUTO seconds of Train B) in OFF then AUTO. position. stopping Aux.

lube oil pump.

CUE: Auxiliary lube oil pump RED (ON) light is DARK and If not started GREEN (OFF and AUTO) within 60 seconds lights are LIT. must repeat above step of JPM.

• 4 Take local control of DG by The Master Switch in Master Switch is placing the Master Switch (u- LOCAL position. located on Local HS-3413-3b, RLMS Train A or Generator Control u-HS-3414-3B, RLMS Train Panel.

B) in LOCAL.

Page 4 of 6 Rev Date: 02/01/00

JPMP3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT CUE: The Master Switch is in the LOCAL position.

• 5 Start the DG by placing the Local emergency Stop- Local emergency local emergency Stop-Start Start handswitch in Stop-Start handswitch (u-HS-3413-4B, START position and handswitch is LOC/EMER/MAN/START engine running. located on the Train A or u-HS-3414-4B Local Generator LOC/EMER/MAN/START Control Panel.

Train B) in START.

CUE: Engine rpm is increasing.

6 Verify auxiliary lube oil pump Auxiliary lube oil pump handswitch (u-HS-3411-1 handswitch in AUTO Train A or u-HS-3412-1 Train position and pump NOT B) in AUTO and pump not running.

running.

CUE: Auxiliary lube oil pump RED (ON) light DARK and GREEN (OFF and AUTO) lights are LIT. Pump handswitch is in AUTO.

• 7 Stop Auxiliary jacket water Auxiliary jacket water Auxiliary jacket pump by placing handswitch pump handswitch in water pump (u-HS-3415-1 Train A or u- AUTO position and handswitch is HS-3416-1 Train B) in OFF pump NOT running. located on the and then AUTO. Verify pump Local Engine is not running. Control Panel.

CUE: Auxiliary jacket water pump RED (ON) light DARK and GREEN (OFF and AUTO) lights are LIT. Pump handswitch is in AUTO.

Page 5 of 6 Rev Date: 02/01/00

JPMP3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 8 Verify DG voltage is building DG voltage increasing DG voltage is and engine speed is normal. and engine speed is read on the Local between 440 and 475 Generator Control CUE: DG voltage is RPM. Panel.

increasing and engine speed is 450 rpm. If Operator asks, Engine speed is voltage is 7000V. read on the Local Engine Control Panel.

9 Check operating parameters: Lube oil pressure RUNNING and Lube oil pressure Turbo oil pressure, left READY TO Turbo oil pressure, left bank front LOAD lights are Turbo oil pressure, right Turbo oil pressure, located on the bank right front Local Engine Jacket water pressure Jacket water pressure Control Panel.

Fuel oil pressure, black-engine Fuel oil pressure, driven pump black-engine driven NOTE: TASK pump may be Engine speed Engine speed TERMINATED CUE: without having a L/O press = 53 psig Reactor Operator T/O LF press = 28 psig Log any of these T/O RF press = 27 psig values SINCE all JW press = 23 psig will be in spec.

FO black press = 42 psig and no action is Engine speed = 450 rpm required TASK COMPLETE Page 6 of 6 Rev Date: 02/01/00

JPMP3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE:

You have been directed to perform a Local Emergency Start of Train A(B) DG for testing. An Engine Water Roll Check, all prerequisites and all Maintenance Department pre-start activities have been performed. The Prompt Team and Chemistry have been informed. The Aslow start@ is NOT being performed. The DG is an auto-start status. This test does not meet the Surveillance Test requirements.

Page 7 of 6 Rev Date: 02/01/00

JPMS1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: Reactor Coolant JTA Task #: CPSES BANK: RO1102 Task

Title:

Start/Stop RCP (ALTERNATE PATH)

KSA Ref: SF4.003.A4.06 PEO: RO: 2.9 SRO: 2.9 Operator=s Name:

Performance Environment: PLANT CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated 20 min Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

References:

Tools, Equipment, Job Aids, etc:

SOP-108A(B), AReactor Coolant Pump@ SOP-108A/B (Working Copy). Reset to Heatup IC.

Rack in #3 RCP breaker using Remote Function Page 1 of 11 Rev Date: 05/18/99

JPMS1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Rack in #3 RCP breaker using Remote Function RCR14. Override Ammeter for RCP #3 to max when pump is started and delete override when pump is stopped.

Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to Manipulate any plant components.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

IPO-001, "Plant Heatup From Cold Shutdown to Hot Standby", has progressed to the point of starting the third Reactor Coolant Pump per SOP-108. All prerequisites have been met and all steps have been completed through step 5.1.7 in SOP-108. All seal flows are within limits. You are directed to start #3 RCP continuing with step 5.1.8 of SOP-108.

Terminating Conditions:

The #3 RCP and its associated oil lift pump has been stopped.

Page 2 of 11 Rev Date: 05/18/99

JPMS1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1 Verify the alarms on ALB-5A The following alarms are clear are checked clear:

CUE: Alarms clear. 1.2 ANY RCP SEAL 1 LKOFF FLO HI 1.6 ANY RCP SEAL WTR INJ FLOW LO 2.2 ANY RCP SEAL 1 _P LO 3.1 ANY RCP SEAL WTR STANDPIPE LVL HI 3.2 ANY RCP SEAL 2 LKOFF FLO HI 4.1 ANY RCP SEAL WTR STANDPIPE LVL LO 3.4 RCP 3 UP BRG L/O RESVR LVL HI/LO 3.5 RCP 3 LOW BRG L/O RESVR LVL HI/LO 2 Verify proper cooling water The following (CB-03) flows. parameters are checked within the specified CUE: u-FI-4683 indicates 175 limits:

gpm.

RCP 3 UP BRG L/O CUE: u-FI-4685 indicates 8 CLR CCW RET FLO u-gpm. FI-4683 indicates 150-190 gpm_ RCP 3 LOW CUE: u-FI-4684 indicates 355 gpm. CUE: u-FI-4686 indicates BRG L/O CLR CCW Page 3 of 7 Rev Date: 05/18/99

JPMS1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure gpm. CUE: u-FI-4686 indicates RET FLO u-FI-4685 indicates 5 to 10 gpm 40 gpm RCP 3 MOTOR AIR CLR CCW RET FLO u-fi-4684 indicates 340 to 380 gpm RCP 3 THBR CLR CCW RET FLO u-FI-4686 indicates 35 to 55 gpm 3 Initiate trending of data for the The plant computer is affected RCP if not previously trending the points done. specified per SOP-108 Attachment 2 CUE: The Relief RO has initiated trending as required.

4 Ensure the breaker for the #3 The #3 RCP breaker is RCP is racked in. racked in (verified by dispatching a PEO to CUE: The breaker was check RCP #3 breaker previously racked in. on uA3 LOCALLY).

5 Ensure the overcurrent trip The #3 RCP selector switch is in the Overcurrent Trip ACOLD LOOP@ position Selector switch is placed in the ACOLD CUE: The selector switch was LOOP@ position previously placed in this (verified by dispatching condition. a PEO to check the switch is in the proper position at the RCP #3 Breaker on uA3 LOCALLY).

6 Station personnel at #3 RCP to Operator asks if the observe the pump. RCP is accessible.

CUE: The RCP is not accessible

• 7 Start the #3 RCP oil lift pump 1/u-PCPX3-LP, RCP 3 OIL LIFT PMP, switch CUE: Green light OFF Red taken to the ASTART@

Page 4 of 7 Rev Date: 05/18/99

JPMS1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure light ON. taken to the ASTART@

position B candidate verifies green light off and red light on and should mark time to verify pump runs for 2 minutes prior to starting

1. 3 RCP.

8 Check OIL PRESS permissive Candidate verifies Blue interlock (blue light) lit. AOIL PRESS@ light lit.

CUE: Blue light ON.

• 9 Start the #3 RCP 1/u-PCPX3 taken to the START _ 2 minutes CUE: Green light OFF Red after the oil lift pump light ON. start. Candidate verifies Green light off and Red light on.

10 Verify Alarm 2.1 on ALB-5B ANY RCP FAIL TO clear. START Alarm 2.1 on ALB-5B is clear.

CUE: Window 2.1 is DARK 11 VERIFY #3 RCP undervoltage Candidate verifies TSLB goes out. TSLB-4, 3.2, RCP 3 BUS UNDERVOLT CUE: White light not lit. NOT lit.

12 Verify #3 Loop flow increases Candidate checks #3 #3 RCP should be within 10 seconds. loop flow on u-FI- stopped if flow 434/35/36, RC LOOP 3 does not increase CUE: Loop flow is increasing FLO within 10 sec.

13 Verify #3 RCP motor amps Candidate checks #3 #3 RCP should be have decreased to less than or motor current on u-II- stopped if motor equal to 750 amp within one RCP3, RCP3 MOTOR current does not minute CURRENT, and decrease to less observes it does not than or equal to CUE: Meter for motor amps is decrease within 1 750 amps in one pegged high. minute. minute.

Page 5 of 7 Rev Date: 05/18/99

JPMS1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure 14 Inform the SRO of problem SRO informed of with motor amps. problem.

CUE: SRO acknowledges report.

• 15 Stop #3 RCP. Candidate momentarily places 1/u-PCPX1, #3 CUE: Green light ON Red RCP to STOP.

light OFF.

16 Stop the #3 RCP oil lift pump Candidate should take switch 1/u-PCPX3-LP.

CUE: Blue and Red lights off. RCP 3 OIL LIFT Green light on. PUMP, to the stop position after RCP #3 has operated greater than 1 minute OR if #3 RCP has been stopped.

TASK COMPLETE Page 6 of 7 Rev Date: 05/18/99

JPMS1 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE:

IPO-001, "Plant Heatup From Cold Shutdown to Hot Standby", has progressed to the point of starting the third Reactor Coolant Pump per SOP-108. All prerequisites have been met and all steps have been completed through step 5.1.7 in SOP-108. All seal flows are within limits.

You are directed to start #3 RCP continuing with step 5.1.8 of SOP-108.

Page 7 of 7 Rev Date: 05/18/99

JPMS2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: Containment Cooling Systems JTA Task #: CPSES BANK: RO1703 Task

Title:

Restore Containment Cooling KSA Ref: SF5.022.A4.01 PEO: RO: 3.6 SRO: 3.6 Operator=s Name:

Performance Environment: PLANT CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated 20 min. Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

References:

Tools, Equipment, Job Aids, etc:

EOP-0.0A, AReactor Trip or Safety Injection@, Load an at Power IC, enter malfunction RP14A &

SOP-814, AVentilation Chilled Water System@, RP14B then delete malfunction, wait two minutes, reset SI, sequencer and phase A. Enter EDR33 & EDR 36 to CLOSE, ensure all pipe penetration fans off with green Page 1 of 7 Rev Date: 1/04/00

JPMS2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure flags.

Page 2 of 7 Rev Date: 1/04/00

JPMS2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

Unit 1 is recovering from a Safety Injection. The Unit Supervisor has directed you to restore Containment Cooling to service per EOP-0.0A, Attachment 9, step 4. SI has been reset and power restored to all MCCs. CCW non-safeguards loop is aligned. HVAC Centrifugal Chillers X-03 and X-04 are unavailable. Containment Phase A isolation has been reset.

Terminating Conditions:

Terminate, once at least one Reactor Coolant Pipe Penetration Ventilation Fan is started.

Page 3 of 7 Rev Date: 1/04/00

JPMS2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1 Ensure 1-HS-4650, VENT Operator visually CUE: If asked CHLR CCW SPLY & RET LV verifies BHS_4650 to inform operator:

is open. be open by red light Vent Chillers X-indication on the 05 & X-06 have CUE: 1-HS-4650 handswitch handswitch at CB-3. CW aligned from indication is red. The chilled Unit 1 water containment isolation valves were closed on Phase A isolation signal.

• 2 Open 1-HS-6082, CH WTR Take handswitch 1-HS- Steps 2 through 4 RET ISOL VLV. 6082 to the open may be done in position and verify red any order.

CUE: 1-HS-6082 handswitch light indication on the indication is red. handswitch on CB-3

• 3 Open 1-HS_6083 CH WTR Take handswitch 1-HS-RET ISOL VLV. 6083 to the open position and verify red CUE: 1-HS-6083 handswitch light indication on the indication is red. handswitch on CB-3.

• 4 Open 1-HS-6084, CH WTR Take handswitch 1-SPLY ISOL VLV. HS_6084 to the open position and verify red CUE: 1-hs-6084 light indication on the HANDSWITCH INDICATION handswitch on CB-3.

IS RED. All chilled water Recirc pumps are tripped.

5 Ensure CH WTR RECIRC Take handswitch X- Steps 5 and 6 may PMP 1 OR 3 running. HS-6055 (pump 1) or be done in any X-HS-6057 (pump 3) to order.

CUE: Depending on which the start position and pump was started: X-HS-6055 verify red light or X-HS-6057 handswitch indication on the indication is red. X-FI-6073 handswitch. Flow may indicates 150 gpm. be verified on X-FI-6073.

6 Ensure CH WTR RECIRC Take handswitch X-PMP 2 OR 4 running. HS-6056 (pump 2) or X-HS-6058 (pump 4) to Page 4 of 7 Rev Date: 1/04/00

JPMS2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT CUE: Depending on which the start position and pump was started: X-HS-6056 verify red light or X-HS-6058 handswitch indication on the indication is red. X-FI-6073 handswitch. Flow may indicates 2500 gpm. be verified on X-FI-6073.

7 Place the remaining two CH Take handswitches for Pumps in this step WTR RECIRC PMPS to the chiller pumps not may be operated AUTO After Stop Position. started to the AUTO in any order.

After Stop Position CUE: Depending on which X-HS-6055 NOTE: If PEO pumps were taken to AUTO X-HS-6056 asked status of After Stop: X-HS-6057 CW Booster X-HS-6055 X-HS-6058 Pumps, report X-HS-6056 Verify green light pumps X-12 & X-X-HS-6057 indication on the 13 running X-HS-6058 handswitch.

Handswitch indication is green.

8 Dispatch PEO to start HVAC Operator uses radio or Note: May only CENTRIFUGAL WATER Gaitronics to dispatch start one chiller.

CHILLER X-01 and X-02. PEO to start HVAC CENTRIFUGAL CUE: HVAC chillers X-01 CHILLERS X-01 and and X-02 are running. X-02.

• 9 Start CNTMT FN CLR FN1. Take handswitch 1-HS- Note: Only 3 5405A to the start CNTMT Fan CUE: 1-HS-5405A position and verify red coolers need be handswitch indication is red. light indication on the started. May be handswitch done in any order.

• 10 Start CNTMT FN CLR 2. Take handswitch 1-HS-5409A to the start CUE: 1-HS-5409A position and verify red handswitch indication is red. light indication on the handswitch.

• 11 Start CNTMT FN CLR FN3. Take handswitch 1-HS-5413A to the start Page 5 of 7 Rev Date: 1/04/00

JPMS2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure CUE: 1-HS-5413A position and verify red handswitch indication is red. light indication on the handswitch.

• 12 Start CNTMT FN CLR FN 4. Take handswitch 1-HS-5417A to the start CUE: 1-HS-5417A position and verify red handswitch indication is red. light indication on the handswitch.

• 13 Start CRDM VENT FN 1. Take handswitch 1-HS- Note: Only 1 5421 to the start CRDM Vent Fan CUE: 1-HS-5421 handswitch position and verify red need be started.

indication is red. light indication on the handswitch.

• 14 Start CRDM VENT FN 2. Take handswitch 1-HS-5423 to the start CUE: 1-HS-5423 handswitch position and verify red indication is red. light indication on the handswitch.

• 15 Start NEUT DET WELL FN Take handswitch 1-HS- Note: Only 1 CLR FN 9 & DMPR 5435 to the start neutron detector position and verify red well fan cooler CUE: 1-HS-5435 handswitch light indication on the need be started.

indication is red. handswitch.

• 16 Start NEUT DET WELL FN Take handswitch 1-HS-CLR FN 10 & DMPR. 5440 to the start position and verify red CUE: 1-HS-5440 handswitch light indication on the indication is red. handswitch.

• 17 Start RC PIPE PENET AREA Take handswitch 1-HS- Note: Must start VENT FN 1. 5461 to the start 1 or 2 Vent Fan position and verify red CUE: 1-HS-5461 handswitch light indication on the indication is red. handswitch.

• 18 Start RC PIPE PENET AREA Take handswitch 1-HS- Note: Must start VENT FN 2. 5463 to the start 1 or 2 Vent Fan position and verify red CUE: 1-HS-5463 handswitch light indication on the indication is red. handswitch

• 19 Start RC PIPE PENET AREA Take handswitch 1-HS- Note: Must start VENT FN 3. 5465 to the start 3 or 4 Vent Fan position and verify red Page 6 of 7 Rev Date: 1/04/00

JPMS2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure CUE: 1-HS-5465 handswitch light indication on the indication is red. handswitch

• 20 Start RC PIPE PENET AREA Take handswitch 1-HS- Note: Must start VENT FN 4. 5467 to the start 1 or 2 Vent Fan position and verify red CUE: 1-HS-5467 handswitch light indication on the indication is red. handswitch TASK COMPLETE Page 7 of 7 Rev Date: 1/04/00

JPMS2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: Unit 1 is recovering from a Safety Injection. The Unit Supervisor has directed you to restore Containment Cooling to service per EOP-0.0A, Attachment 9, step 4. SI has been reset and power restored to all MCCs. CCW non-safeguards loop is aligned. HVAC Centrifugal Chillers X-03 and X-04 are unavailable. Containment Phase A isolation has been reset.

Page 8 of 7 Rev Date: 1/04/00

JPMS3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: CVCS JTA Task #: CPSES BANK: RO1336 Task

Title:

Rx M/U Water Malfunction (ALTERNATE PATH)

KSA Ref: SF2.004.A4.07 PEO: RO: 3.9 SRO: 3.7 Operator=s Name:

Performance Environment: PLANT CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated 15 min. Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

References:

Tools, Equipment, Job Aids, etc:

ABN-105 ACVCS Malfunctions@ Simulator Setup: IC-15, enter CV01A, trip #1 Rx MU SOP-104A(B) ARx M/U System@ Pump, with RSCU code 1 when dilution started. IO ALM-011A(B) alarm ALB-1, C.5 (ON) and ZL-5349AB (ON) when ALM-061A(B) pump trips.

Page 1 of 5 Rev Date: 01/24/01

JPMS3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure TDM-203A(B)

Page 2 of 5 Rev Date: 01/24/01

JPMS3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

You have just relieved the shift and Reactor power is 50%. The Unit Supervisor directs you to perform a normal dilution of 50 gallons to prepare to raise power.

Terminating Conditions:

PEO dispatched to start Common RMUW pump.

Page 3 of 5 Rev Date: 01/24/01

JPMS3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1 Place 1/u-LCV-112A in HUT 1/u-LCV-112A in HUT Step 1 may not be position position and associated performed per red light is lit. NOTE in SOP-CUE: HUT Ared@ light on 1/u- 104A Section LCV-112A 5.1.3.

2 Monitor VCT level and Monitor u-L1-112A and pressure during dilution. u-P1-115 during dilution.

CUE: u-L1-112A indicates 48% and u-P1-115 indicates 19 psig.

3 Go to ASTOP@ MU RCS MU 1/u-MU RCS MU MAN MAN ACT ACT in ASTOP@

CUE: 1/u-MU green light on 4 Place 43/u-MU RCS MU 43/u-MU RCS MU NOT CRITICAL MODE SELECT in ADILUTE@ MODE SELECT in dilution evaluated ADILUTE@ in another JPM.

5 Set u-FK-111 to desired flow. u-FK-111 set as desired.

CUE: RMUW Pot set to desired flow.

6 Set u-FY-111B ARCS MU Set u-FY-111B ARCS BATCH FLO@ flow to 50 MU BATCH FLO@ to gallons. 50 gal CUE: u-FY-111B set to 50 gal 7 Go to start on 1/u-MU, RCS 1/u-MU, RCS MU Activate CV09A MU MAN ACT MAN ACT IN with MFA1 ASTART@

CUE: The following alarms Activate IOs come in: ALB-1, C/5 to RMUW LO PRESS, on ALB-1, CN ZL-5349AB 2.5 to ON RMUW PMP 1/COMM OVRLOAD TRIP, on ALB-1, 3.5 RCS MU FLO DEV on ALB-6A 3.7 Page 4 of 5 Rev Date: 01/24/01

JPMS3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 8 Identify the affected pump on u- Monitor status of lights ZL-5349A RMUQ PMP 1 and u-ZL-5349A and x-ZL-X-ZL-5350A COMM RMUW 5350A.

PMP.

CUE: Green and white light lit on u-ZL-5349A, green light on X-ZL-5350A.

9 Go to stop on 1/u-MU, RCS 1/u-MU, RCS MU MU MAN ACT MAN ACT IN ASTOP@

CUE: 1/u-MU, RCS MU MAN ACT IN ASTOP@

• 10 Start X-HS-5350, RMUW Dispatch PEO to start pump X-01. X-HS-5350, RMUW pump X-01.

CUE: PEO called Page 5 of 5 Rev Date: 01/24/01

JPMS3 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: You have just relieved the shift and Reactor power is 50%. The Unit Supervisor directs you to perform a normal dilution of 50 gallons to prepare to raise power.

Page 6 of 5 Rev Date: 01/24/01

JPMS4 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: Component Cooling Water System JTA Task #: CPSES BANK (MOD): RO3608 Task

Title:

Shift CCW Pumps with CCW Pump Trip (ALTERNATE PATH)

KSA Ref: APE.026.AK3.04 PEO: RO: 3.5 SRO: 3.7 Operator=s Name:

Performance Environment: PLANT CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

References:

Tools, Equipment, Job Aids, etc:

SOP-502A, ACCW System@ ABN-502, Simulator: 1) Load 100% IC ABN-502, AComponent Cooling Water System 2) Insert and activate MALF-CC03A??

Malfunction@

3) Insert and activate MALF-CC02A??

Page 1 of 4 Rev Date: 11/02/98

JPMS4 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure

4) Insert and activate MALF-CC02B??

Page 2 of 4 Rev Date: 11/02/98

JPMS4 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to Manipulate any plant components.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

The Unit is operating at 50% power. The Unit Supervisor directs you to shift CCW pumps (start CCWP2, and secure CCWP1 per SOP-502) in preparation for maintenance.

Terminating Conditions:

Reactor tripped.

Page 3 of 5 Rev Date: 11/02/98

JPMS4 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1 Ensure SSWP2 is running Operator visually verifies SSWP2 is CUE: SSWP2 indication is running by verifying RED. handswitch indication is RED.

2 Ensure oil level in bearing Operator directs housings for CCWP2 are someone to verify oil normal. level for CCWP2.

CUE: bearing housing oil levels are reported normal.

• 3 Start CCWP2 Take handswitch u-HS-4519A to the start CUE: u-HS-4519A handswitch position and verify red light indication is RED. light indication on the handswitch.

4 Ensure the following equipment Same as Element.

are removed from service:

RHR Pumps 1-01/02, CS Pumps 1-01/02/03/04 CUE: Listed Pumps are removed from service.

• 5 Stop CCWP1 Operator holds the u- WARNING:

HS-4518A handswitch Operator may CUE: u-HS-4518A handswitch in STOP until flow and attempt to trip RX light indication is green. pressure stabilize and (per section 6.0 of then releases ABN-502A ALoss (CCWP2 trips): u-HS-4519A handswitch. of all CCW green light and white trip light Flow@) when lit. CCWP2 trips; Annunciator Alarms: CCWP operator 2 OVRLOAD/TRIP, CCW SHOULD go to TRN A/B SFGD LOOP PRESS section 2.0 of LO, CCW HX 2 OUT & ABN-502A RECIRC FLO LO, CCW HX 2 Page 4 of 5 Rev Date: 11/02/98

JPMS4 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure RECIRC FLO LO, CCW HX 2 ACCW Pump SPLY FLO LO Trip@ and attempt to start CCWP1; DO NOT allow operator to trip RX (it would interfere with JPMS3 running concurrently).

6 Verify unaffected train CCW Operator visually If operator Pump B RUNNING. verifies CCWP 1 is attempts to trip running by verifying u- the RX, DO NOT CUE: u-HS-4518A handswitch HS-4518A handswitch allow RX trip, light indication is green. indication is RED on and terminate the CB-3 JPM.

• 7 Start u-HS-4518A CCWP 1 Take handswitch u-HS-4518A to the start CUE: u-HS-4518A RED light position and verify red lit and flow restored. light indication on the handswitch and flow restored.

TASK COMPLETE Page 5 of 5 Rev Date: 11/02/98

JPMS4 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: The Unit is operating at 50% power. The Unit Supervisor directs you to shift CCW pumps (start CCWP2, and secure CCWP1 per SOP-502) in preparation for maintenance.

Page 6 of 5 Rev Date: 11/02/98

Appendix D Scenario Outline Form ES-D-1 Facility: CPSES Scenario No.: 1 Op-Test No.: 11/2002 Examiners: Howard Bundy Operators:

Mike Murphy Tom Stetka Fred Sanchez Note: (NEW) SRO Admin A.5-1, Emerg. Class. is to be done in conjunction with this Scenario. (PRELOAD - MET Tower Data -> wind 105)

Time (T) = 0 at end of power increase -> as directed by Chief Examiner Initial Conditions: Full power steady state; BOL; Equilibrium Xenon; Severe thunderstorm warning and high winds issued and ABN-907, Section 5 completed.

EDG 1-01 is out of service for maintenance (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> into LCO).

(IC Info.: EGR06 - DG1 out of service)

Turnover: The plant has been at 100% power for the last 15 days. A power reduction to 76% is required to perform MSIV testing. The load reduction should be initiated as soon as the shift change is completed.

Event Malf. Event Event No. No. Type* Description 1 N (SRO) Reduce power to 76%

T=0 R (RO) 2 RX05A I (SRO) Pressurizer level transmitter LT-459 fails low [value=0, ramp T=15 I (RO) over 1 min]

3 TC05A C (SRO) #1 Main turbine control valve fails closed T=22 C (BOP) 4 ED06G C (ALL) Loss of 1D3 bus T=30 5 RC03D C (RO) RCP 4 vibration - initial severity @ 9 mils and ramp severity to T=33 C (SRO) 25 mils over 30 min. High vib. alarm on RCP 4 (shaft) alarms at 15 mils & increasing @ approx 0.5 mils/min.

T=35 Manual Rx Scram due to high RCP 1-04 vibrations, no SI.

Enter EOP-0.0A and then transition to EOS-0.1A.

6 ED01 M (ALL) Lighting strike in switchyard - loss of offsite power. EDG 1-02 T=44 starts and loads (E19 triggers automatically when the reactor is tripped) 7 EG07B C (ALL) EDG 1-02 trips (overspeed) - loss of all power. Transition to T=50 ECA-0.0A and possibly ABN-601.

T=60 EDG 1-02 is restarted after S/G depressurization has started per ECA-0.0A.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 1 Event No: 1 Page 1 of 1 Event

Description:

Reduce power to 70%

Time RO BOP SRO Applicant's Actions or Behavior Review IPO-003A, Power Operations Notifies the Dispatcher prior to reducing load Notifies Chemistry and Radiation Protection if power reduction will be greater than 15% in one hour Notifies Reactor Engineering of power reduction greater than 25%

Calculates the amount of boration required Calculates the rate of boration Reviews AFD guidance Sets in the desired unloading rate on the LOAD GRADIENT device Initiates boration Lowers the LOAD REFERENCE device in incremental steps to control the power decrease Maintains AFD within the target band Maintains rods above the rod insertion limit Maintain Tavg within 1°F of Tref

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 1 Event No: 2 Page 1 of 3 Event

Description:

Pressurizer level transmitter LT-459 fails low Time RO BOP SRO Applicant's Actions or Behavior Recognizes indications that pressurizer level transmitter LT-459 failed low:

LI459A, pressurizer level channel I, indicates low Letdown isolates Pressurizer low level heater cutoff PRZR LVL LO (5B-3.6)

PRZR LVL DEV LO (5C-1.2)

Informs SRO Refers to ABN-706, Pressurizer Level Instrumentation Malfunction, and directs operators Stops load decrease and Assists as directed Transfers LS-459D, PRZR LVL CTRL CHAN SELECT, to an operable alternate control channel Verifies automatic control restoring pressurizer level to program Verifies instruments on common instrument line - NORMAL Ensures LS-4590E, LR-459 PRZR LVL SELECT selected to a valid channel Directs I&C to place bistable BS-1, Cab 01, Frame 08, Card 47, test switch in TEST and verify channel test status light ON

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 1 Event No: 2 Page 2 of 3 Event

Description:

Pressurizer level transmitter LT-459 fails low Time RO BOP SRO Applicant's Actions or Behavior Verifies trip status panel TSLB-5 indicator 1.1 ON and Notes verification in Unit Log Restores letdown:

Ensures charging flow through regenerative heat exchanger Opens LCV-459 and LCV-460, letdown isolation valves Takes manual control of PK-131, LTDN HX OUT PRESS CTRL, and opens the valve to 30% demand Opens the desired orifice isolation valve Adjusts PK-131, LTDN HX OUT PRESS CTRL, to obtain approximately 310 psig on PI-131, LTDN HX OUT PRESS, then places in automatic Adjusts TK-130, LTDN HX OUT TEMP CTRL to obtain approximately 95°F on TI 130, LTDN HX OUT TEMP, then places in automatic Recloses pressurizer heater group C feeder breaker by placing PRZR CTRL HTR GROUP C control switch in the ON position

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 1 Event No: 2 Page 3 of 3 Event

Description:

Pressurizer level transmitter LT-459 fails low Time RO BOP SRO Applicant's Actions or Behavior Refers to Technical Specifications:

Reactor Trip Instrumentation T. S. Table 3.3-1 Item No. 11 Accident Monitoring T. S. Table 3.3-6 Item No. 5 Initiates repairs per STA-606 Initiates a ONE Form per STA-421 as applicable

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 1 Event No: 3 Page 1 of 1 Event

Description:

1. 1 Main Turbine control valve fails closed Time RO BOP SRO Applicant's Actions or Behavior Determines turbine/reactor power change - informs SRO Ensure rod control and steam dumps maintain RCS temperature Determines turbine control valve closed Directs and Implements ABN-401:

1. Verifies S/G level control, PRZR level control, and PRZR pressure control working correctly

2. Verify turbine load stable and match LOAD REFERENCE indication with existing load

3. Reduce turbine load until all operable HP control valves indicate <100% open

4. Check status of ALL main turbine stop and control valves Notify PSO, plant management, and prompt team Note for simulator operator - If asked, as PEO, report no apparent reason for #1 CV closure

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 1 Event No: 4 Page 1 of 1 Event

Description:

Loss of 1D3 Bus Time RO BOP SRO Applicant's Actions or Behavior Performs actions of ALM-0102 After performing a board walkdown, observes that 1D3 voltage is pegged low (1-CB-11) and announces loss of 1D3 bus (this can be difficult to identify - will require some good analysis)

Send PEO to equipment to check Determines that RCPs can not be tripped from control room Refers to T/S 3.3.1

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 1 Event No: 5 Page 1 of 1 Event

Description:

High Vibration on RCP 1-04 (shaft)

Time RO BOP SRO Applicant's Actions or Behavior Directs and Implements ABN-101 Trip the reactor due to high rate of RCP vibration increase. Make plant announcement Go to EOP-0.0A Stop RCP 1 locally (call to have AO open breaker)

Note: Trip the reactor due to high RCP vibration - preventing a challenge to plant safety and a degradation of any barrier to fission product release (App D, Step D.1.a)

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 1 Event No: 6 Page 1 of 1 Event

Description:

Switchyard lighting strike - loss of offsite pwr (EDG 1-02 starts and loads)

Time RO BOP SRO Applicant's Actions or Behavior Direct and Implement ABN-601 Section 5 Check 6.9 KV safeguard buses energized (Train B)

Check 6.9 KV non-safeguard buses energized Check Blackout Sequencer Check switchyard buses - will be de-energized Perform Attachment 20 Refer to EPP-201 -> classify as NOUE Verify numerous transformer/switchyard status Re-energize various buses (next event before this can be completed)

Shift briefing, various announcements, contact distribution, and contact Prompt team Note to Simulator Operator: Call RO and report lighting strike in switchyard and high winds. Load Met Tower with wind speed of 105 mph (sustained)

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 1 Event No: 7 Page 1 of 2 Event

Description:

EDG 1-02 trips on overspeed -> Loss of all power Time RO BOP SRO Applicant's Actions or Behavior Direct and Implement ECA-0.0A Verify Rx trip Verify turbine trip Check RCS isolated Verify AFW flow > 460 gpm Power can not be restored to AC safeguards bus - go to ABN-601, Step 6 Initiate DC bus load shedding - Control Room calls and has someone begin to load shed - local actions Depressurize intact SGs to 270 psig Send PEO to check on EDG trip (trip on overspeed)

Direct and Implement ABN-601 Start the DG per Attachment 1- EDG restarted AFTER SG depressurization started

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 1 Event No: 7 Page 2 of 2 Event

Description:

EDG 1-02 trips on overspeed -> Loss of all power Time RO BOP SRO Applicant's Actions or Behavior Transition back to ECA-0.0A After SG pressures have been stabilized - end of scenario (based on Chief Examiner)

Note: Depressurize intact SGs > Reduce temp and press of RCS to reduce RCP seal leakage and minimize RCS inventory loss (no way to makeup). (preventing a challenge to plant safety (App D, Step D.1.a))

• BOLD INDICATES CRITICAL STEP

JPMS2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure System: Containment Cooling Systems JTA Task #: CPSES BANK: RO1703 Task

Title:

Restore Containment Cooling KSA Ref: SF5.022.A4.01 PEO: RO: 3.6 SRO: 3.6 Operator=s Name:

Performance Environment: PLANT CONTROL ROOM SIMULATOR Performance Method: PERFORMED SIMULATED DISCUSSED Time to complete JPM: Estimated 20 min. Actual The operator=s performance was evaluated against the standards contained in this JPM and was determined to be:

SATISFACTORY UNSATISFACTORY Reason, if unsatisfactory:

Evaluator=s Signature: Date:

Comments (list all steps not satisfactorily completed):

References:

Tools, Equipment, Job Aids, etc:

EOP-0.0A, AReactor Trip or Safety Injection@, Load an at Power IC, enter malfunction RP14A &

SOP-814, AVentilation Chilled Water System@, RP14B then delete malfunction, wait two minutes, reset SI, sequencer and phase A. Enter EDR33 & EDR 36 to CLOSE, ensure all pipe penetration fans off with green Page 1 of 7 Rev Date: 1/04/00

JPMS2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure flags.

Page 2 of 7 Rev Date: 1/04/00

JPMS2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure Safety Considerations:

If this JPM is to be performed in the plant/control room, the candidate is NOT to manipulate any plant components unless he/she has permission from the Shift/Unit Supervisor.

Comments:

Cues for indications and controls need not be given if this JPM is performed on an operating simulator.

Instructions:

Make or simulate all written and/or oral reports as if the evolution is actually being performed.

You are expected to discuss the steps that you would take to include an identification of what switches/indications you would use.

Initiating Cue:

Unit 1 is recovering from a Safety Injection. The Unit Supervisor has directed you to restore Containment Cooling to service per EOP-0.0A, Attachment 9, step 4. SI has been reset and power restored to all MCCs. CCW non-safeguards loop is aligned. HVAC Centrifugal Chillers X-03 and X-04 are unavailable. Containment Phase A isolation has been reset.

Terminating Conditions:

Terminate, once at least one Reactor Coolant Pipe Penetration Ventilation Fan is started.

Page 3 of 7 Rev Date: 1/04/00

JPMS2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT 1 Ensure 1-HS-4650, VENT Operator visually CUE: If asked CHLR CCW SPLY & RET LV verifies BHS_4650 to inform operator:

is open. be open by red light Vent Chillers X-indication on the 05 & X-06 have CUE: 1-HS-4650 handswitch handswitch at CB-3. CW aligned from indication is red. The chilled Unit 1 water containment isolation valves were closed on Phase A isolation signal.

• 2 Open 1-HS-6082, CH WTR Take handswitch 1-HS- Steps 2 through 4 RET ISOL VLV. 6082 to the open may be done in position and verify red any order.

CUE: 1-HS-6082 handswitch light indication on the indication is red. handswitch on CB-3

• 3 Open 1-HS_6083 CH WTR Take handswitch 1-HS-RET ISOL VLV. 6083 to the open position and verify red CUE: 1-HS-6083 handswitch light indication on the indication is red. handswitch on CB-3.

• 4 Open 1-HS-6084, CH WTR Take handswitch 1-SPLY ISOL VLV. HS_6084 to the open position and verify red CUE: 1-hs-6084 light indication on the HANDSWITCH INDICATION handswitch on CB-3.

IS RED. All chilled water Recirc pumps are tripped.

5 Ensure CH WTR RECIRC Take handswitch X- Steps 5 and 6 may PMP 1 OR 3 running. HS-6055 (pump 1) or be done in any X-HS-6057 (pump 3) to order.

CUE: Depending on which the start position and pump was started: X-HS-6055 verify red light or X-HS-6057 handswitch indication on the indication is red. X-FI-6073 handswitch. Flow may indicates 150 gpm. be verified on X-FI-6073.

6 Ensure CH WTR RECIRC Take handswitch X-PMP 2 OR 4 running. HS-6056 (pump 2) or X-HS-6058 (pump 4) to Page 4 of 7 Rev Date: 1/04/00

JPMS2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure STEP#

• Critical SAT/

ELEMENT STANDARD NOTES UNSAT CUE: Depending on which the start position and pump was started: X-HS-6056 verify red light or X-HS-6058 handswitch indication on the indication is red. X-FI-6073 handswitch. Flow may indicates 2500 gpm. be verified on X-FI-6073.

7 Place the remaining two CH Take handswitches for Pumps in this step WTR RECIRC PMPS to the chiller pumps not may be operated AUTO After Stop Position. started to the AUTO in any order.

After Stop Position CUE: Depending on which X-HS-6055 NOTE: If PEO pumps were taken to AUTO X-HS-6056 asked status of After Stop: X-HS-6057 CW Booster X-HS-6055 X-HS-6058 Pumps, report X-HS-6056 Verify green light pumps X-12 & X-X-HS-6057 indication on the 13 running X-HS-6058 handswitch.

Handswitch indication is green.

8 Dispatch PEO to start HVAC Operator uses radio or Note: May only CENTRIFUGAL WATER Gaitronics to dispatch start one chiller.

CHILLER X-01 and X-02. PEO to start HVAC CENTRIFUGAL CUE: HVAC chillers X-01 CHILLERS X-01 and and X-02 are running. X-02.

• 9 Start CNTMT FN CLR FN1. Take handswitch 1-HS- Note: Only 3 5405A to the start CNTMT Fan CUE: 1-HS-5405A position and verify red coolers need be handswitch indication is red. light indication on the started. May be handswitch done in any order.

• 10 Start CNTMT FN CLR 2. Take handswitch 1-HS-5409A to the start CUE: 1-HS-5409A position and verify red handswitch indication is red. light indication on the handswitch.

• 11 Start CNTMT FN CLR FN3. Take handswitch 1-HS-5413A to the start Page 5 of 7 Rev Date: 1/04/00

JPMS2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure CUE: 1-HS-5413A position and verify red handswitch indication is red. light indication on the handswitch.

• 12 Start CNTMT FN CLR FN 4. Take handswitch 1-HS-5417A to the start CUE: 1-HS-5417A position and verify red handswitch indication is red. light indication on the handswitch.

• 13 Start CRDM VENT FN 1. Take handswitch 1-HS- Note: Only 1 5421 to the start CRDM Vent Fan CUE: 1-HS-5421 handswitch position and verify red need be started.

indication is red. light indication on the handswitch.

• 14 Start CRDM VENT FN 2. Take handswitch 1-HS-5423 to the start CUE: 1-HS-5423 handswitch position and verify red indication is red. light indication on the handswitch.

• 15 Start NEUT DET WELL FN Take handswitch 1-HS- Note: Only 1 CLR FN 9 & DMPR 5435 to the start neutron detector position and verify red well fan cooler CUE: 1-HS-5435 handswitch light indication on the need be started.

indication is red. handswitch.

• 16 Start NEUT DET WELL FN Take handswitch 1-HS-CLR FN 10 & DMPR. 5440 to the start position and verify red CUE: 1-HS-5440 handswitch light indication on the indication is red. handswitch.

• 17 Start RC PIPE PENET AREA Take handswitch 1-HS- Note: Must start VENT FN 1. 5461 to the start 1 or 2 Vent Fan position and verify red CUE: 1-HS-5461 handswitch light indication on the indication is red. handswitch.

• 18 Start RC PIPE PENET AREA Take handswitch 1-HS- Note: Must start VENT FN 2. 5463 to the start 1 or 2 Vent Fan position and verify red CUE: 1-HS-5463 handswitch light indication on the indication is red. handswitch

• 19 Start RC PIPE PENET AREA Take handswitch 1-HS- Note: Must start VENT FN 3. 5465 to the start 3 or 4 Vent Fan position and verify red Page 6 of 7 Rev Date: 1/04/00

JPMS2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure CUE: 1-HS-5465 handswitch light indication on the indication is red. handswitch

• 20 Start RC PIPE PENET AREA Take handswitch 1-HS- Note: Must start VENT FN 4. 5467 to the start 1 or 2 Vent Fan position and verify red CUE: 1-HS-5467 handswitch light indication on the indication is red. handswitch TASK COMPLETE Page 7 of 7 Rev Date: 1/04/00

JPMS2 Comanche Peak Steam Electric Station ILE-11/2002 Job Performance Measure INITIATING CUE: Unit 1 is recovering from a Safety Injection. The Unit Supervisor has directed you to restore Containment Cooling to service per EOP-0.0A, Attachment 9, step 4. SI has been reset and power restored to all MCCs. CCW non-safeguards loop is aligned. HVAC Centrifugal Chillers X-03 and X-04 are unavailable. Containment Phase A isolation has been reset.

Page 8 of 7 Rev Date: 1/04/00

Appendix D Scenario Outline Form ES-D-1 Facility: CPSES Scenario No.: 3 Op-Test No.: 11/2002 Examiners: Howard Bundy Operators:

Mike Murphy Tom Stetka Fred Sanchez Note: (BANK) This scenario is an unused spare from the 2001 CPSES exam Initial Conditions: 50% power and steady.

Turnover: No equipment is out of service. Train A equipment is in service. FWP repairs have been completed by the previous shift. You have been directed to return to 100%

power @8%/hr not to exceed 10%/hr.

Event Malf. Event Event No. No. Type* Description 1 N (SRO) Increase Reactor power back to 100%

T=0 N (BOP)

R (RO) 2** MS13A I (RO) MSL 1 Press Instrument PI-2325 fails high (100%)

T=15 I (SRO) 3 FW16 C (RO) Lowering vacuum on main condenser due to loss of vacuum T=22 C (BOP)

C (SRO) breaker water seal (6% severity) 4 RX15A C (RO) Pzr spray flow control valve failure (PCV-455B) @ 60%

T=32 C (SRO) severity. RXR96 is PCV-455B CTRL driver card - remove then delete malfunction 5 TC06C M (ALL) Main turbine spurious trip and MSIV #1 closes causing SG1 T=45 MS07A MS10A1 Safety MS-021 to fail open

@100%

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

• • Note - Initiate after Chief Examiner determines power increase is sufficient

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 3 Event No: 1 Page 1 of 1 Event

Description:

Increase Rx Power - approx 8%/hr Time RO BOP SRO Applicant's Actions or Behavior Increase reactor power per IPO-003A Provide shift briefing Calc amount of dilution needed to raise power to 1145 Mwe (Rx Eng data)

Initiate dilution and outward rod motion Set desired loading rate on the LOAD GRADIENT device Raise the LIMIT LOAD device to >1180 MW Raise the LOAD REFERENCE device to increase turbine load Verify proper rod bank insertion, overlap, and sequencing

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 3 Event No: 2 Page 1 of 1 Event

Description:

MSL #1 Press Instrument (PI-2325) Fails High Time RO BOP SRO Applicant's Actions or Behavior Refers to ALM-0064A and diagnosis ARV open by control board indications Directs and Implements ABN-709, Section 2.0 Determines PI-2325 failed high and ZL-2325 indicates valve open Ensures SG 1 press <1125 psig and manually closes ARV Notifies Chemistry to determine if release permit is required Contacts Prompt Team and initiates repairs

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 3 Event No: 3 Page 1 of 1 Event

Description:

Main Condenser Air In-leakage Time RO BOP SRO Applicant's Actions or Behavior Determines Condenser Vacuum Lowering Directs Actions of ABN-304, Section 3.0 Starts all available condenser vacuum pumps Notifies Shift Manager and Load Dispatcher of imminent load reduction Reduces turbine load as necessary per IPO-3A Notifies Chemistry of excessive air in-leakage Dispatches personnel to check for leaks Note to Simulator Operator: 2 minutes after being dispatched as PEO to check for leakage paths, remove Malf FW16 and report back that main condenser vacuum breaker loop seal was empty and has been refilled Stop unnecessary CEVs per SOP-309 Critical Task - Turbine/Rx trip does not occur on low condenser vacuum.

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 3 Event No: 4 Page 1 of 1 Event

Description:

PZR Spray Valve PCV-455 fails to 60% open Time RO BOP SRO Applicant's Actions or Behavior Determines PRZR Spray Valve RC Loop 1 is open Directs Actions of ABN-705, Section 3 Attempts to close Spray Valve PK-455B Initiate load reduction to 40% per IPO-3A Ensures all PRZR heaters are on Directs I&C to de-energize Spray Valve PCV-455B by removing 1-PCY-0455B Driver Card Note to Simulator Operator: After 1 minute, using remote function RXR96, remove/pull PCV-455B Ctrl Drive Card and remove malfunction RX15A. Report back to control room that card has been removed.

Check PRZR pressure trending to normal Contact Plant Management and initiate repairs Critical Task -> Rx does not trip on low press

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 3 Event No: 5 Page 1 of 2 Event

Description:

Turbine Spurious trip, MSIV #1 closure, Stm Line Safety Valve 1MS-0021 fails open Time RO BOP SRO Applicant's Actions or Behavior Determines #1 MSIV closed and STM Safety is failed open Trips the reactor Directs and implements EOP-0.0 Verifies Rx trip and bypass brks open, all rod bottom lights on, neutron flux decreasing, and turbine tripped Verifies power to AC SFGD buses Verifies SI actuated or is required Determines SG1 is FAULTED and transitions to EOP-2.0 Directs and Implements EOP-2.0 Closes all MSIVs and checks bypasses closed Isolates #1 S/G including #1 MSL supply to TDAFWP Checks for SGTR by verifying Secondary Rad levels --

normal

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 3 Event No: 5 Page 2 of 2 Event

Description:

Turbine Spurious trip, MSIV #1 closure, Stm Line Safety Valve 1MS-0021 fails open Time RO BOP SRO Applicant's Actions or Behavior Transitions to EOP-1.0 Directs and Implements EOP-1.0 Check if RCPs should be stopped Check for faulted S/Gs Check intact S/G levels and Secondary Rad levels Transition to EOS-1.1 Terminate scenario when Crew transitions to EOS-1.1 or at the discretion of the Chief Examiner

• BOLD INDICATES CRITICAL STEP

Appendix D Scenario Outline Form ES-D-1 Facility: CPSES Scenario No.: 4 Op-Test No.: 11/2002 Examiners: Howard Bundy Operators:

Mike Murphy Tom Stetka Fred Sanchez Note: (NEW)

Initial Conditions: 20% Turbine Load at BOL Turnover: Plant Startup in Progress following a routine refueling outage. No equipment is out of service. IPO-003A, Power Operations is complete through step 5.3.9.

Starting at step 5.4, Establishing 100% Turbine Load, continue the plant startup in accordance with IPO-003A.

Event Malf. Event Event No. No. Type* Description 1 R (RO) Increase turbine load in accordance with IPO003A, Power T=0 N (BOP)

N (SRO)

Operations When operator starts dilution, insert malfunction CV16A 2 CV16A I (RO) LT-112 Fails within the auto makeup range T=15 I (SRO) 3 RC03C C (RO) RCP 3 shaft high vibration T=25 C (SRO) 4 RC09C2 M (ALL) Reactor coolant system loop #3 cold leg rupture (double ended T=35 shear) 5 C (ALL) Rx will not trip in manual or automatic. Go to FRS-0.1A, T=35 Response to Nuclear Power Generation/ATWT 6 SI04B C (RO) Train B SI Pump failure T=35

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Preload Information T=0:

! RP01 Auto Rx trip failure

! RP15E Rx trip breakers jammed closed

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 4 Event No: 1 Page 1 of 1 Event

Description:

Increase turbine load in accordance with IPO-003A, Power Operation Time RO BOP SRO Applicant's Actions or Behavior Review IPO-003A, Power Operation Contacts chemistry to verify SG and secondary chemistry parameters Notifies the Dispatcher of intent to increase turbine load Verifies:

PCIP, 1.2, IR TRN A RX TRIP BLK is on PCIP, 2.2, IR TRN B RX TRIP BLK is on PCIP, 3.2, PR TRN A LO SETPT TRIP BLK is on PCIP, 4.2, PR TRN B LO SETPT TRIP BLK is on Calculates amount of dilution required Sets in the desired loading rate on the LOAD GRADIENT device Initiates RCS dilution Maintains Axial Flux Difference within the band Rases the LIMIT LOAD device to 400 MW Raises the LOAD REFERENCE device to 350 MW in incremental steps

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 4 Event No: 2 Page 1 of 1 Event

Description:

VCT Level Transmitter LT-112 Fails in the Auto Makeup Range Time RO BOP SRO Applicant's Actions or Behavior Recognizes indication of LT-112 failure:

Auto makeup start and does not stop VCT level increasing VCT LVL LO annunciator VCT LVL LO-LO annunciator Informs SRO Refers to or directs operators to ALM-0061A 3.5 or 4.5, VCT Level LO, VCT LVL LO-LO Monitors VCT on LI-112A and LI-185.

Places 1/1-MU, RCS MU MAN ACT, in STOP Reduce VCT level by positioning 1/1-LCV-112A, VCT LVL CTRL VLV to HUT Verify 1-LK-112C, VCT LVL CTRL, potentiometer setpoint is correct per TDM-203A Verify 1-PI-115, VCT PRESS, is approximately 30 psig Ensure 1-LI-185, VCT LVL, and 1-PI-115, VCT PRESS, are decreasing Refers to ABN-105, Chemical and Volume Control System Malfunction, and directs operators

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 4 Event No: 3 Page 1 of 1 Event

Description:

RCP #3 shaft high vibration Time RO BOP SRO Applicant's Actions or Behavior Recognizes indications that #3 RCP shaft vibration is high Refers to ABN-101, Reactor Coolant Pump Trip/Malfunction and directs the operators Stops load change if in progress Determines that #3 RCP shaft vibration is 18 mils, Frame vibration 3 mils and steady NOTE: If consulted by SRO, Shift Manager and Duty Manager will advise to secure the affected pump and shutdown the plant.

Stops RCP #3 Stabilizes the secondary plant Directs shutdown per IPO - 003A/004A Notifies Load Dispatcher of power reduction NOTE: Manual and automatic RX trip functions are not functional.

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 4 Event No: 4/5 Page 1 of 4 Event

Description:

Reactor coolant system loop #3 cold leg rupture (double ended guillotine shear) and ATWT (SI Pump B failure)

Time RO BOP SRO Applicant's Actions or Behavior Recognize indications of loop #3 cold leg rupture:

Safety Injection Pressurizer pressure decreasing Pressurizer level low Containment pressure and humidity increasing Transitions to EOP-0.0A, Reactor Trip or Safety Injection, Step 1 and directs operators Recognize RX failed to trip and inform SRO Attempt to manually trip reactor from both trip switches Transitions to FRS-0.1A, Response to Nuclear Power Generation/ATWT, Step 1, and directs operators Verifies control rods inserting at greater than 48 steps per minute OR manually insert control rods Manually trips turbine Verifies total AFW flow is greater than 860 gpm

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 4 Event No: 4/5 Page 2 of 4 Event

Description:

Reactor coolant system loop #3 cold leg rupture (double ended guillotine shear) and ATWT (SI Pump B failure)

Time RO BOP SRO Applicant's Actions or Behavior Performs IMMEDIATE ACTION to initiate Emergency Boration of RCS:

Ensures at least one CCP running Verifies charging flow is greater that 30 gpm Starts available boric acid pump Opens Emergency Boration valve 1-8104 Verifies emergency boration flow Checks PRZR pressure less than 2335 psig Dispatch an operator to locally trip the reactor NOTE: steps 1-14 of EOP-0.0A, Reactor Trip or Safety Injection, should be accomplished concurrent with FRS-0.1A Verify Containment Ventilation Isolation Verify reactor subcritical Verify CST Levels Check SG level Ensure all dilution paths isolated Check for reactivity insertion from uncontrolled cooldown

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 4 Event No: 4/5 Page 3 of 4 Event

Description:

Reactor coolant system loop #3 cold leg rupture (double ended guillotine shear) and ATWT (SI Pump B failure)

Time RO BOP SRO Applicant's Actions or Behavior Check MSIVs and bypass valves closed Direct steps 1-14 of EOP-0.0A, Reactor Trip or Safety Injection, concurrent with FRS-0.1A Verify power to Safeguards buses Verify both trains of SI actuated Verify SSW pumps - RUNNING Recognize Train B SI Pump failed to start Send AO to attempt manual start of SI pump When AO reports pump coupling broke (7 minutes after being sent), secure pump - pull to lock Verify CIS Phase A Verify CVIS actuation Verify CS initiated Verify CCW pumps running Verify RHR pumps running Verify CVCS proper alignment Verify Feedwater Isolation

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 4 Event No: 4/5 Page 4 of 4 Event

Description:

Reactor coolant system loop #3 cold leg rupture (double ended guillotine shear) and ATWT (SI Pump B failure)

Time RO BOP SRO Applicant's Actions or Behavior Verify AFW Alignment Verify ECCS Flow

• BOLD INDICATES CRITICAL STEP

Appendix D Scenario Outline Form ES-D-1 Facility: CPSES Scenario No.: 5 Op-Test No.: 11/2002 Examiners: Howard Bundy Operators:

Mike Murphy Tom Stetka Fred Sanchez Note: (BANK) This Scenario is an unused backup from the 1999 CPSES Exam Initial Conditions: Full power steady state; BOL; Equilibrium Xenon (I/C Info: EG06, DG1 Out of Service.)

Turnover: The plant has been at 100% power for the last 15 days. Diesel Generator 1 is out of service for injector replacement; Diesel Generator 1 should be returned to service in about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Shift order directs you to shift CCPs to add oil to CCP1-01.

Event Malf. Event Event No. No. Type* Description 1 N (RO) SWAP Charging Pumps T=0 N (SRO) 2 I (BOP) Steam Generator Pressure Transmitter PT-2325 fails high T=10 I (SRO)

[Value = 100]

3 C (BOP) Heater drain pump 1-02 trips/auto turbine runback.

T=20 C (SRO)

R (RO)

Annunciator ALB-9A Window 8.2 4 M (ALL) Loss of all off-site power.

T=32 Mechanical failure causes spurious trip of diesel generator 2 breaker [Initiate 5 minutes after diesel starts] [Return diesel generator to service 15 minutes after the reactor trip]

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 5 Event No: 1 Page 1 of 1 Event

Description:

Swap centrifigal charging pumps Time RO BOP SRO Applicant's Actions or Behavior Directs operator to place 1-02 ccp in service and secure ccp 1-01 per SOP Ensures breaker is racked in.

Ensures 1/1-8110, 1/1-8111, 1-ZL-8220, 1-ZL-8221 are open Contacts PEO to start 1-02 ccp aux oil pump.

Starts ccp 1-02.

Controls PZR level Secures ccp1-01 per SOP-103A, 5.3.4 Contacts PEO to secure 1-01 ccp aux oil pump

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 5 Event No: 2 Page 1 of 1 Event

Description:

Steam Generator No. 1 pressure transmitter PT-2325 fails high Time RO BOP SRO Applicant's Actions or Behavior Recognizes indication that PT-2325 failed high:

SG 1 Atmospheric Relief Valve opens Tave decreasing Informs SRO Refers to ABN-709, Steam Line, Steam Header & 1st Stage Pressure

& Feed Header Pressure Instrument Malfunction, and directs operators Assists as directed Verifies SG atmospheric relief is NOT closed Take manual control of relief valve and close valve Adjusts to within 1 degree of Tref Initiates repair and informs management

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 5 Event No: 3 Page 1 of 1 Event

Description:

PV-2610, heater drain pump 1-02 water injection pressure control valve fails closed Time RO BOP SRO Applicant's Actions or Behavior Recognizes indication that PV-2610 failed closed:

HDP 2 SEAL WTR PRESS LO (8.2 illuminated)

Informs SRO Assists as directed Refer to ALM-0091A 8.2, HDP SEAL WTR PRESS LO, and direct operators:

Dispatch an operator to TB 755 to determine cause of alarm Ensure instrument air is aligned to PC-2610 (TBO performs)

Verify HD-0312, HTR DRN PMP 1-01/1-02 SL WTR IN ISOL VLV is open (TBO perform)

Directs operator to reduce turbine power to <70% per IPO-003A Shutdown HDP 1-02 per SOP-308A for Shutdown

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 5 Event No: 4 Page 1 of 2 Event

Description:

Loss of All AC Power Time RO BOP SRO Applicant's Actions or Behavior Enters EOP-0.0A, Reactor Trip or Safety Injection, and directs operators Verify reactor trip Verify turbine trip Verify power to AC safeguards busses Check if SI is actuated Reports loss of off-site power Reports only 1 AC safeguards bus is energized Following Safety Injection remain in EOP-0.0A and directs operators Recognize loss of all AC (diesel generator 2 output breaker trips 5 minutes after the diesel starts)

Transitions to ECA-0.0A, Loss of All AC Power, and directs operators Check if RCS is isolated

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 5 Event No: 4 Page 2 of 2 Event

Description:

Loss of All AC Power Time RO BOP SRO Applicant's Actions or Behavior Verify AFW flow - Greater than 460 gpm Closes diesel generator 2 output breaker When diesel generator 1 is restored to service (15 minutes after reactor trip) restore power to an AC Safeguards Bus Transitions to ECA-0.0A, Loss of All AC Power, step 24, when power is restored to an AC Safeguards Bus and directs operators Transitions to ECA-0.1A, Loss of All AC Power Recovery Without SI Required, or ECA-0.2A, Loss of All AC Power Recovery With SI Required, and direct opertors

• BOLD INDICATES CRITICAL STEP

Appendix D Scenario Outline Form ES-D-1 Facility: CPSES Scenario No.: 6(SPARE) Op-Test No.: 11/2002 Examiners: Howard Bundy Operators:

Mike Murphy Tom Stetka Fred Sanchez Note: (NEW)

Initial Conditions: 50% Turbine Load at EOL (IC20; MS08B; MSIV 2 fails to close; Need to update operator aid to 25 psig in VCT)

Turnover: Plant startup in progress following a routine refueling outage. No equipment is out of service. IPO-003A, Power Operations, is complete through step 5.4.22.

Starting at step 5.4.23, Establishing 100% Turbine Load, continue the plant startup in accordance with IPO-003A. Control Bank D at 170 steps, 517 MWE, 1554 ppm RCS boron Conc., Xenon at equilibrium conditions, Target power change ramp rate of 8%, MAX ramp rate of 10%.

Event Malf. Event Event No. No. Type* Description 1 R (RO) Increase turbine load in accordance with IPO-003A, Power T=0 N (BOP)

N (SRO)

Operation Note: Examiner must initiate Event 2 2 CV15 C (SRO) PCV-131, Letdown Pressure Control Valve fails closed.

T=15 C (RO) 3 IA01A C (ALL) Instrument air leak - IA Receiver 1-01 relief valve lifting T=23 (Severity = 1500 scfm leak) 4 RP06A I (SRO) Loop 1 N16 fails high (Start Event 5 prior to RO/BOP T=30 I (RO) placing bistables in trip) 5 RD01D C (RO) Control bank continuous rod withdrawal (Control Bank D)

T=46 C (SRO) 6 MS02 M (ALL) Main steam line leak outside containment downstream of SG 2 MS08B MSIV; SG 2 MSIV, HV-2334A, fails to close. (Insert at 1.13 x 10E7 lbm/hour) EXAMINER NOTE: INSERT AFTER TRANSITION TO EOS-0.1A.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 6 Event No: 1 Page 1 of 1 Event

Description:

Increase turbine load in accordance with IPO-003A, Power Operations Time RO BOP SRO Applicant's Actions or Behavior Review IPO-003A, Power Operations Briefs Crew on power change Calculates amount of dilution required Initiates RCS dilution Sets in the desired loading rate on the LOAD GRADIENT device Raises the LIMIT LOAD device to1100 MW.

Raises the LOAD REFERENCE device to 1050 MW in incremental steps Maintains Axial Flux Difference within the band

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 6 Event No: 2 Page 1 of 1 Event

Description:

PCV-131, LTDN Press Ctrl Valve, fails closed Time RO BOP SRO Applicant's Actions or Behavior Refer to ALM-0061A Letdown press > 310 psig, isolates letdown -> closes 1/1-8149A, 1/1-8149B, and 1/1-8149C and transitions to ABN-105 Directs and Implements Procedure ABN-105, Section 5.0 Establishes excess letdown Simultaneously lower 1-FK-121 to 32 gpm and adjust 1-HC-182 to 6 to 13 gpm Align excess letdown per SOP-103A Contacts the Prompt Team to repair PCV-131 and notifies Ops Managment Note to Sim Oper: When called as PEO to open LCS-8409-RO, U1 Ltdn Hx Out Press Ctrl Vlv Byp Remote Oper, report that the valve is stuck shut and CANNOT be opened

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 6 Event No: 3 Page 1 of 1 Event

Description:

Instrument Air leak due to IA Receiver 1-01 relief valve lifting Time RO BOP SRO Applicant's Actions or Behavior Determines IA system has a leak by acknowledging alarm and observing plant parameters Directs and Implements Procedure ABN-301 Verifies both IA compressors are running Determines IA press < 85psig Starts and aligns a common IA compressor Stops unnecessary use of IA Sends PEO to determine cause of low IA press (PEO finds IA Receiver 1-01 relief valve lifting - able to reset the valve)

Checks equipment on main control board for proper operation Contacts Prompt Team and informs Ops Managment

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 6 Event No: 4 Page 1 of 1 Event

Description:

Loop 1 N16 fails high Time RO BOP SRO Applicant's Actions or Behavior Directs and Implements Procedure ABN-704 Place control rods in manual and ensure T ave is within 1oF of T ref Select the failed channel on 1/1-JS-411E, CHAN DEFEAT Within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> have I&C place bistable test switches for failed channel in the CLOSED position Refer to T/S 3.3.1 Contacts Prompt Team and Ops Management

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 6 Event No: 5 Page 1 of 1 Event

Description:

Control Bank Continuous Rod Withdrawal Time RO BOP SRO Applicant's Actions or Behavior Recognizes indications of control bank continuous withdrawal:

Rods stepping out when not required Tavg increasing Pressurizer pressure increasing Pressurizer level increasing Informs SRO Refers to ABN-712, Rod Control System Malfunction, and directs operators Places rod control in manual and Reports rods continue to step out Directs operator to trip the reactor and perform the immediate actions of EOP-0.0A, Reactor Trip or Safety Injection, and directs operators Verify Reactor Trip Verify Turbine Trip Verify Power to AC Safeguards Busses Check if SI is Actuated Transitions to EOS-0.1A, Reactor Trip Response and directs operators

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 6 Event No: 6 Page 1 of 3 Event

Description:

Main Steam line break outside containment downstream of SG 2 MSIV, HV-2334A, which fails to close Time RO BOP SRO Applicant's Actions or Behavior Recognize indications of main steam line break outside containment:

MSIVs on 1, 3 and 4 SGs close Safety Injection Steam line pressure decreasing Containment pressure and humidity indicates normal Transitions back to EOP-0.0A, Reactor Trip or Safety Injection, Step 1 and directs operators Verify Reactor Trip Verify Turbine Trip Verify Power to AC Safeguards Bussed Verify both trains of SI actuated Verify SSW pumps - RUNNING Verify SI Pumps running Verify CIS Phase A Verify CVIS actuation Verify CS initiated Verify CCW pumps running Verify RHR pumps running Verify CVCS proper alignment Verify Feedwater Isolation

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 6 Event No: 6 Page 2 of 3 Event

Description:

Main Steam line break outside containment downstream of SG 2 MSIV, HV-2334A, which fails to close Time RO BOP SRO Applicant's Actions or Behavior Check if MS lines should be isolated Verify AFW Alignment Verify ECCS Flow Verify EDG status Check RCS Tave at or tending to 557 Check PZR valve status Check if RCPs should be stopped At step 22, Check if any SG is faulted, transitions to EOP-2.0A, Faulted SG Isolation, and directs operators Attempts to manually close SG 2 MSIV - dispatches operators to locally close SG 2 MSIV Directs operators in isolation of SG 2

• BOLD INDICATES CRITICAL STEP

Appendix D Operator Form ES-D-2 Op-Test No: 11/2002 Scenario No: 6 Event No: 6 Page 3 of 3 Event

Description:

Main Steam line break outside containment downstream of SG 2 MSIV, HV-2334A, which fails to close Time RO BOP SRO Applicant's Actions or Behavior Isolates SG 2 main feedline Isolates AFW flow to SG 2 Isolates SG 2 blowdown and sample lines Ensures SG 2 atmospherics closed Ensures SG 2 main steamline drip pot isolation valve closed At Step 8, transitions to EOP-1.0A, Loss of Reactor or Secondary Coolant, Step 1, and directs operators

• BOLD INDICATES CRITICAL STEP

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # CP1 1 Group # 1 1 K/A # 4.1.074.EA1.24 Importance Rating 3.6 3.8 Proposed Question:

The plant is responding to an inadequate core cooling condition with core exit thermocouples greater than 1200°F. From the choices below, select the choice that lists the best recovery technique in the correct priority for this condition.

A. Start ECCS, depressurize secondary, start RCP, depressurize RCS.

B. Start RCP, depressurize RCS, depressurize secondary, start ECCS.

C. Trip RCPs, trip turbine, depressurize secondary, isolate accumulators.

D. Start ECCS, depressurize RCS, trip RCPs, depressurize secondary.

Proposed Answer: A Explanation:

Technical

Reference:

FRC-0.1A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified MCO.MI3.OB105-005 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 1

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.1.074.EA1.26 Importance Rating 3.8 3.8 Proposed Question:

The flowpath of the "Cold Leg Recirculation Phase" of the ECCS is that water is delivered from the:

A. RWST to the RCS cold legs.

B. Containment sumps to the RCS cold legs.

C. Containment sumps to the RCS hot legs.

D. RWST to the RCS hot legs.

Proposed Answer: B Explanation:

Technical

Reference:

EOS-1.3A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.SI1.OB900 -

061 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 2

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.005.AA1.05 Importance Rating 3.4 3.4 Proposed Question:

During a Reactor startup with Control Bank D at 20 steps and the Reactor subcritical, the DRPI ROD DEV annunciator is received. The Reactor Operator observes that Control Bank B rod F2 indicates 210 steps while Control Bank B Group 1 step counter indicates 228 steps. No other alarms are received and all other parameters indicate normal. This event would require the crew to:

A. Consider the rod misaligned and within one hour insert all Control Banks to Control Bank Offset (CBO).

B. Consider the rod misaligned and continue rod withdrawal to reach Critical conditions then realign the rod.

C. Consider the rod misaligned and compare DRPI and Step Counter positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D. Consider the rod misaligned and implement the requirements of Technical Specifications 3.0.3.

Proposed Answer: A Explanation:

Technical

Reference:

ABN-712 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.CR1.OB15- 4 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 3

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.067.AA1.05 Importance Rating 3.0 3.1 Proposed Question:

The Control Room Ventilation System has been aligned for Control Room Recirculation due to a large fire in a field adjacent the plant. The Unit Supervisor checks the logs and realizes that the ventilation system has been in recirc for approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Which of the following statements describes the situation in the Control Room?

A. The humidity in the Control Room has dropped dangerously low due to too much time operating on recirc.

B. The carbon monoxide level in the Control Room is increasing due to too much time operating on recirc.

C. The air quality in the Control Room has been polluted by contaminants from the fire due to too much time operating on recirc.

D. The carbon dioxide level in the Control room is increasing due to too much time operating on recirc.

Proposed Answer: D Explanation:

Technical

Reference:

SOP-802 Control Room Ventilation System Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 4

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.068.AA1.14 Importance Rating 4.2 4.4 Proposed Question:

A fire in the control room with heavy smoke requires immediate evacuation of the control room. Unit 1 was at 95% power at the time the evacuation procedure was initiated. The Unit 1 Reactor Operator was only able to trip the turbine prior to exiting the control room.

Assuming that the plant responds as expected, which ONE of the following local actions needs to be taken to complete the RO's initial evacuation assignments?

A. Open the Reactor Trip Breakers.

B. Isolate the Main Steam lines.

C. Remove pressurizer PORV fuses.

D. Isolate dilution paths and S/G Process Sampling.

Proposed Answer: B Explanation:

Technical

Reference:

ABN-803A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 2703 Modified X New Question History: Last NRC Exam Prairie Island 1(WEC), 6/16/1997 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 8, 10 55.43 5 Comments:

Modifications: clarified stem, and adapted distracters to CPSES, and replaced one distracter.

RO TEST QUESTION #: 5

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.068.AA2.10 Importance Rating 4.2 4.4 Proposed Question:

A bomb threat has forced a control room evacuation. Prior to the bomb threat, the plant was operating steady at 100%. The relevant control room actions directed by ABN-905A "Loss of Control Room Habitability" were completed and plant operations have been transferred to the Remote Shutdown Panel (RSP). When the Reactor Operator arrives at the RSP, he should expect to see the following indications:

A. Neutron flux decreasing steadily and rod bottom lights on.

B. Neutron flux and rods at approximately the level they were when he left the control room.

C. Neutron flux decreasing steadily and the reactor trip breakers are open.

D. Neutron flux at approximately the level it was before he left the control room and reactor trip breakers closed.

Proposed Answer: C Explanation:

ABN-905A directs a reactor trip prior to leaving the control room, and rod bottom lights are not indicated at the RSP. The RO can observe both neutron flux decreasing, and reactor trip breakers open from the RSP.

Technical

Reference:

ABN-905A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 1, 6, 10 55.43 Comments:

RO TEST QUESTION #: 6

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.076.AA2.03 Importance Rating 2.5 3.0 Proposed Question:

Unit 1 was at 35% power during a plant shutdown when a 20% load rejection occurred. The plant has been stabilized, and the shutdown is continuing. The daily RCS chemistry sample has been analyzed and the RCS specific activity determined to be 0.1 uc/gm Dose Equivalent I-131. The previous sample had a specific activity of 0.01 uc/gm Dose Equivalent I-131. Which one of the below statements identifies the required response?

A. Be in mode 3 condition with Tave less than 500 degrees F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

B. Initiate a Safety Injection and enter EOP-0.0A.

C. Obtain and analyze a plant vent grab sample.

D. Continue with plant operations as planned, there is no required response to the stated conditions.

Proposed Answer: C Explanation:

Technical

Reference:

IPO-004A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified IPO.XO4.OB900

- 002 X New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 5 Comments:

Modifications: altered two distractors.

RO TEST QUESTION #: 7

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.076.AA2.04 Importance Rating 2.6 3.0 Proposed Question:

The Liquid Waste Processing Effluent Radiation Monitor High Radiation alarm has been received. Which of the following is the correct action for the operator to take initially?

A. Ensure X-RV-5251 is closed or close its upstream isolation valve.

B. Reopen X-RV-5251 and ensure correct pump is running.

C. Reopen X-RV-5253 and ensure correct pump is running.

D. Ensure X-RV-5253 is closed or close its upstream isolation valve.

Proposed Answer: D Explanation:

Technical

Reference:

ALM-301, ABN-903 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.WP1.OB12 -

003 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 5 Comments:

RO TEST QUESTION #: 8

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.027.G.2.4.2 Importance Rating 3.9 4.1 Proposed Question:

The following SEQUENTIAL events have just occurred:

- charging flow decreased to minimum,

- pressurized level decreased,

- letdown isolated and heaters turned off,

- pressurized level increased to high level reactor trip.

Pressurizer level control selector switch is in the LT-459 position and pressure control is on PT-455. No operator actions have been taken. Which failure has occurred?

A. Pressure Channel 455 failed high.

B. Pressure Channel 455 failed low.

C. Level channel 459 failed high.

D. Level channel 459 failed low.

Proposed Answer: C Explanation:

Technical

Reference:

LO21.RLS.IC3.LN Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified MCO.TA3.OB103

- 002 X New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Modifications: altered two of the distracters.

RO TEST QUESTION #: 9

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.1.055.EK1.02 Importance Rating 4.1 4.4 Proposed Question:

Unit 1 has just experienced a station blackout and a subsequent reactor trip. According to EOS-0.1A "Reactor Trip Response," all of the following are indications of natural circulation flow EXCEPT:

A. Steam generator pressures are stable or decreasing B. Pressurizer pressure is stable or decreasing C. Core exit thermocouple temperatures are stable or decreasing D. RCS cold leg temperatures at saturation temperature for S/G pressure Proposed Answer: B Explanation:

Technical

Reference:

EOS-0.1A Attachment 3 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 10526 Modified X New Question History: Last NRC Exam Indian Point 3 (WEC), 4/15/1996 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8, 10 55.43 Comments:

Modifications: adapted to CPSES terminology, and replaced one distracter.

RO TEST QUESTION #: 10

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.067.AK1.01 Importance Rating 2.9 3.9 Proposed Question:

While you are on shift on Saturday night, an equipment operator calls the control room and informs you that he has found a fire smoldering in an electrical panel. If available, the preferred method for fighting this type of fire is:

A. halon.

B. foam.

C. water fog/spray.

D. dry powder extinguisher.

Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 5378 Modified New Question History: Last NRC Exam Salem 1(WEC), 1/22/1996 Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8, 10 55.43 Comments:

RO TEST QUESTION #: 11

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.069.AK1.01 Importance Rating 2.6 3.1 Proposed Question:

The following plant conditions exist:

o Procedure in effect EOP-1.0B.

o Containment pressure 65 psig and increasing.

You transition to FRZ-0.1B, "Response to High Containment Pressure" and upon completion of all steps in FRZ-0.1B, you determine that containment pressure is now 61 psig. At this point, you are required to:

A. reinitiate and remain in FRZ-0.1B until the condition is no longer an ORANGE priority.

B. exit FRZ-0.1B and enter EOS-0.0B.

C. reinitiate and remain in FRZ-0.1B until the condition is no longer a RED priority.

D. exit FRZ-0.1B and return to EOP-1.0B at the step in effect.

Proposed Answer: D Explanation:

Technical

Reference:

FRZ-0.1B, and ODA-407 Guideline on Use of Porcedures Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8, 10 55.43 5 Comments:

RO TEST QUESTION #: 12

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.5.E09.EK1.02 Importance Rating 3.3 3.7 Proposed Question:

Which of the below most correctly completes the following statement regarding natural circulation?

Natural Circulation flowrate will be greater if...

A. ONE reactor coolant pump runs for an hour after the reactor trip, then stops."

B. ALL reactor coolant pumps run until the plant is in mode 4, then stop."

C. ALL reactor coolant pumps stop at the same time the reactor trips.

D. ALL reactor coolant pumps run for an hour after the reactor trip, then stop."

Proposed Answer: C Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SJ2.XG7.OB104 -

002 X New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8, 10 55.43 Comments:

Modifications: several distracters altered.

RO TEST QUESTION #: 13

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.068.AK2.03 Importance Rating 2.9 3.1 Proposed Question:

Choose the statement which correctly describes the operational characteristics of CR/HSP switches positioned to HSP.

A. Deenergizes the associated component to its fail-safe position.

B. Aligns alternate safe-shutdown control power to ensure automatic operation during a fire.

C. Isolates the component from the Control Room and removes automatic control function.

D. Isolates the component from the Control Room but maintains automatic control functions.

Proposed Answer: C Explanation:

Technical

Reference:

OPT-216A Remote Shutdown Operability Test Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 14

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.051.AK3.01 Importance Rating 2.8 3.1 Proposed Question:

Given the following Unit 1 plant conditions:

o Unit was initially at 100% power and has been manually tripped.

o Tave is 542F on all channels.

o "A" Condenser vacuum is 14" vacuum o "B" Condenser vacuum is 18" vacuum o two Circ water pumps are running Which ONE of the following describes steam dump availability?

A. Only the atmospheric dumps are available.

B. Steam dump is NOT available.

C. Only the condenser dump is available.

D. Both atmospheric and condenser dumps are available Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 2694 Modified New Question History: Last NRC Exam Prairie Island 1 (WEC) 6/16/1997 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

RO TEST QUESTION #: 15

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.5.E07.EK3.01 Importance Rating 3.1 3.7 Proposed Question:

Given the following:

-The RCS has had a stuck open Pressurizer safety valve.

-The reactor tripped and safety injection initiated.

-The RCS rapidly depressurized to saturation conditions.

-Pressurizer level initially dropped and then began to rise rapidly.

Which one of the following characterizes the relationship between pressurizer level and RCS inventory under these conditions?

A. Level is an accurate indication of inventory, because voiding would occur first in the pressurizer due to the high temperature of the pressurizer walls.

B. Level is an accurate indication of inventory, because hydraulic pressure would force any voids to the pressurizer steam space and out the safety valve.

C. Level is NOT an accurate indication of inventory, because RCS voiding may result in a rapidly increasing pressurizer level.

D. Level is NOT an accurate indication of inventory, because at higher temperatures the cold calibrated pressurizer level channels falsely indicate high.

Proposed Answer: C Explanation:

Technical

Reference:

EOS-1.2A, step 14 caution Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified EO1.XG3.OB900 -4 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

RO TEST QUESTION #: 16

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.1.029.EA1.03 Importance Rating 3.5 3.2 Proposed Question:

Given the following plant conditions:

- The unit was at 100% power

- A condition requiring a trip was diagnosed

- The operators are using FRS-0.1A, "Response to Nuclear Power Generation/ATWT", to respond to an ATWT

- The Turbine is tripped

- Emergency Boration valve 1/1-8104 has failed to open Which ONE of the following describes the actions that the operator is required to perform?

A. Open RWST supply to CCPs 1/1 LCV-112D and 1/1 LCV-112E, and shut VCT supply to CCPs 1/1 LCV-112B and 1/1 LCV-112C.

B. Open VCT supply to CCPs 1/1 LCV-112B and 1/1 LCV-112C, and shut RWST supply to CCPs 1/1 LCV-112D and 1/1 LCV-112E.

C. Open RWST supply to CCPs 1/1 LCV-112D, and shut VCT supply to CCPs 1/1 LCV-112B.

D. Open VCT supply to CCPs 1/1 LCV-112B, and shut RWST supply to CCPs 1/1 LCV-112D.

Proposed Answer: A Explanation:

Technical

Reference:

FRS-0.1A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 17

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.5.E02.EA1.01 Importance Rating 4.0 3.9 Proposed Question:

Unit 1 and Unit 2 have experienced a Reactor trip and a loss of offsite power. Unit 2 systems and equipment functioned as required. The following complications were experienced on Unit 1:

-The Train B Diesel Generator was tagged out for maintenance and Train A Diesel Generator started and supplied the 6.9 safeguards bus as required. An inadvertent Safety Injection has occurred.Train A CCP tripped on restart as the Blackout Sequencer fired.

-During the response actions of EOS-1.1A, "Safety Injection Termination", the Unit Supervisor identifies a caution that states "If RCP seal cooling had previously been lost, the affected RCP(s) should not be started prior to a status evaluation".

Which of the following is the appropriate recovery actions of EOS-1.1A for the conditions as described in this event?

A. RCP seal injection valves are isolated. The PD pump is loaded on the Train A electrical bus to provide normal charging. Following restoration of non-safeguards power, RCPs are not started prior to an engineering evaluation.

B. RCP seal injection valves are isolated. The PD pump is load shed on an SI signal and is not available to reload until the automatic SI signal is reinstated. Following restoration of non-safeguards power, RCPs are not started prior to an engineering evaluation.

C. The PD pump is manually loaded on the Train A electrical bus to provide normal charging and seal injection. Following restoration of non-safeguards power, the RCP can be started in accordance with RCP operating instructions without an engineering evaluation.RCP seal injection valves are isolated.

D. The PD pump is load shed on an SI signal and is not available to reload until the automatic SI signal is reinstated. Following restoration of non-safeguards power, RCPs can be started without an engineering evaluation.

Proposed Answer: C Technical

Reference:

EOS-1.1A, STEP 26 CAUTION, EOP-0.0A, ATT. 9 Question Source: Bank # CPSES Modified SJ1.XG9.OB107-1 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 18

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.5.E02.EA2.01 Importance Rating 3.3 4.2 Proposed Question:

Given the following:

o A Turbine/Generator trip has caused a Reactor trip.

o The operators are in EOP-0.0A, "Reactor Trip or Safety Injection," at step 4, "Check SI Status."

o RCS pressure is 1980 psig and slowly dropping.

o Pressurizer level is 22% and stable.

o Core exit T/Cs are 575 F and slowly rising.

o Containment pressure is 15 psia.

o All S/G NR levels are 20% and slowly rising.

Which of the following actions should be taken?

A. Transition to FRZ-0.1A, "Response to High Containment Pressure."

B. Proceed to EOS-0.1A, Reactor Trip Response.

C. Transition to FRH-0.1A, "Response to Loss of Secondary Heat Sink."

D. Initiate SI and continue in EOP-0.0A.

Proposed Answer: C Explanation:

Technical

Reference:

EOP-0.0A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

RO TEST QUESTION #: 19

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.1.009.EA2.01 Importance Rating 4.2 4.8 Proposed Question:

The plant is recovering from a loss of coolant accident in accordance with EOP-1.0A Loss of Reactor or Secondary Coolant with current conditions as follows:

-SI Pump Status: Both On

-RCP Status: ALL On

-RCS Pressure: 1987 psig and Stable

-Highest T-hot: 552 degrees F and Stable

-Highest CET: 560 degrees F and Stable

-Pressurizer Level: 34% and Increasing

-1A S/G Narrow Range Level: 12% and Stable

-1B S/G Narrow Range Level: 17% and Decreasing

-Total AFW Flow: 100 gpm

-Containment Pressure: 5 psig Which ONE of the following actions should be taken?

A. Stop all running RCPs B. Transition to FRZ-0.1A Response to High Containment Pressure C. Increase Total AFW flow to > 200 gpm D. Transition to EOS-1.1A SI Termination Proposed Answer: D Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 10764 Modified X New Question History: Last NRC Exam Kewaunee 1 (WEC), 12/18/1997 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 5 Comments:

Modifications: replaced one distracter.

RO TEST QUESTION #: 20

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.2.061.AA2.03 Importance Rating 3.0 3.3 Proposed Question:

The Containment Critical Safety Function Status Tree requires operators to immediately transition to a Function Restoration Procedure in the event of an imminent challenge to containment integrity. The condition that represents an imminent challenge to containment integrity is:

A. containment sump water level at 716 ft.

B. containment pressure at 19 psig.

C. containment temperature at 215 degrees F.

D. containment radiation at than 22 R/hr.

Proposed Answer: B Explanation:

Technical

Reference:

ERG-HP/LP Background, FRZ-0.1A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified MCO.MIF.OB103

- 003 X New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8 55.43 5 Comments:

Modifications: altered all distracters.

RO TEST QUESTION #: 21

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.1.038.3EA2.11 Importance Rating 3.7 3.9 Proposed Question:

During the diagnostic steps of EOP-0.0 following a manual Reactor trip and SI due to a slowly decreasing Pressurizer level, the BOP notices that the Main Steam Line Radiation Monitor for one of the Steam Generators had been in alarm, but is now reading only slightly above normal on the PC-11 trends. Which statement below is correct?

A. The trend is correct because when the Reactor and Turbine were tripped, the steam flow through the detector decreased resulting in the lower reading.

B. The trend is correct because while the Reactor was critical, N-16 was being produced and entering the SG through a leak. The N-16 has now decayed away resulting in a lower reading.

C. The trend is correct because the Main Steam Line Radiation Monitors are isolated on the SI signal resulting in the decreased reading.

D. The trend is incorrect because if the radiation monitor was in alarm, the trend should continue to increase as the Krypton and Xenon reach a new higher equilibrium value until the leak is stopped.

Proposed Answer: B Explanation:

Technical

Reference:

SOER 93-1, PALO VERDE SGTR Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.RM1.OB13-6 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 11 55.43 5 Comments:

RO TEST QUESTION #: 22

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.1.011.G.2.4.18 Importance Rating 2.7 3.6 Proposed Question:

A Large Break Loss of Coolant Accident (LBLOCA) has occurred and all RCS hot leg temperatures indicate 385°F. Why should the SI Accumulators Injection Valves be closed at this time?

A. Ensures that the RCS saturation pressure for 385°F does NOT exceed the SI Accumulator pressure after the accumulator water has been discharged.

B. Prevents overpressurization of Containment, which could occur if the nitrogen in the Accumulators was allowed to enter the RCS and exit via the break.

C. Ensures adequate volume of borated water and nitrogen have been injected to recover the Core with liquid and inert the hydrogen gas contained within the RCS and Containment.

D. Prevents further nitrogen injection into the RCS which could impede further RCS depressurization.

Proposed Answer: D Explanation:

Technical

Reference:

EOP-1.0A STEP 14 BASIS Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.SI1.OB16-2 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

RO TEST QUESTION #: 23

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.5.E02.EK1.02 Importance Rating 3.4 3.9 Proposed Question:

Following a LOCA, if the SI accumulators cannot be isolated, the correct action is to:

A. continue with the following steps, since isolation is not required.

B. drain the SI accumulators.

C. sample the pressurizer steam space for noncondensibles.

D. vent the SI accumulators.

Proposed Answer: D Explanation:

Technical

Reference:

EOP-1.0A, STEP 15 BASIS Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified ERG.XDD.OB103-1 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8, 10 55.43 Comments:

RO TEST QUESTION #: 24

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.5.E04.EK1.01 Importance Rating 3.5 3.9 Proposed Question:

ECA-1.2A, "LOCA Outside Containment", alerts the operator that some points of the system are a high probability for a LOCA. Which of the below has the highest probability for a LOCA outside containment?

A. CCW piping interface with RCP Seals B. RHR low pressure piping arrangement C. SI to RHR cross-tie piping arrangement D. SI piping and injection lines to the RCS Proposed Answer: B Explanation:

Technical

Reference:

ECA-1.2A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SM1.XGH.OB102-1 X New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8, 10 55.43 Comments:

Modification: altered one distracter.

RO TEST QUESTION #: 25

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.5.E01.EK2.01 Importance Rating 3.3 3.5 Proposed Question:

In accordance with the information provided on the foldout page of EOS-0.0A, "Rediagnosis" operators should proceed to FRZ-0.1A, "Response to High Containment Pressure," if:

A. containment pressure indicates > 50 psig.

B. containment pressure is > 5 psig, and level in all SGs is < 5% (NR).

C. containment pressure indicates >5 psig.

D. containment pressure is >15 psig and containment spray is not on.

Proposed Answer: A Explanation:

Technical

Reference:

EOS-0.0A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SJ1.XG5.OB105 -

002 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 26

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.5.E01.EK2.02 Importance Rating 3.5 3.8 Proposed Question:

Unit 2 is operating in EOP-0.0B, REACTOR TRIP OR SAFETY INJECTION. The Reactor is tripped and safety injection has actuated. The following plant indications and responses are observed;

• Containment pressure is 8 psig and rising.

• RCS subcooling is 57°F.

• Both CCPs and SIPs are running.

• Both CCWPs are running.

• Pressurizer level is 13%.

• Pressurizer pressure is 1815 psig.

• Two banks of steam dumps are open.

• Tave is 563 and rising.

Based on the above information, from the list below SELECT the required action.

A. Increase auxiliary feedwater flow to the steam generators.

B. Take manual control of steam dumps and increase demand.

C. Take manual control of SG ARVs and throttle to control temperature.

D. Allow SG ARVs to automatically control temperature..

Proposed Answer: C Technical

Reference:

EOP-0.0B Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified EO0.XG2.OB402-2 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 27

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.2.001.AK2.05 Importance Rating 2.9 3.1 Proposed Question:

Unit 1 is steady with reactor power at 90%. All systems are operating normally with the rod control system in automatic. Without warning, the rods begin to step and Tavg begins to increase above Tref, which remains constant. Pressurizer pressure and level also begin to increase.

These symptoms are consistent with which of the following?

A. PRZR pressure control system failure B. Main turbine/generator load increase C. Continuous rod insertion D. Continuous rod withdrawal Proposed Answer: D Explanation:

Technical

Reference:

ABN-712A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.CR1.OB09-1 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 28

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.5.E05.EK3.01 Importance Rating 3.4 3.8 Proposed Question:

What adverse consequence could result from delaying feed and bleed cooling if the conditions are met in FRH-0.1B Response to Loss of Secondary Heat Sink?

A. Inability to provide sufficient injection for core cooling due to high RCS pressure.

B. High temperature induced failure of U-tube bends C. RCP seal failure D. Inablity to recover the SGs without damage from high thermal stresses.

Proposed Answer: A Explanation:

Technical

Reference:

FRH-0.1B Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 8340 Modified New Question History: Last NRC Exam Ginna 1 (WEC), 5/8/1996 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

RO TEST QUESTION #: 29

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.5.E16.EK3.01 Importance Rating 2.9 3.1 Proposed Question:

Unit 2 is operating at 100% power. Over twelve hours the following plant indications and responses were observed in the control room;

• Containment humidity increased slightly

• Containment radiation increased slightly

• Containment dew point increased slightly

• Containment sump pumps have operated 1 time every hour.

• Automatic makeup to the VCT occurred 7 times.

• Letdown was maintained at 70 gpm and charging went from 82 gpm to 78 gpm.

• Pressurizer level has remained at 60%.

• Pressurizer pressure has trended from 2235 psig to 2220 psig and stabilized.

• No other abnormal alarms are annunciated.

Based on the above indications the operating crew entered ABN-103 and the following actions were taken;

• Radiation Protection was contacted to investigate containment radiation.

• Preparations are in progress to make a containment entry.

• Radiation Protection and Radwaste were notified that containment sumps would be left in operation to the WHT.

• Letdown and charging have been isolated and then realigned for normal operation.

• OPT-303 has been performed and unidentified leakage is 6 gpm.

• Preparations are being made to commence a reactor shutdown.

Based on the above information, SELECT from the list below the source of the unidentified leakage.

A. Reactor Coolant System cold leg leak.

B. Reactor Coolant System hot leg leak.

C. Pressurizer vapor space leak.

D. The yellow condition guideline must be implemented immediately due to plant conditions.

Proposed Answer: C Technical

Reference:

ABN-103A Question Source: Bank # CPSES Modified SYS.RC1.OB14 010 New Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

RO TEST QUESTION #: 30

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.5.E01.EK3.02 Importance Rating 3.0 3.9 Proposed Question:

Which of the below most correctly completes the following statement regarding natural circulation?

"Natural circulation flowrate will be greater if..

A. reactor coolant pumps stop at the same time the reactor trips"..

B. ALL reactor coolant pumps run for an hour after the reactor trip, then stop".

C. one reactor coolant pump runs for an hour after the reactor trip, then stops".

D. two reactor coolant pumps run for an hour after the reactor trip, then stop".

Proposed Answer: B Explanation:

Technical

Reference:

EOS-0.0A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SJ1.XG5.OB101 -

001 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

RO TEST QUESTION #: 31

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.2.008.AK3.03 Importance Rating 4.1 4.6 Proposed Question:

EOP-1.0A, "Loss of Reactor or Secondary Coolant," Step 1; "Check if RCPs should be stopped," is a continuous action step. Which ONE of the following is the basis for continuously monitoring for the criteria to perform this step in response to a LOCA?

A. Minimize cooldown rate B. Prevent excessive RCS inventory loss C. Prevent RCP damage from cavitation D. Minimize RCP run time with less than the required subcooling Proposed Answer: B Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank INPO 10769 Modifie

1. d New Question History: Last NRC Exam Kewaunee 1 (WEC), 12/18/1997 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

RO TEST QUESTION #: 32

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.5.E03.EK3.04 Importance Rating 3.5 3.9 Proposed Question:

Unit 1 Pressurizer level is 89% and the RVLIS 49" above flange lights are dark and the plant computer indicates an INVENTORY yellow condition. The unit has experienced a small break LOCA and plant response is being directed by EOS-1.2A, POST-LOCA COOLDOWN AND DEPRESSURIZATION. ECCS flow has not been terminated. The Unit Supervisor has currently decided not to implement the yellow condition guideline. From the list below SELECT why this is or is not an acceptable decision.

A. Transition has been made from EOP-0.0A, the yellow condition guideline should be implemented when EOS-1.2A is completed.

B. There exist other, more critical plant conditions that should be addressed before implementation of the yellow condition guideline.

C. Voids are not a concern when responding to a small break LOCA.

D. The yellow condition guideline must be implemented immediately due to plant conditions.

Proposed Answer: B Explanation:

Technical

Reference:

FRI-0.3A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified FRI.XH6.OB401 005 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

RO TEST QUESTION #: 33

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 3 2 K/A # 4.2.065.AA1.05 Importance Rating 3.3 3.3 Proposed Question:

Unit 1 is in MODE 2 with a startup in progress when instrument air header pressure begins decreasing. Attempts to restart and align an instrument air compressor to Unit 1 are unsuccessful and instrument air header pressure reaches 30 psig. The RO opens the Reactor Trip Breakers and the crew enters EOP-0.0. Select the corrective actions to be taken in response to this loss of Instrument air.

Dispatch a PEO to..............

A. close the MSIVs.

B. control charging flow.

C. close the S/G ARVs.

D. control AFW flow.

Proposed Answer: B Explanation:

Technical

Reference:

ABN-301A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.IA1.OB14-005 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 34

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 3 3 K/A # 4.2.028.AA1.07 Importance Rating 3.3 3.3 Proposed Question:

The reactor is critical at 10E-4% power when charging pump suction inadvertently switches from the VCT to the RWST. This occurs for approximately 10 minutes, then is stopped by the operators. Which one of the following describes the comparative effect that this will have on letdown flow?

A. It will decrease the most at EOL.

B. It will decrease the most at BOL.

C. It will not be significantly affected.

D. It will increase the most at BOL.

Proposed Answer: C Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank INPO 194 Modifie

1. d New Question History: Last NRC Exam Arkansas Nuclear 2 (CE), 8/28/1998 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 35

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 3 3 K/A # 4.2.056.AA2.02 Importance Rating 3.5 3.6 Proposed Question:

The plant is recovering from a loss of off-site power. Select the choice below which can be used as an indication that the Blackout Sequencer Operator Lockouts have reset (no longer present).

A. OL light on the associated sequencer is lit.

B. All step lights are lit on both sequencers.

C. Start of RMUW pump on associated train.

D. TD AFW pump steam supply valve opens.

Proposed Answer: C Explanation:

Technical

Reference:

ABN-602A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.ES3.OB11-1 d New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 5 Comments:

RO TEST QUESTION #: 36

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.7.015.A1.08 Importance Rating 3.3 3.4 Proposed Question:

Which limiting safety system setting provides a correction for changes in density and heat capacity of the reactor coolant system?

A. Overpower Delta T B. Power Range High Flux C. Pressurizer Low Pressure D. Overtemperature Delta T Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank INPO 9124 Modifie X

1. d New Question History: Last NRC Exam Cook 1 (WEC), 7/7/1997 Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 Comments:

Modifications: Replaced one distracter.

RO TEST QUESTION #: 37

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.5.022.A1.02 Importance Rating 3.6 3.8 Proposed Question:

Technical Specification state, "Containment pressure shall be maintained between -

0.3 and +1.3 psig in Modes 1, 2, 3 and 4." Which Containment system is used to control Containment pressure?

A. Containment Pressure Relief System B. Containment Ventilation System C. Containment Pressure Control System D. Containment Purge Supply and Exhaust System Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie X

1. SYS.CL1.OB16 d New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 Comments:

Modifications: Replaced one distracter.

RO TEST QUESTION #: 38

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.5.022.A2.06 Importance Rating 2.8 3.2 Proposed Question:

The containment design criteria are based on limiting the containment leakage rate under design basis accident conditions. According to the limiting containment analysis, containment pressure will:

A. exceed the containment design pressure for a short time, but the containment cooling systems will ultimately restore containment pressure below the design limit.

B. not exceed the containment design pressure initially. However, the analysis assumes a hydrogen burn that results in containment overpressure, which is ultimately controlled by the containment cooling systems.

C. exceed the containment ultimate capacity, leading to a gross failure of the containment structure.

D. not exceed the containment design pressure as long as a single train of containment cooling systems operates to perform its design function.

Proposed Answer: D Explanation:

Technical

Reference:

ERG-HP/LP BACKGROUND, FRZ-0.1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. MCO.MIF.OB102- d 1

New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments:

RO TEST QUESTION #: 39

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.4.059.A2.04 Importance Rating 2.9 3.4 Proposed Question:

ECA-2.1A/B, "Uncontrolled Depressurization of All Steam Generators," identifies that Auxiliary Feedwater flow to each Steam Generator with a narrow range level of less than 5% must be controlled at a minimum of 100 gpm. Which of the following is the reason for the minimum flow requirement?

A. Prevent Steam Generator tube dryout.

B. Ensure adequate RCS subcooling margin.

C. Maintain a verifiable cooldown rate.

D. Prevent further Steam Generator depressurization.

Proposed Answer: A Explanation:

Technical

Reference:

ECA-2.1A/B STEP 2 AND BASES Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SK1.XG1.OB103- d 1

New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments:

RO TEST QUESTION #: 40

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.7.072.A2.01 Importance Rating 2.7 2.9 Proposed Question:

WHICH ONE of the following electrical power systems would effect the operation of the Unit 1 Control Room Air Area Radiation Monitors when LOST?

A. 118 VAC Instrument Bus System.

B. QSPDS Power Supply System.

C. 120 Volt Vital AC System.

D. Non-Safety related 125 VDC System.

Proposed Answer: A Explanation:

Technical

Reference:

Drawing E1-0018-H Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments:

RO TEST QUESTION #: 41

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.2.004.A2.19 Importance Rating 2.8 3.5 Proposed Question:

During oxygen scavenging in the RCS, the CVCS demineralizers flow is:

A. maximized to aid in removal of the ammonia which is created by the evolution.

B. bypassed to prevent the creation of ammonia from the added hydrazine.

C. maximized to aid in removal of chlorides and fluorides from the RCS.

D. bypassed to prevent the removal of the added hydrazine before it can remove the oxygen.

Proposed Answer: D Explanation:

Technical

Reference:

IPO-001 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. IPO.XO1.OB900- d 6

New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments:

RO TEST QUESTION #: 42

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.4.061.A3.02 Importance Rating 4.0 4.0 Proposed Question:

Given the following:

-ECA-2.1A, Uncontrolled Depressurization of All Steam Generators, has been entered.

-SGs 1, 3, and 4 narrow range levels are 20%.

-SG 2 narrow range level is 40%.

-RCS pressure is 1200 psig and decreasing.

-RCS subcooling is 42 degrees F.

-Containment pressure is 14 psig.

-RCS cooldown rate is greater than 100 degrees F/hour.

Which one of the following actions should be taken for the given conditions?

A. Stop AFW flow to all SGs until cooldown rate is less than 100 degrees F/hour.

B. Reduce AFW flow to SGs 1, 3, and 4 to 100 gpm until cooldown rate is less than 100 degrees F/hour.

C. Stop AFW flow to SGs 1, 3, and 4 until cooldown rate is less than 100 degrees F/hour.

D. Reduce AFW flow to SG 2 to 100 gpm and stop AFW flow to SGs 1, 3, and 4 until cooldown rate is less than 100 degrees F/hour.

Proposed Answer: B Explanation:

Technical

Reference:

ECA-2.1A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. EO2.XG4.OB900 d 001 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 43

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.2.004.A3.12 Importance Rating 3.0 2.7 Proposed Question:

TCV-129 protects the BTRS demineralizers by:

A. shutting the BTRS isolation valves at 155°F upstream of the BTRS demineralizers.

B. diverting CVCS letdown flow to the VCT which stops flow through BTRS at 155°F upstream of the BTRS demineralizers.

C. starting the BTRS chiller at 155°F upstream of the BTRS demineralizers.

D. TCV-129 does not protect the BTRS demineralizers.

Proposed Answer: B Explanation:

Technical

Reference:

SOP-106A SECTION 4.0 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.BT1.OB900 d 016 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 44

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.4.003.A3.01 Importance Rating 3.3 3.2 Proposed Question:

A caution in EOP-1.0A/B, "Loss of Reactor or Secondary Coolant" states that "seal injection flow should be maintained to all RCPs". After the Unit Supervisor has informed the operating crew of this caution, the RO checks seal injection flow and identifies that seal injection flow is approximately 20 gpm to each Reactor Coolant Pump.

Which of the following is the proper initial response to the current plant conditions?

A. Quickly proceed to the ECCS Termination Criteria to determine if one CCP can be stopped.

B. Reference ABN-101, "Reactor Coolant Pump Trip/Malfunction" for possible RCP No. 1 Seal Failure.

C. Verify that HV-8801A and HV-8801B have not closed causing an increased flow through the RCP seal injection.

D. Adjust charging flow control valve FCV-121 to obtain seal injection flow to within 6 to 13 gpm.

Proposed Answer: D Explanation:

Technical

Reference:

EOP-1.0A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SJ3.XG2.OB104 d 009 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 45

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.4.059.A4.11 Importance Rating 3.1 3.3 Proposed Question:

Which ONE of the following Feedwater Isolation Signals (FWI) must be manually reset by pushing the FWI reset pushbuttons before the feedwater isolation valves may be opened?

A. Containment Isolation B. Safety Injection C. Hi-Hi Steam Generator Level D. P-4 coincident with Lo Tave.

Proposed Answer: D Explanation:

Technical

Reference:

SOP-302A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.MF1.OB07 - d 002 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 46

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.9.068.G.2.3.4 Importance Rating 2.5 3.1 Proposed Question:

A discharge permit is being routed to discharge Plant Effluent Holdup and Monitor Tank to Outfall 004. Which of the following Post NID QA Analysis results require that the radwaste supervisor be notified?

A. Antimony (Sb) - 1.5 E-6 uci/ml B. Cobalt (Co) - 2.3 E-7 uci/ml C. Cesium (CS) - 1.0 E-5 uci/ml D. Iodine (I) - < MDA Proposed Answer: C Explanation:

Technical

Reference:

RWS-103 ATT9 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.WP1.OB07 d 001 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 4 Comments:

RO TEST QUESTION #: 47

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.7.015.K1.03 Importance Rating 3.1 3.1 Proposed Question:

A normal reactor startup is planned for the unit following maintenance on excore nuclear instrumentation. Believing a problem may still exist, the RO is directed to closely observe source range operation throughout the evolution. Which one of the following is an indicator that the source range channel failed high during the reactor startup? Assume that the reactor trips.

A. Rod withdrawal block B. P-6 energized C. P-10 energized D. Flux Doubling Alarm is lit Proposed Answer: D Explanation:

Technical

Reference:

ALM-0064 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.EC1.OB10-2 d New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2, 9 55.43 Comments:

RO TEST QUESTION #: 48

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.7.017.K1.02 Importance Rating 3.3 3.5 Proposed Question:

With Hot and Cold leg injection in progress, which of the following temperature indications should be used to monitor RCS temperature?

CET Temperature equal to:

A. Representative CET B. Hot leg Safety Channel C. Cold leg Safety Channel D. Subcooled Margin Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 3145 Modified New Question History: Last NRC Exam Waterford 3 (WEC), 9/6/1996 Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2, 9 55.43 Comments:

RO TEST QUESTION #: 49

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.1.001.K1.05 Importance Rating 4.5 4.4 Proposed Question:

An approach to criticality is being performed by means of control rod withdrawal. The RO stops control rod motion when the reactor is close to criticality but still subcritical.

The SR count rate should:

A. continue to increase, but at a slower rate. The startup rate should stabilize at a lower positive value.

B. continue to increase for a short time and then plateau. The startup rate should gradually decease to zero.

C. stop increasing and stabilize at its present value. The startup rate should immediately decrease to zero.

D. begin to slowly decrease. The startup rate should gradually decrease to zero from a slightly negative value.

Proposed Answer: B Explanation:

Technical

Reference:

IPO-002A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. IPO.XO2.OB900- d 012 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2, 9 55.43 Comments:

RO TEST QUESTION #: 50

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.7.015.K1.08 Importance Rating 2.6 2.9 Proposed Question:

With the unit at 85% power, the Reactor Operator notes that the P-8 permissive lamp on the PCIP suddenly comes on. The Unit Supervisor determines that protection is no longer provided for the loss of a single RCP. The most appropriate action in accordance with Technical Specifications would be to:

A. Restore P-8 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in HSB within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

B. Restore P-8 within one hour or be in MODE 2 in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

C. Restore P-8 within one hour or trip associated bistables within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

D. Reduce power to less than 48% within one hour.

Proposed Answer: B Explanation:

Technical

Reference:

TS 3.3.1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.ES1.OB17-1 d New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2, 9 55.43 Comments:

RO TEST QUESTION #: 51

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.4.003.K1.01 Importance Rating 2.6 2.8 Proposed Question:

Unit 1 is operating at 50% power when a RCP Lube Oil Low Level alarm actuates.

Maintenance personnel request to enter the Containment Loop Rooms to setup a camera for remote monitoring capability. Who must approve this entry into the Containment Loop Rooms?

A. Shift Manager.

B. Radiation Protection Manager.

C. Plant Manager.

D. Either B or C.

Proposed Answer: D Explanation:

Technical

Reference:

OPD1.ADM.XAB, STA-620 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. ADM.XAB.OB13- d 1

New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2, 9 55.43 Comments:

RO TEST QUESTION #: 52

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.4.003.K1.10 Importance Rating 3.0 3.2 Proposed Question:

The following conditions exist:

- RCS temperature - 340 degrees F

- Steam Generator pressure - 50 psig

- A bubble exists in the Pressurizer Which ONE of the following statements would describe the initial primary plant response if a Reactor Coolant Pump were started?

RCS RCS temperature pressure A. INCREASE INCREASE B. INCREASE DECREASE C. DECREASE INCREASE D. DECREASE DECREASE Proposed Answer: D Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 16073 Modified New Question History: Last NRC Exam Byron 1 (WEC), 10/14/1996 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2, 9 55.43 Comments:

RO TEST QUESTION #: 53

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.5.022.K3.02 Importance Rating 3.0 3.3 Proposed Question:

Which plant condition will most likely cause a RV FLANGE LKOFF TEMP HI alarm?

A. Loss of Ventilation Chillers 1, 2, 3 and 4.

B. Loss of Ventilation Chillers 7, 8 and 9.

C. Loss of power to 1PC1.

D. Loss of power to 1C1.

Proposed Answer: A Explanation:

Technical

Reference:

ALM-0053A, Window 1.1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.RC1.OB04 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 54

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.4.061.K3.02 Importance Rating 4.2 4.4 Proposed Question:

During the performance of IPO-002A the operator is directed to replace Motor Driven AFW pump fuses. These fuses restore pump auto-start on:

A. LO-LO S/G level.

B. Blackout Signal.

C. Safety Injection Signal.

D. trip of both Main Feedwater Pumps..

Proposed Answer: D Explanation:

Technical

Reference:

IPO-002A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. IPO.XO2.OB900 - d 023 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 55

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.4.061.K4.01 Importance Rating 4.1 4.2 Proposed Question:

Given the following:

o The Unit is in mode 3.

o A loss of offsite power has occurred.

o Steam is being released through the S/G PORV's.

What is the minimum level required in the CST to support cooldown to RHR entry conditions?

A. 63%

B. 69%.

C. 53%.

D. 59%.

Proposed Answer: C Explanation:

Technical

Reference:

TS 3.7.6 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 56

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.2.013.K4.12 Importance Rating 3.7 3.9 Proposed Question:

WHICH ONE (1) of the following describes the design interlock or operating practice that is used to prevent ALL automatic Safety Injection (SI) actuations following a reset of the SI signal?

A. The sixty (60) second delay timer in the SI reset circuitry.

B. Manually blocking steam line pressure and PZR pressure SI from the control board.

C. The seal-in feature of the reset circuitry disarms all subsequent SI actuations.

D. The P-4 interlock, actuated by the opening of the reactor trip breakers.

Proposed Answer: D Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank INPO 4225 Modifie

1. d New Question History: Last NRC Exam Harris 1 (WEC), 2/24/1997 Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 57

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.1.001.K4.23 Importance Rating 3.4 3.8 Proposed Question:

During a 10% step load increase, the operator observes:

• 855 MWe (stable)

• Tave - Tref error = 8°F (Tave 8°F low)

• 68% RTP (increasing)

• OTNI6/C-3 (PCIP) dark

• all controls in automatic Which of the below describes a possible response of the rod control system during this transient?

A. Rods not moving out due to the OPNI6 rod stop (C-4).

B. Rods moving out due to Rx power increasing with turbine load constant.

C. Rods not moving out to restore Tave (when Tave is 3°F low) due to Reactor power increasing.

D. Rods moving out to restore Tave (when Tave is 3°F low) due to Reactor power increasing.

Proposed Answer: C Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified X MCO.TA2.OB103 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Modification: replaced one distracter.

RO TEST QUESTION #: 58

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.2.013.K6.01 Importance Rating 2.7 3.1 Proposed Question:

An Engineered Safety Features (ESF) Containment Hi-3 Pressure signal occurs when:

A. 2/4 Hi containment pressure detectors sense pressure > 3.2 psig.

B. 2/4 Hi containment pressure detectors sense pressure > 18.2 psig.

C. 2/3 Hi containment pressure detectors sense pressure > 18.2 psig.

D. 2/3 Hi containment pressure detectors sense pressure > 3.2 psig.

Proposed Answer: B Explanation:

Technical

Reference:

ALM-0022A (ALB 2B, 3.10)

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.CT1.OB04-3 d X New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Modified: altered one distracter RO TEST QUESTION #: 59

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.7.012.A1.01 Importance Rating 2.9 3.4 Proposed Question:

During the performance of OPT-309, "Unit Calorimetric", the feedwater temperature points utilized were reading 10°F LOWER than actual feedwater temperature. Power range nuclear instruments adjustments were performed per the OPT.

What is the status of the current power range indications?

A. Indicated power is LESS THAN actual power; therefore, power range instruments are set CONSERVATIVELY.

B. Indicated power is LESS THAN actual power; therefore, power range instruments are set NON-CONSERVATIVELY.

C. Indicated power is GREATER THAN actual power; therefore, power range instruments are set NON-CONSERVATIVELY.

D. Indicated power is GREATER THAN actual power; therefore, power range instruments are set CONSERVATIVELY.

Proposed Answer: D Explanation:

Technical

Reference:

LO21.SF4.XOC, OPT-309 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SF4.XOC.OB103- d 1

New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 Comments:

RO TEST QUESTION #: 60

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.8.029.A2.01 Importance Rating 2.9 3.6 Proposed Question:

Given the following conditions:

-Unit 1 is in mode 6 for a refueling outage.

-Off-load of fuel is 55 % complete and ongoing.

-Containment purge and exhaust is in service.

-The instrument department has just reported that the current HI and HI-HI setpoints for CONTAINMENT EXHAUST RADIATION MONITOR were incorrectly set two decades HIGH.

Based on this information, the required action is to:

A. suspend core off-load until the containment purge and exhaust valves are closed.

B. suspend core off-load until the correct setpoints are entered.

C. continue core off-load and direct HP to perform continuous air monitoring of the containment.

D. continue core off-load and verify purge exhaust directed through the charcoal filter bank.

Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 1342 Modified New Question History: Last NRC Exam North Anna 1 (WEC), 1/26/1996 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments:

RO TEST QUESTION #: 61

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.6.062.A2.09 Importance Rating 2.7 3.0 Proposed Question:

Current flow to ground is limited in a neutral grounding transformer by:

A. the reflected impedance of the secondary into the primary.

B. a series current limiting resistor.

C. a protective overcurrent relay.

D. a circuit breaker Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.AC2.OB900 d

- 002 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments:

RO TEST QUESTION #: 62

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.7.073.A2.01 Importance Rating 2.5 2.9 Proposed Question:

WHICH ONE (I) of the following actions occur upon loss of power to the Containment Atmosphere Particulate Radioactivity Monitor?

A. Containment purge isolation will occur DIRECTLY from the monitor.

B. A loss of process sample flow occurs and causes a high radiation alarm due to detector integration.

C. A loss of process sample flow occurs and blocks any actuation from the monitor.

D. Phase "A" isolation will occur from fail safe relays in the RM-80.

Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 4252 Modified New Question History: Last NRC Exam Harris 1 (WEC), 2/24/1997 Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments:

RO TEST QUESTION #: 63

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.2.011.A2.04 Importance Rating 3.5 3.7 Proposed Question:

Unit 1 is in the following configuration: RCS pressure is 300 psig, Tavg is 300°F, and Train "A" RHR is in the shutdown cooling mode. At this point, pressurizer level starts decreasing rapidly with flow controller FK-121 fully open.

Select the correct action to be taken if pressurizer level continues to decrease.

A. Unisolate the Safety Injection Accumulators.

B. Reduce letdown flow - transfer to the 45 gpm orifice.

C. Dispatch an operator to rack in the breakers to the non-operating CCP and one SIP.

D. Reset containment isolation Phase A and B.

Proposed Answer: C Explanation:

Technical

Reference:

ABN-108 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.RC1.OB30 - d 032 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments:

RO TEST QUESTION #: 64

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 1 K/A # 3.5.026.A3.01 Importance Rating 4.3 4.5 Proposed Question:

A large break LOCA has occurred on Unit 1. Given the following conditions:

- Containment pressure is 22 psig

- Containment Spray failed to automatically initiate

- Manual pushbutton actuation for Containment Spray was also unsuccessful Which ONE of the following describes the required operator actions following manual start of Containment Spray Pumps?

A. Verify CS Heat Exchanger Outlet valves are OPEN; manually OPEN Chemical Additive Tank Discharge valves.

B. Manually OPEN CS Heat Exchanger Outlet valves; manually OPEN Chemical Additive Tank Discharge valves.

C. Manually OPEN CS Heat Exchanger Outlet valves; verify Chemical Additive Tank Discharge valves are OPEN.

D. Verify CS Heat Exchanger Outlet valves are OPEN; verify Chemical Additive Tank Discharge valves are OPEN.

Proposed Answer: B Explanation:

Technical

Reference:

SOP-204A, FRZ-0.1A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 65

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.4.055.A3.03 Importance Rating 2.5 2.7 Proposed Question:

Unit 1 is at 100% power with CEV 1-02 running, CEV 1-01 in standby, and CEV 1-03 off. While conducting a CEV lineup verification, you discover 1CV-0235 CNDSR VAC PMP 1-01 SUCT PRESS SW 2970A/2971A/2972A HP RT VLV closed, and the instrument air line between 1PS-2971A and 1CV-235 is disconnected. If Main Condenser vacuum decreases to 23" with this alignment, how will CEV operation be affected?

A. CEV 1-02 will eventually trip.

B. CEV 1-01 will start on low vacuum, and 1-HV-2956 will open.

C. CEV 1-01 will NOT start on low vacuum, and 1-HV-2956 will NOT open.

D. CEV 1-01 will start on low vacuum, but 1-HV-2956 will NOT open.

Proposed Answer: D Explanation:

Technical

Reference:

M1-2211, SH 02 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.CV1.OB106- d 003 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 66

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.8.029.A4.04 Importance Rating 3.5 3.6 Proposed Question:

While lifting a fuel assembly from the Reactor vessel lower core plate, audible Source Range indication inside Containment is lost and cannot be corrected. Which of the following actions are correct for this situation?

A. Movement of the fuel assembly must cease immediately. Containment evacuation is required.

B. Core alterations may continue as long as the criticality alarm is NOT alarming.

Containment evacuation is NOT required.

C. Movement of the fuel assembly shall continue to place it in a safe location.

Containment evacuation is required.

D. Core alteration may continue as long as Containment Integrity is met.

Containment evacuation is NOT required.

Proposed Answer: C Explanation:

Technical

Reference:

TS 3.9; RFO-102, RFO-302 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. RFO.SYE.OB404 d 002 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 67

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.7.012.G.2.2.22 Importance Rating 3.4 4.1 Proposed Question:

While in mode 4 with one Control Bank rod indicating at 9 steps, which of the following conditions requires entry into a Technical Specification LCO?

A. One Source Range Nuclear Instrument is inoperable.

B. Planned maintenance on a Coolant Charging Pump.

C. Maintenance on a Power Range Nuclear Instrument.

D. One channel of Pressurizer Pressure Instrument fails low.

Proposed Answer: A Explanation:

Technical

Reference:

TS SECTION 3.3.1-1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank Modifie

1. d New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2, 7, 10 55.43 2 Comments:

RO TEST QUESTION #: 68

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.7.016.K1.10 Importance Rating 3.1 3.1 Proposed Question:

Which of the following conditions would require entering a CPSES Technical Specification Limiting Condition for Operation action with the plant in hot standby?

A. Opening the outer door to the Personnel Air Lock to enter Containment B. Containment pressure at 1.2 psig C. Containment air temperature 123°F D. One train of Electric Hydrogen Recombiners inoperable Proposed Answer: C Explanation:

Technical

Reference:

TS 3.6.5 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.CY1.OB900- d 25 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2, 9 55.43 Comments:

RO TEST QUESTION #: 69

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.2.006.K2.02 Importance Rating 2.5 2.9 Proposed Question:

Upon loss of all a/c power while operating in mode 1 at 100% power, how will the SIS Accumulator Isolation Valves respond?

A. SIS Accumulator Isolation Valves are air operated and are not affected by loss of a/c.

B. They will fail open.

C. They will fail shut.

D. They will remain in the same position they were in before the loss of a/c.

Proposed Answer: D Explanation:

The SIS Accumulator Isolation Valves are motor operated and will not change positions on loss of their 480v power supply.

Technical

Reference:

Drawings M1-0262, M1-2262, E1-0005, E1-0009 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank Modifie

1. d New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 3, 7 55.43 Comments:

RO TEST QUESTION #: 70

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.4.035.K3.01 Importance Rating 4.4 4.6 Proposed Question:

Due to a malfunction with the S/G Blowdown Mixed Bed Demineralizer Outlet Radiation Valve, S/G Blowdown flow has isolated. What effect does this have on Reactor power if the unit is operating at 80% RTP?

A. Reactor power increases approximately 5%.

B. Reactor power decreases approximately 2%.

C. Reactor power remains the same.

D. Reactor power decreases initially, and slowly rises back to original value.

Proposed Answer: B Explanation:

Technical

Reference:

DBD-ME-0239 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.SB1.OB06-1 d New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 71

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.7.016.K3.08 Importance Rating 3.5 3.7 Proposed Question:

Unit 1 is operating at 100% power with all control systems in their normal alignment when the Pressurizer Pressure Instrument selected for control to the Pressurizer Master Pressure Controller fails high. Which of the below actions will occur?

(assume no operator actions)

A. PCV-455A will open and not re-close.

B. PCV-456 will open and not re-close.

C. PCV-456 will open and re-close at 2185 psig.

D. PCV-455A will open and re-close at 2185 psig.

Proposed Answer: D Explanation:

Technical

Reference:

LO21.MCO.TA3.LP Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. MCO.TA3.OB102 d

- 24 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 72

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.4.035.K4.06 Importance Rating 3.1 3.4 Proposed Question:

The are designed to prevent overpressurization of the S/Gs.

A. S/G Atmospherics B. Main Steam Safety Valves C. LP Turbine Atmospheric Relief Diaphragms D. MSR Relief Valves Proposed Answer: B Explanation:

Technical

Reference:

OP51.SYS.MR1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.MR1.OB03-1 d New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 73

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.8.029.K4.03 Importance Rating 3.2 3.5 Proposed Question:

With the Unit in Mode 5, which of the following automatic actions will occur when the Containment Purge Exhaust Monitor reaches a High-High alarm condition?

A. A Containment Isolation Signal will be generated isolating all Phase-A flowpaths from the containment.

B. Containment Purge Supply and Exhaust Fans will trip, and the Purge Supply and Exhaust Dampers will close.

C. The Supplemental Leak Collection and Release System (SLCRS) will be aligned to bypass the Main Filter Bank and provide an elevated release flowpath.

D. The Containment Purge Exhaust will be aligned to the SLCRS and then filtered through the Main Filter Banks.

Proposed Answer: B Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 588 Modified New Question History: Last NRC Exam Beaver Valley 2 (WEC), 3/17/1997 Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 74

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.7.073.K4.01 Importance Rating 4.0 4.3 Proposed Question:

If the S/G Blowdown Mixed Bed Demineralizer Outlet Radiation Monitor was to lose power, what effect would this have on the S/G Blowdown System?

A. The Control Room would not receive warning of S/G Blowdown Demineralizer resin exhaustion.

B. The radiation valve would close and all S/G Blowdown flow stops.

C. The radiation valve will be unable to perform its intended function.

D. The Control Room would receive a S/G Blowdown Panel trouble alarm and the system will continue to operate.

Proposed Answer: B Explanation:

Technical

Reference:

E1-0040, Sh 97, ALM-3200 att 3 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.SB1.OB09-2 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 4 Comments:

RO TEST QUESTION #: 75

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.8.086.K4.01 Importance Rating 3.1 3.7 Proposed Question:

A fire has been reported in the Aux. Building. The Fire Brigade has responded and is using the Fire Protection Hose Stations to fight the fire. Which ONE of the following describes the response of the fire pumps to decreasing fire header pressure?

A. The diesel driven pumps start at 142 psig and the electric fire pump starts if pressure is not raised above 120 psig in 10 seconds.

B. One diesel driven fire pump starts at 148 psig and the electric fire pump starts at 120 psig.

C. The electric fire pump starts at 142 psig and one diesel driven fire pump starts in 10 seconds if pressure is not above 140 psig.

D. The electric fire pump starts at 142 psig; one diesel driven fire pump starts at 120 psig; the other diesel driven fire pump starts in 10 seconds if pressure is not raised above 120 psig.

Proposed Answer: C Explanation:

Technical

Reference:

SOP-904 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.FP1.OB106-001 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 76

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.4.035.K4.05 Importance Rating 2.9 3.2 Proposed Question:

The following conditions are observed on Unit 2 at the moment of a reactor trip:

Reactor Power = 29 %

S/G NR Level = 27 %

One Reactor Coolant Pump has just tripped off Which of the following statements are the likely to be true regarding the reactor trip?

A. The reactor tripped on S/G Water Level Low-Low to prevent a loss of heat sink.

B. The reactor tripped on S/G Water Level Low-Low to prevent a loss of level indication.

C. The reactor tripped on P-8 interlock to ensure adequate margins to DNB are maintained.

D. The reactor tripped on P-8 interlock to prevent exceeding peak fuel centerline temperature limits.

Proposed Answer: A Explanation:

Power is below the P-8 Low Flow trip block of 39%, and the purpose of SG Low-Low Level trip is to prevent loss of heat sink, not loss of level indication.

Technical

Reference:

TS TABLE 3.3.1-1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank Modifie

1. d New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4, 6, 8 55.43 Comments:

RO TEST QUESTION #: 77

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.8.086.K4.03 Importance Rating 3.1 3.7 Proposed Question:

The Unit 2 Safeguards PEO has reported that the 2-02 Diesel Generator Starting Air Compressor is extremely warm. If a fire were to occur on this component a local......

A. ionization smoke detector would detect the fire and initiate the deluge system.

B. thermal detector would detect the fire and provide alarms.

C. thermal detector would detect the fire and initiate the deluge system.

D. ionization smoke detector would detect the fire and provide alarms.

Proposed Answer: D Explanation:

Technical

Reference:

ABN-901 att1 & 5 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.FP1.OB303 - d 001 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 78

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.3.010.K5.02 Importance Rating 2.6 3.0 Proposed Question:

The pressurizer is being maintained at 2000 psia and 636 °F when one of the Power-Operated Relief Valves (PORVs) starts to leak to the Pressurizer Relief Tank (PRT).

The PRT pressure is maintained at 5 psig. The TEMPERATURE of the fluid immediately downstream of the PORV is approximately:

A. 220°F B. 240°F C. 230°F D. 250°F Proposed Answer: C Explanation:

The process is isenthalpic and the fluid downstream of the PORV is at the same pressure as the PRT. Assume Containment pressure is 15 psia. Convert PRT pressure from psig to psia:

-PRT pressure = 5 psig + 15 psi = 20 psia.

-From Steam Table 2 (or the Mollier Diagram),

-Tsat (20 psia) = 228 °F (approx. 230 °F).

Technical

Reference:

OP51.SYS.PP1.LN Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.PP1.OB09-7 d New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 Comments:

RO TEST QUESTION #: 79

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 3 3 K/A # 3.8.008.A2.04 Importance Rating 3.3 3.5 Proposed Question:

Unit 4 is operating at 100% power in normal alignment when the following events occur:

-A rupture develops in a RCP thermal barrier.

-ONE of the CCW PRMS monitors has just gone into alarm.

-CCW head tank level indicates 81%.

-CCW surge tank level reads 100%.

-CCW flow from RCP thermal barriers has increased to 110 gpm.

Which one of the following describes current condition of the CCW head tank vent valve, and RCP thermal barrier outlet?

A. CCW head tank vent is open. RCP thermal barrier outlet is closed.

B. CCW head tank vent is open. RCP thermal barrier outlet is open.

C. CCW head tank vent is closed. RCP thermal barrier outlet is closed.

D. CCW head tank vent is closed. RCP thermal barrier outlet is open.

Proposed Answer: D Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 5100 Modified New Question History: Last NRC Exam Turkey Point 4 (WEC), 8/7/1998 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments:

RO TEST QUESTION #: 80

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 3 3 K/A # 3.4.045.K1.06 Importance Rating 2.6 2.6 Proposed Question:

When testing Main Steam Isolation Valve #1 (MSIV-1) from the control room, which of the following conditions will actuate the "MSIV #1 TEST FAILED" alarm?

A. MSIV-1 fails to reach 90% open in 10 seconds or less.

B. MSIV-1 fails to reach 90% open in 20 seconds or less.

C. MSIV-1 closes 10% and fails to return to full open.

D. MSIV-1 closes more than 10% during the test.

Proposed Answer: B Explanation:

Technical

Reference:

OP51.SYS.MR1.OB20 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.MR1.OB20-1 d New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2,9 55.43 Comments:

RO TEST QUESTION #: 81

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 3 3 K/A # 3.4.076.K1.07 Importance Rating 2.5 2.3 Proposed Question:

The service water pump bearings are cooled and lubricated with water supplied from the:

A. discharge of service water pumps.

B. discharge of screen wash pumps.

C. demineralized water pumps.

D. circulating water pumps.

Proposed Answer: A Explanation:

Technical

Reference:

OP51.SYS.SW1.LN; M1-0233 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.SW1.OB02- d 6

New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2,9 55.43 Comments:

RO TEST QUESTION #: 82

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 3 3 K/A # 3.4.076.K2.01 Importance Rating 2.7 2.7 Proposed Question:

Which of the following components is powered from the safeguards 6.9 KV buses?

A. CW pumps B. RCPs C. HDPs D. SSW pumps Proposed Answer: D Explanation:

Technical

Reference:

E1-0003, E1-0004 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.AC2.OB03 -

004 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 83

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 3 3 K/A # 3.4.045.K4.47 Importance Rating 4.0 4.3 Proposed Question:

A reactor trip generates a turbine trip by:

A. deenergizing the remote trip solenoids in the EHC system.

B. deenergizing the main trip valve in the EHC system.

C. energizing the remote trip solenoids in the EHC system.

D. energizing the main trip valve in the EHC system.

Proposed Answer: C Explanation:

Technical

Reference:

CP-0003-26,sect 12 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.MT1.OB27 -

001 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 84

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 3 3 K/A # 3.5.007.K4.01 Importance Rating 2.6 2.9 Proposed Question:

What is a disadvantage of using the RCDT method to cool the water in the PRT?

A. May take up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to cool down the PRT.

B. Requires a TS LCO entry.

C. May take up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to cool down the PRT.

D. Maximum flow through LCV-1003 is limited by the heat exchanger.

Proposed Answer: C Explanation:

Technical

Reference:

SOP-110A, Section 5.4 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.RC1.OB15 - d 003 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 85

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 3 2 K/A # 3.5.028.K5.02 Importance Rating 3.4 3.9 Proposed Question:

The following conditions exist:

-The plant was operating at 100% power, when a Large Break LOCA to Containment occurred

- Containment Hydrogen is 1%

-Water level in the Reactor Core is 50% (half the fuel is exposed)

Which ONE of the following will make hydrogen conditions in containment worse?

A. Water level in the reactor core increasing from 50% to 90% level B. Instrument air leak to containment C. Excessive leakage from containment thru the Containment Vacuum Breakers D. Exit Thermocouples at 1800 degrees F and rising Proposed Answer: D Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 10850 Modified New Question History: Last NRC Exam Kewaunee 1 (WEC), 12/18/1997 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 Comments:

RO TEST QUESTION #: 86

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 3 2 K/A # 3.5.028.K6.01 Importance Rating 2.6 3.1 Proposed Question:

The temperature of the air mixture in the containment hydrogen recombiners is controlled by:

A. cycling the recombiner electric heaters on and off to maintain temperature in the proper band.

B. regulating the air flow at the discharge of the recombiner used to preheat the inlet flow.

C. varying the power to the recombiner electric heaters.

D. regulating the air flow at the inlet of the recombiner.

Proposed Answer: C Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 5355 Modified New Question History: Last NRC Exam Salem 1 (WEC), 1/22/1996 Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 87

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 1 1 K/A # 2.1.16 Importance Rating 2.9 2.8 Proposed Question:

Select the statement that describes why portable radios should not be used in "Radio Free Zones.

A. Radio transmission interferes with security radios in the event of a security plan implementation.

B. Radio frequencies may inadvertently interfere with CENTREX equipment.

C. Radios are useless in these areas due to signal reception difficulties.

D. Radios produce electromagnetic interference (EMI) that may cause inadvertent equipment operation.

Proposed Answer: D Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 5417 Modified New Question History: Last NRC Exam Salem 1 (WEC), 1/22/1996 Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

RO TEST QUESTION #: 88

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 1 1 K/A # 2.1.18 Importance Rating 2.9 3.0 Proposed Question:

The NRC must be notified in writing within 30 days if a licensed operator is convicted of a felony. Which of the following is responsible for notifying the NRC of the conviction?

A. The licensed individual.

B. The Manager, Operations.

C. The Plant Manager.

D. Vice President, Nuclear Operations.

Proposed Answer: A Explanation:

Technical

Reference:

STA-501 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified ADM.XA7.OB01-2 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

RO TEST QUESTION #: 89

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 1 1 K/A # 2.1.24 Importance Rating 2.8 3.1 Proposed Question:

Given drawing E1-0057 Sheet 16, determine which of the following signals will generate an open signal to Fan 9 Isolation Damper 1-HV-5953.

A. Energizing the 42 relay.

B. Energizing the 1-HX-5952 relay.

C. Energizing the 1-42AX/5952 relay.

D. Energizing the 74 relay.

Proposed Answer: B Explanation:

Technical

Reference:

E1-0057 sheet 16 Proposed references to be provided to applicants during examination:

E1-0057 sheet 16 Learning Objective:

Question Source: Bank # CPSES Modified SYS.HV2.OB07-1 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO TEST QUESTION #: 90

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 2 2 K/A # 2.2.3 Importance Rating 3.1 3.3 Proposed Question:

Identify the unit difference of the Process Sampling System.

A. Unit 1 sample coolers are supplied by Train A CCW while Unit 2 sample coolers are supplied by Train B CCW.

B. Unit 2 sampling valves all fail open.

C. Unit 1 sample hood purge flow is directed to FDT #3.

D. Spent Fuel Pool demineralizers sample is taken on Unit 1 side.

Proposed Answer: D Explanation:

Technical

Reference:

OP51.SYS.PA2.OB21 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.PA2.OB21-1 d New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 7 Comments:

RO TEST QUESTION #: 91

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 2 2 K/A # 2.2.22 Importance Rating 3.4 4.1 Proposed Question:

During a post trip review, it was noted that the reactor had tripped in response to a high Pressurizer pressure signal at 2360 psig. Which of the following statements is correct? (Assume only the High Pressure setpoint was affected)

A. The channel must be declared inoperable and related bistables tripped within six hours.

B. Mode 2 must not be re-entered until the setpoint is adjusted to the proper pressure.

C. The setpoint does not meet the LCO, but no power restrictions are in effect while the setpoint is being adjusted.

D. The setpoint meets the LCO requirements and should not affect the status of ability to operate at power.

Proposed Answer: D Explanation:

Technical

Reference:

TS 3.3.1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.RC1.OB30 -

040 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 2 Comments:

RO TEST QUESTION #: 92

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 2 2 K/A # 2.2.23 Importance Rating 2.6 3.8 Proposed Question:

A LCOAR which applies to the present plant MODE or plant conditions and requires certain restrictions while the plant is in a degraded condition is called:

A. a Tracking LCOAR.

B. an Active LCOAR.

C. a Degraded Condition LCOAR.

D. an Outage LCOAR.

Proposed Answer: B Explanation:

Technical

Reference:

ODA-308, 4.2 and 4.11 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified ADM.XA5.OB12 -

003 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 2 Comments:

RO TEST QUESTION #: 93

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 2 2 K/A # 2.2.11 Importance Rating 2.5 3.4 Proposed Question:

WHICH ONE (1) of the following activities is considered a temporary modification?

A. Sample tubing connected to a sample port.

B. Installing a pressure gauge on an instrument tap.

C. A hose connected to a drain valve to route drainage to a floor drain.

D. Installation of a portable space heater to maintain operability of a safety related valve.

Sample tubing connected to a sample port.

Proposed Answer: D Explanation:

Technical

Reference:

STA-602 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 5496 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 3 Comments:

RO TEST QUESTION #: 94

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 3 3 K/A # 2.3.2 Importance Rating 2.5 2.9 Proposed Question:

An uncontrolled radiation release is in progress, which is projected to result in offsite, thyroid dose equivalents significantly in excess of the 10 CFR 100 limits. Manual action is required in order to isolate the release path. Various combinations of personnel could accomplish the task, but only 20 qualified individuals are available to perform the actions in a timely manner.

From the following list, select the number of individuals performing the task that meets both the Protective Action Guides for emergency workers and the ALARA guidelines.

A. Four individuals each receive a dose equivalent of 30 rems.

B. Ten individuals each receive a dose equivalent of 15 rems.

C. Twenty individuals each receive a dose equivalent of 10 rems.

D. Five individuals each receive a dose equivalent of 20 rems..

Proposed Answer: D Explanation:

Technical

Reference:

EPP-305, STA-651 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified MCO.MIB.OB101

- 001 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 12 55.43 4 Comments:

RO TEST QUESTION #: 95

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 3 3 K/A # 2.3.4 Importance Rating 2.5 3.1 Proposed Question:

A nineteen (19) year old new employee received 360 mrem during the current quarter (2250 mRem for the calendar year) at the Monticello Nuclear Generating Station before being hired here. Which one of the following is the MAXIMUM additional exposure the new employee may receive throughout the remainder of the calender year with an ADMINISTRATIVE annual dose level extension?

A. No additional exposure is permitted.

B. 1750 mRem.

C. 1390 mRem.

D. 2000 mRem.

Proposed Answer: B Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 2834 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 12 55.43 4 Comments:

RO TEST QUESTION #: 96

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 4 4 K/A # 2.4.39 Importance Rating 3.3 3.1 Proposed Question:

You are a licensed Reactor Operator on dayshift, working on outage tagouts in the Work Control Center. You do not have assigned responsibilities in the Emergency Response Organization (ERO). A transient occurs that results in the declaration of an ALERT Emergency and activation of the Evacuation Alarm. To which of the following locations do you report?

A. The Technical Support Center (TSC).

B. The Emergency Operations Facility (EOF).

C. The Control Room.

D. The Operations Support Center (OSC).

Proposed Answer: C Explanation:

Technical

Reference:

CPSES/EP Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 5 Comments:

RO TEST QUESTION #: 97

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 4 4 K/A # 2.4.46 Importance Rating 3.5 3.6 Proposed Question:

The plant is in an emergency condition, and you have completed the immediate action steps of EOP-0.0A, "Reactor Trip or Safety Injection". MSIV 1, 3 and 4 Hydraulic Trouble N2 low pressure and MSIV NOT OPEN alarm windows have just illuminated. It is noted that S/G #2 pressure is approximately 600 psig, and that both the pressure and level in S/G #2 are rapidly decreasing. Pressures in the other S/Gs are approximately 740 psig and are decreasing very slowly. Levels in the other S/Gs are constant.

In response to these S/G conditions, which of the following should you perform?

A. Increase AFW flow to S/G #2 to stabilize level.

B. Check secondary radiation levels to determine if a SGTR is indicated.

C. Open S/Gs #1, #3 and #4 atmospheric relief valves to reduce RCS temperature.

D. Check that the MSIVs and bypass valves are closed.

Proposed Answer: D Explanation:

Technical

Reference:

EOP-0.0A/B Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified EO2.XG4.OB407

- 002 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 5 Comments:

RO TEST QUESTION #: 98

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 4 4 K/A # 2.4.47 Importance Rating 3.4 3.7 Proposed Question:

Given the following conditions:

- The crew is performing a reactor startup.

- The RO has just pulled the control rods several steps and is waiting for source range counts to stabilize.

Assuming the reactor is very close, but not yet critical, source range counts should:

A. stop increasing and stabilize immediately, with SUR dropping to zero.

B. begin to slowly decrease, with SUR gradually decreasing to zero.

C. continue to increase, but at a slower rate, with SUR stabilizing at a lower positive value.

D. continue to increase for a short period of time, then plateau, with SUR decreasing to zero.

Proposed Answer: D Explanation:

Technical

Reference:

IPO-002, SECTION 5.2 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.EC1.OB13-3 d New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 5 Comments:

RO TEST QUESTION #: 99

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 4 4 K/A # 2.4.25 Importance Rating 2.9 3.4 Proposed Question:

The following unit conditions exist:

-MODE 1: 100% equilibrium power

-All systems in automatic

-Shift staffing normal

-A fire has occurred in one of the control room panels The Shift Manager has made and announced the decision to evacuate the control room. Which of the following actions is to be performed prior to exiting the control room in accordance with ABN-803A "Response to a Fire in the Control Room or Cable Spreading Room"?

A. Take the turbine-driven AFW pump Trip Throttle Valve control switch to TRIP.

B. Place the feeder breakers for 1EA2 to Pull-Out.

C. Place the VCT inlet valve controller for LCV-112A to DIVERT/HUT.

D. Take the pressurizer spray valves controllers to CLOSE.

Proposed Answer: A Explanation:

Technical

Reference:

ABN-803A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.FP1.OB401 -

006 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 5 Comments:

RO TEST QUESTION #: 100

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.1.074.EA1.24 Importance Rating 3.6 3.8 Proposed Question:

The plant is responding to an inadequate core cooling condition with core exit thermocouples greater than 1200°F. From the choices below, select the choice that lists the best recovery technique in the correct priority for this condition.

A. Start ECCS, depressurize secondary, start RCP, depressurize RCS.

B. Start RCP, depressurize RCS, depressurize secondary, start ECCS.

C. Trip RCPs, trip turbine, depressurize secondary, isolate accumulators.

D. Start ECCS, depressurize RCS, trip RCPs, depressurize secondary.

Proposed Answer: A Explanation:

Technical

Reference:

FRC-0.1A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified MCO.MI3.OB105-005 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 1

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.1.038.EA1.37 Importance Rating 3.5 3.4 Proposed Question:

An operator could cause a Steam Generator Tube Rupture to become a Pressurized Thermal Shock concern by:

A. not terminating the required cooldown in a timely manner.

B. isolating the ruptured steam generator too soon.

C. terminating safety injection before the criteria is met.

D. not depressurizing the RCS before the initial cooldown.

Proposed Answer: A Explanation:

Technical

Reference:

EOP-3.0A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SK2.XG4.OB103 -

001 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 2, 5 Comments:

(originally #101)

SRO (ONLY) TEST QUESTION #: 2

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.005.AA1.05 Importance Rating 3.4 3.4 Proposed Question:

During a Reactor startup with Control Bank D at 20 steps and the Reactor subcritical, the DRPI ROD DEV annunciator is received. The Reactor Operator observes that Control Bank B rod F2 indicates 210 steps while Control Bank B Group 1 step counter indicates 228 steps. No other alarms are received and all other parameters indicate normal. This event would require the crew to:

A. Consider the rod misaligned and within one hour insert all Control Banks to Control Bank Offset (CBO).

B. Consider the rod misaligned and continue rod withdrawal to reach Critical conditions then realign the rod.

C. Consider the rod misaligned and compare DRPI and Step Counter positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D. Consider the rod misaligned and implement the requirements of Technical Specifications 3.0.3.

Proposed Answer: A Explanation:

Technical

Reference:

ABN-712 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.CR1.OB15- 4 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 3

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.067.AA1.05 Importance Rating 3.0 3.1 Proposed Question:

The Control Room Ventilation System has been aligned for Control Room Recirculation due to a large fire in a field adjacent the plant. The Unit Supervisor checks the logs and realizes that the ventilation system has been in recirc for approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Which of the following statements describes the situation in the Control Room?

A. The humidity in the Control Room has dropped dangerously low due to too much time operating on recirc.

B. The carbon monoxide level in the Control Room is increasing due to too much time operating on recirc.

C. The air quality in the Control Room has been polluted by contaminants from the fire due to too much time operating on recirc.

D. The carbon dioxide level in the Control room is increasing due to too much time operating on recirc.

Proposed Answer: D Explanation:

Technical

Reference:

SOP-802 Control Room Ventilation System Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 4

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.068.AA1.14 Importance Rating 4.2 4.4 Proposed Question:

A fire in the control room with heavy smoke requires immediate evacuation of the control room. Unit 1 was at 95% power at the time the evacuation procedure was initiated. The Unit 1 Reactor Operator was only able to trip the turbine prior to exiting the control room.

Assuming that the plant responds as expected, which ONE of the following local actions needs to be taken to complete the RO's initial evacuation assignments?

A. Open the Reactor Trip Breakers.

B. Isolate the Main Steam lines.

C. Remove pressurizer PORV fuses.

D. Isolate dilution paths and S/G Process Sampling.

Proposed Answer: B Explanation:

Technical

Reference:

ABN-803A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 2703 Modified X New Question History: Last NRC Exam Prairie Island 1(WEC), 6/16/1997 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 8, 10 55.43 5 Comments:

Modifications: clarified stem, and adapted distracters to CPSES, and replaced one distracter.

RO/SRO TEST QUESTION #: 5

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.068.AA2.10 Importance Rating 4.2 4.4 Proposed Question:

A bomb threat has forced a control room evacuation. Prior to the bomb threat, the plant was operating steady at 100%. The relevant control room actions directed by ABN-905A "Loss of Control Room Habitability" were completed and plant operations have been transferred to the Remote Shutdown Panel (RSP). When the Reactor Operator arrives at the RSP, he should expect to see the following indications:

A. Neutron flux decreasing steadily and rod bottom lights on.

B. Neutron flux and rods at approximately the level they were when he left the control room.

C. Neutron flux decreasing steadily and the reactor trip breakers are open.

D. Neutron flux at approximately the level it was before he left the control room and reactor trip breakers closed.

Proposed Answer: C Explanation:

ABN-905A directs a reactor trip prior to leaving the control room, and rod bottom lights are not indicated at the RSP. The RO can observe both neutron flux decreasing, and reactor trip breakers open from the RSP.

Technical

Reference:

ABN-905A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 1, 6, 10 55.43 Comments:

RO/SRO TEST QUESTION #: 6

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.076.AA2.03 Importance Rating 2.5 3.0 Proposed Question:

Unit 1 was at 35% power during a plant shutdown when a 20% load rejection occurred. The plant has been stabilized, and the shutdown is continuing. The daily RCS chemistry sample has been analyzed and the RCS specific activity determined to be 0.1 uc/gm Dose Equivalent I-131. The previous sample had a specific activity of 0.01 uc/gm Dose Equivalent I-131. Which one of the below statements identifies the required response?

A. Be in mode 3 condition with Tave less than 500 degrees F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

B. Initiate a Safety Injection and enter EOP-0.0A.

C. Obtain and analyze a plant vent grab sample.

D. Continue with plant operations as planned, there is no required response to the stated conditions.

Proposed Answer: C Explanation:

Technical

Reference:

IPO-004A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified IPO.XO4.OB900

- 002 X New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 5 Comments:

Modifications: altered two distractors.

RO/SRO TEST QUESTION #: 7

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.076.AA2.04 Importance Rating 2.6 3.0 Proposed Question:

The Liquid Waste Processing Effluent Radiation Monitor High Radiation alarm has been received. Which of the following is the correct action for the operator to take initially?

A. Ensure X-RV-5251 is closed or close its upstream isolation valve.

B. Reopen X-RV-5251 and ensure correct pump is running.

C. Reopen X-RV-5253 and ensure correct pump is running.

D. Ensure X-RV-5253 is closed or close its upstream isolation valve.

Proposed Answer: D Explanation:

Technical

Reference:

ALM-301, ABN-903 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.WP1.OB12 -

003 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 5 Comments:

RO/SRO TEST QUESTION #: 8

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.027.G.2.4.2 Importance Rating 3.9 4.1 Proposed Question:

The following SEQUENTIAL events have just occurred:

- charging flow decreased to minimum,

- pressurized level decreased,

- letdown isolated and heaters turned off,

- pressurized level increased to high level reactor trip.

Pressurizer level control selector switch is in the LT-459 position and pressure control is on PT-455. No operator actions have been taken. Which failure has occurred?

A. Pressure Channel 455 failed high.

B. Pressure Channel 455 failed low.

C. Level channel 459 failed high.

D. Level channel 459 failed low.

Proposed Answer: C Explanation:

Technical

Reference:

LO21.RLS.IC3.LN Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified MCO.TA3.OB103

- 002 X New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Modifications: altered two of the distracters.

RO/SRO TEST QUESTION #: 9

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.1.055.EK1.02 Importance Rating 4.1 4.4 Proposed Question:

Unit 1 has just experienced a station blackout and a subsequent reactor trip. According to EOS-0.1A "Reactor Trip Response," all of the following are indications of natural circulation flow EXCEPT:

A. Steam generator pressures are stable or decreasing B. Pressurizer pressure is stable or decreasing C. Core exit thermocouple temperatures are stable or decreasing D. RCS cold leg temperatures at saturation temperature for S/G pressure Proposed Answer: B Explanation:

Technical

Reference:

EOS-0.1A Attachment 3 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 10526 Modified X New Question History: Last NRC Exam Indian Point 3 (WEC), 4/15/1996 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8, 10 55.43 Comments:

Modifications: adapted to CPSES terminology, and replaced one distracter.

RO/SRO TEST QUESTION #: 10

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.067.AK1.01 Importance Rating 2.9 3.9 Proposed Question:

While you are on shift on Saturday night, an equipment operator calls the control room and informs you that he has found a fire smoldering in an electrical panel. If available, the preferred method for fighting this type of fire is:

A. halon.

B. foam.

C. water fog/spray.

D. dry powder extinguisher.

Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 5378 Modified New Question History: Last NRC Exam Salem 1(WEC), 1/22/1996 Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8, 10 55.43 Comments:

RO/SRO TEST QUESTION #: 11

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.069.AK1.01 Importance Rating 2.6 3.1 Proposed Question:

The following plant conditions exist:

o Procedure in effect EOP-1.0B.

o Containment pressure 65 psig and increasing.

You transition to FRZ-0.1B, "Response to High Containment Pressure" and upon completion of all steps in FRZ-0.1B, you determine that containment pressure is now 61 psig. At this point, you are required to:

A. reinitiate and remain in FRZ-0.1B until the condition is no longer an ORANGE priority.

B. exit FRZ-0.1B and enter EOS-0.0B.

C. reinitiate and remain in FRZ-0.1B until the condition is no longer a RED priority.

D. exit FRZ-0.1B and return to EOP-1.0B at the step in effect.

Proposed Answer: D Explanation:

Technical

Reference:

FRZ-0.1B, and ODA-407 Guideline on Use of Porcedures Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8, 10 55.43 5 Comments:

RO/SRO TEST QUESTION #: 12

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.5.E09.EK1.02 Importance Rating 3.3 3.7 Proposed Question:

Which of the below most correctly completes the following statement regarding natural circulation?

Natural Circulation flowrate will be greater if...

A. ONE reactor coolant pump runs for an hour after the reactor trip, then stops."

B. ALL reactor coolant pumps run until the plant is in mode 4, then stop."

C. ALL reactor coolant pumps stop at the same time the reactor trips.

D. ALL reactor coolant pumps run for an hour after the reactor trip, then stop."

Proposed Answer: C Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SJ2.XG7.OB104 -

002 X New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8, 10 55.43 Comments:

Modifications: several distracters altered.

RO/SRO TEST QUESTION #: 13

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.068.AK2.03 Importance Rating 2.9 3.1 Proposed Question:

Unit 2 is currently in mode 4, but a transition into mode 3 is planned for later today. During conduct of the Pressurizer Pressure Control Remote Shutdown Operability Test, it is discovered that the PRZR HTR BACKUP GROUP A CTRL XFER (STP) switch fails to properly transfer control of the heaters to the HSP. Regarding the planned transition to mode 3, A. Technical Specifications require that the plant remain in mode 4 until the transfer switch is restored to operability.

B. Technical Specifications allow the plant to proceed into mode 3 while repairs are made to the transfer switch.

C. Technical Specifications do not address this transfer switch, so the mode change is unaffected by its failure.

D. Technical Specifications require that the plant be placed in mode 5 until the transfer switch is restored to operability.

Proposed Answer: B Explanation:

TS allows mode increase while in LCO related to Remote Shutdown Transfer switches.

Technical

Reference:

OPT-216A Remote Shutdown Operability Test, TS 3.3.4 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 Comments:

SRO (ONLY) TEST QUESTION #: 14

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.2.051.AK3.01 Importance Rating 2.8 3.1 Proposed Question:

Given the following Unit 1 plant conditions:

o Unit was initially at 100% power and has been manually tripped.

o Tave is 542F on all channels.

o "A" Condenser vacuum is 14" vacuum o "B" Condenser vacuum is 18" vacuum o two Circ water pumps are running Which ONE of the following describes steam dump availability?

A. Only the atmospheric dumps are available.

B. Steam dump is NOT available.

C. Only the condenser dump is available.

D. Both atmospheric and condenser dumps are available Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 2694 Modified New Question History: Last NRC Exam Prairie Island 1 (WEC) 6/16/1997 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

RO/SRO TEST QUESTION #: 15

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 1 1 K/A # 4.5.E07.EK3.01 Importance Rating 3.1 3.7 Proposed Question:

Given the following:

-The RCS has had a stuck open Pressurizer safety valve.

-The reactor tripped and safety injection initiated.

-The RCS rapidly depressurized to saturation conditions.

-Pressurizer level initially dropped and then began to rise rapidly.

Which one of the following characterizes the relationship between pressurizer level and RCS inventory under these conditions?

A. Level is an accurate indication of inventory, because voiding would occur first in the pressurizer due to the high temperature of the pressurizer walls.

B. Level is an accurate indication of inventory, because hydraulic pressure would force any voids to the pressurizer steam space and out the safety valve.

C. Level is NOT an accurate indication of inventory, because RCS voiding may result in a rapidly increasing pressurizer level.

D. Level is NOT an accurate indication of inventory, because at higher temperatures the cold calibrated pressurizer level channels falsely indicate high.

Proposed Answer: C Explanation:

Technical

Reference:

EOS-1.2A, step 14 caution Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified EO1.XG3.OB900 -4 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

RO/SRO TEST QUESTION #: 16

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.1.029.EA1.03 Importance Rating 3.5 3.2 Proposed Question:

Given the following plant conditions:

- The unit was at 100% power

- A condition requiring a trip was diagnosed

- The operators are using FRS-0.1A, "Response to Nuclear Power Generation/ATWT", to respond to an ATWT

- The Turbine is tripped

- Emergency Boration valve 1/1-8104 has failed to open Which ONE of the following describes the actions that the operator is required to perform?

A. Open RWST supply to CCPs 1/1 LCV-112D and 1/1 LCV-112E, and shut VCT supply to CCPs 1/1 LCV-112B and 1/1 LCV-112C.

B. Open VCT supply to CCPs 1/1 LCV-112B and 1/1 LCV-112C, and shut RWST supply to CCPs 1/1 LCV-112D and 1/1 LCV-112E.

C. Open RWST supply to CCPs 1/1 LCV-112D, and shut VCT supply to CCPs 1/1 LCV-112B.

D. Open VCT supply to CCPs 1/1 LCV-112B, and shut RWST supply to CCPs 1/1 LCV-112D.

Proposed Answer: A Explanation:

Technical

Reference:

FRS-0.1A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 17

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.5.E02.EA1.01 Importance Rating 4.0 3.9 Proposed Question:

Unit 1 and Unit 2 have experienced a Reactor trip and a loss of offsite power. Unit 2 systems and equipment functioned as required. The following complications were experienced on Unit 1:

-The Train B Diesel Generator was tagged out for maintenance and Train A Diesel Generator started and supplied the 6.9 safeguards bus as required. An inadvertent Safety Injection has occurred.Train A CCP tripped on restart as the Blackout Sequencer fired.

-During the response actions of EOS-1.1A, "Safety Injection Termination", the Unit Supervisor identifies a caution that states "If RCP seal cooling had previously been lost, the affected RCP(s) should not be started prior to a status evaluation".

Which of the following is the appropriate recovery actions of EOS-1.1A for the conditions as described in this event?

A. RCP seal injection valves are isolated. The PD pump is loaded on the Train A electrical bus to provide normal charging. Following restoration of non-safeguards power, RCPs are not started prior to an engineering evaluation.

B. RCP seal injection valves are isolated. The PD pump is load shed on an SI signal and is not available to reload until the automatic SI signal is reinstated. Following restoration of non-safeguards power, RCPs are not started prior to an engineering evaluation.

C. The PD pump is manually loaded on the Train A electrical bus to provide normal charging and seal injection. Following restoration of non-safeguards power, the RCP can be started in accordance with RCP operating instructions without an engineering evaluation.RCP seal injection valves are isolated.

D. The PD pump is load shed on an SI signal and is not available to reload until the automatic SI signal is reinstated. Following restoration of non-safeguards power, RCPs can be started without an engineering evaluation.

Proposed Answer: C Technical

Reference:

EOS-1.1A, STEP 26 CAUTION, EOP-0.0A, ATT. 9 Question Source: Bank # CPSES Modified SJ1.XG9.OB107-1 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 18

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.5.E02.EA2.01 Importance Rating 3.3 4.2 Proposed Question:

Given the following:

o A Turbine/Generator trip has caused a Reactor trip.

o The operators are in EOS-0.1A, "Reactor Trip Response," at step 1, "Check RCS Average Temperature - Stable at or Trending to 557 F."

o RCS pressure is 1822 psig.

o Pressurizer level is 22% and stable.

o Core exit T/Cs are 610 F and slowly rising.

o Containment pressure is 1.5 psig.

o All S/G NR levels are 20% and slowly rising.

Which of the following actions should be taken?

A. Transition to FRZ-0.1A,"Response to High Containment Pressure."

B. Dump steam to the Condenser and proceed to step 2 of EOS-0.1A.

C. Transition to FRH-0.1A, "Response to Loss of Secondary Heat Sink."

D. Initiate SI and go to EOP-0.0A," Reactor trip or Safety Injection," step 1.

Proposed Answer: D Explanation:

The fold-out for EOS-0.1A requires initiation of SI at less than 25 degrees subcooling; with the RCS at 1822 psig and 610 degrees, that criteria is just satisfied.

Technical

Reference:

EOS-0.1A and Steam Tables Proposed references to be provided to applicants during examination:

Steam Tables Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

SRO (ONLY) TEST QUESTION #: 19

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.1.009.EA2.01 Importance Rating 4.2 4.8 Proposed Question:

The plant is recovering from a loss of coolant accident in accordance with EOP-1.0A Loss of Reactor or Secondary Coolant with current conditions as follows:

-SI Pump Status: Both On

-RCP Status: ALL On

-RCS Pressure: 1987 psig and Stable

-Highest T-hot: 552 degrees F and Stable

-Highest CET: 560 degrees F and Stable

-Pressurizer Level: 34% and Increasing

-1A S/G Narrow Range Level: 12% and Stable

-1B S/G Narrow Range Level: 17% and Decreasing

-Total AFW Flow: 100 gpm

-Containment Pressure: 5 psig Which ONE of the following actions should be taken?

A. Stop all running RCPs B. Transition to FRZ-0.1A Response to High Containment Pressure C. Increase Total AFW flow to > 200 gpm D. Transition to EOS-1.1A SI Termination Proposed Answer: D Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 10764 Modified X New Question History: Last NRC Exam Kewaunee 1 (WEC), 12/18/1997 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 5 Comments:

Modifications: replaced one distracter.

RO/SRO TEST QUESTION #: 20

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.2.061.AA2.03 Importance Rating 3.0 3.3 Proposed Question:

The Containment Critical Safety Function Status Tree requires operators to immediately transition to a Function Restoration Procedure in the event of an imminent challenge to containment integrity. The condition that represents an imminent challenge to containment integrity is:

A. containment sump water level at 716 ft.

B. containment pressure at 19 psig.

C. containment temperature at 215 degrees F.

D. containment radiation at than 22 R/hr.

Proposed Answer: B Explanation:

Technical

Reference:

ERG-HP/LP Background, FRZ-0.1A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified MCO.MIF.OB103

- 003 X New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8 55.43 5 Comments:

Modifications: altered all distracters.

RO/SRO TEST QUESTION #: 21

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.1.038.3EA2.11 Importance Rating 3.7 3.9 Proposed Question:

During the diagnostic steps of EOP-0.0 following a manual Reactor trip and SI due to a slowly decreasing Pressurizer level, the BOP notices that the Main Steam Line Radiation Monitor for one of the Steam Generators had been in alarm, but is now reading only slightly above normal on the PC-11 trends. Which statement below is correct?

A. The trend is correct because when the Reactor and Turbine were tripped, the steam flow through the detector decreased resulting in the lower reading.

B. The trend is correct because while the Reactor was critical, N-16 was being produced and entering the SG through a leak. The N-16 has now decayed away resulting in a lower reading.

C. The trend is correct because the Main Steam Line Radiation Monitors are isolated on the SI signal resulting in the decreased reading.

D. The trend is incorrect because if the radiation monitor was in alarm, the trend should continue to increase as the Krypton and Xenon reach a new higher equilibrium value until the leak is stopped.

Proposed Answer: B Explanation:

Technical

Reference:

SOER 93-1, PALO VERDE SGTR Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.RM1.OB13-6 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 11 55.43 5 Comments:

RO/SRO TEST QUESTION #: 22

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.1.011.G.2.4.18 Importance Rating 2.7 3.6 Proposed Question:

A Large Break Loss of Coolant Accident (LBLOCA) has occurred and all RCS hot leg temperatures indicate 385°F. Why should the SI Accumulators Injection Valves be closed at this time?

A. Ensures that the RCS saturation pressure for 385°F does NOT exceed the SI Accumulator pressure after the accumulator water has been discharged.

B. Prevents overpressurization of Containment, which could occur if the nitrogen in the Accumulators was allowed to enter the RCS and exit via the break.

C. Ensures adequate volume of borated water and nitrogen have been injected to recover the Core with liquid and inert the hydrogen gas contained within the RCS and Containment.

D. Prevents further nitrogen injection into the RCS which could impede further RCS depressurization.

Proposed Answer: D Explanation:

Technical

Reference:

EOP-1.0A STEP 14 BASIS Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.SI1.OB16-2 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

RO/SRO TEST QUESTION #: 23

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.5.E02.EK1.02 Importance Rating 3.4 3.9 Proposed Question:

Following a LOCA, if the SI accumulators cannot be isolated, the correct action is to:

A. continue with the following steps, since isolation is not required.

B. drain the SI accumulators.

C. sample the pressurizer steam space for noncondensibles.

D. vent the SI accumulators.

Proposed Answer: D Explanation:

Technical

Reference:

EOP-1.0A, STEP 15 BASIS Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified ERG.XDD.OB103-1 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8, 10 55.43 Comments:

RO/SRO TEST QUESTION #: 24

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.5.E04.EK1.01 Importance Rating 3.5 3.9 Proposed Question:

ECA-1.2A, "LOCA Outside Containment", alerts the operator that some points of the system are a high probability for a LOCA. Which of the below has the highest probability for a LOCA outside containment?

A. CCW piping interface with RCP Seals B. RHR low pressure piping arrangement C. SI to RHR cross-tie piping arrangement D. SI piping and injection lines to the RCS Proposed Answer: B Explanation:

Technical

Reference:

ECA-1.2A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SM1.XGH.OB102-1 X New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8, 10 55.43 Comments:

Modification: altered one distracter.

RO/SRO TEST QUESTION #: 25

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.5.E01.EK2.01 Importance Rating 3.3 3.5 Proposed Question:

In accordance with the information provided on the foldout page of EOS-0.0A, "Rediagnosis" operators should proceed to FRZ-0.1A, "Response to High Containment Pressure," if:

A. containment pressure indicates > 50 psig.

B. containment pressure is > 5 psig, and level in all SGs is < 5% (NR).

C. containment pressure indicates >5 psig.

D. containment pressure is >15 psig and containment spray is not on.

Proposed Answer: A Explanation:

Technical

Reference:

EOS-0.0A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SJ1.XG5.OB105 -

002 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 26

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.5.E01.EK2.02 Importance Rating 3.5 3.8 Proposed Question:

Unit 2 is operating in EOP-0.0B, REACTOR TRIP OR SAFETY INJECTION. The Reactor is tripped and safety injection has actuated. The following plant indications and responses are observed;

• Containment pressure is 8 psig and rising.

• RCS subcooling is 57°F.

• Both CCPs and SIPs are running.

• Both CCWPs are running.

• Pressurizer level is 13%.

• Pressurizer pressure is 1815 psig.

• Two banks of steam dumps are open.

• Tave is 563 and rising.

Based on the above information, from the list below SELECT the required action.

A. Increase auxiliary feedwater flow to the steam generators.

B. Take manual control of steam dumps and increase demand.

C. Take manual control of SG ARVs and throttle to control temperature.

D. Allow SG ARVs to automatically control temperature..

Proposed Answer: C Technical

Reference:

EOP-0.0B Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified EO0.XG2.OB402-2 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 27

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.2.001.AK2.05 Importance Rating 2.9 3.1 Proposed Question:

Unit 1 is steady with reactor power at 90%. All systems are operating normally with the rod control system in automatic. Without warning, the rods begin to step and Tavg begins to increase above Tref, which remains constant. Pressurizer pressure and level also begin to increase.

These symptoms are consistent with which of the following?

A. PRZR pressure control system failure B. Main turbine/generator load increase C. Continuous rod insertion D. Continuous rod withdrawal Proposed Answer: D Explanation:

Technical

Reference:

ABN-712A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.CR1.OB09-1 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 28

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.5.E05.EK3.01 Importance Rating 3.4 3.8 Proposed Question:

What adverse consequence could result from delaying feed and bleed cooling if the conditions are met in FRH-0.1B Response to Loss of Secondary Heat Sink?

A. Inability to provide sufficient injection for core cooling due to high RCS pressure.

B. High temperature induced failure of U-tube bends C. RCP seal failure D. Inablity to recover the SGs without damage from high thermal stresses.

Proposed Answer: A Explanation:

Technical

Reference:

FRH-0.1B Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 8340 Modified New Question History: Last NRC Exam Ginna 1 (WEC), 5/8/1996 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

RO/SRO TEST QUESTION #: 29

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.5.E16.EK3.01 Importance Rating 2.9 3.1 Proposed Question:

Unit 2 is operating at 100% power. Over twelve hours the following plant indications and responses were observed in the control room;

• Containment humidity increased slightly

• Containment radiation increased slightly

• Containment dew point increased slightly

• Containment sump pumps have operated 1 time every hour.

• Automatic makeup to the VCT occurred 7 times.

• Letdown was maintained at 70 gpm and charging went from 82 gpm to 78 gpm.

• Pressurizer level has remained at 60%.

• Pressurizer pressure has trended from 2235 psig to 2220 psig and stabilized.

• No other abnormal alarms are annunciated.

Based on the above indications the operating crew entered ABN-103 and the following actions were taken;

• Radiation Protection was contacted to investigate containment radiation.

• Preparations are in progress to make a containment entry.

• Radiation Protection and Radwaste were notified that containment sumps would be left in operation to the WHT.

• Letdown and charging have been isolated and then realigned for normal operation.

• OPT-303 has been performed and unidentified leakage is 6 gpm.

• Preparations are being made to commence a reactor shutdown.

Based on the above information, SELECT from the list below the source of the unidentified leakage.

A. Reactor Coolant System cold leg leak.

B. Reactor Coolant System hot leg leak.

C. Pressurizer vapor space leak.

D. The yellow condition guideline must be implemented immediately due to plant conditions.

Proposed Answer: C Technical

Reference:

ABN-103A Question Source: Bank # CPSES Modified SYS.RC1.OB14 010 New Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

RO/SRO TEST QUESTION #: 30

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 1 K/A # 4.5.E01.EK3.02 Importance Rating 3.0 3.9 Proposed Question:

Which of the below most correctly completes the following statement regarding natural circulation?

"Natural circulation flowrate will be greater if..

A. reactor coolant pumps stop at the same time the reactor trips"..

B. ALL reactor coolant pumps run for an hour after the reactor trip, then stop".

C. one reactor coolant pump runs for an hour after the reactor trip, then stops".

D. two reactor coolant pumps run for an hour after the reactor trip, then stop".

Proposed Answer: B Explanation:

Technical

Reference:

EOS-0.0A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SJ1.XG5.OB101 -

001 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

RO/SRO TEST QUESTION #: 31

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.2.008.AK3.03 Importance Rating 4.1 4.6 Proposed Question:

EOP-1.0A, "Loss of Reactor or Secondary Coolant," Step 1; "Check if RCPs should be stopped," is a continuous action step. Which ONE of the following is the basis for continuously monitoring for the criteria to perform this step in response to a LOCA?

A. Minimize cooldown rate B. Prevent excessive RCS inventory loss C. Prevent RCP damage from cavitation D. Minimize RCP run time with less than the required subcooling Proposed Answer: B Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank INPO 10769 Modifie

1. d New Question History: Last NRC Exam Kewaunee 1 (WEC), 12/18/1997 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

RO/SRO TEST QUESTION #: 32

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.5.E03.EK3.04 Importance Rating 3.5 3.9 Proposed Question:

Unit 1 Pressurizer level is 89% and the RVLIS 49" above flange lights are dark and the plant computer indicates an INVENTORY yellow condition. The unit has experienced a small break LOCA and plant response is being directed by EOS-1.2A, POST-LOCA COOLDOWN AND DEPRESSURIZATION. ECCS flow has not been terminated. The Unit Supervisor has currently decided not to implement the yellow condition guideline. From the list below SELECT why this is or is not an acceptable decision.

A. Transition has been made from EOP-0.0A, the yellow condition guideline should be implemented when EOS-1.2A is completed.

B. There exist other, more critical plant conditions that should be addressed before implementation of the yellow condition guideline.

C. Voids are not a concern when responding to a small break LOCA.

D. The yellow condition guideline must be implemented immediately due to plant conditions.

Proposed Answer: B Explanation:

Technical

Reference:

FRI-0.3A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified FRI.XH6.OB401 005 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

RO/SRO TEST QUESTION #: 33

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 3 2 K/A # 4.2.065.AA1.05 Importance Rating 3.3 3.3 Proposed Question:

Unit 1 is in MODE 2 with a startup in progress when instrument air header pressure begins decreasing. Attempts to restart and align an instrument air compressor to Unit 1 are unsuccessful and instrument air header pressure reaches 30 psig. The RO opens the Reactor Trip Breakers and the crew enters EOP-0.0. Select the corrective actions to be taken in response to this loss of Instrument air.

Dispatch a PEO to..............

A. close the MSIVs.

B. control charging flow.

C. close the S/G ARVs.

D. control AFW flow.

Proposed Answer: B Explanation:

Technical

Reference:

ABN-301A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.IA1.OB14-005 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 34

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 3 3 K/A # 4.2.028.AA1.07 Importance Rating 3.3 3.3 Proposed Question:

The reactor is critical at 10E-4% power when charging pump suction inadvertently switches from the VCT to the RWST. This occurs for approximately 10 minutes, then is stopped by the operators. Which one of the following describes the comparative effect that this will have on letdown flow?

A. It will decrease the most at EOL.

B. It will decrease the most at BOL.

C. It will not be significantly affected.

D. It will increase the most at BOL.

Proposed Answer: C Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank INPO 194 Modifie

1. d New Question History: Last NRC Exam Arkansas Nuclear 2 (CE), 8/28/1998 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 35

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 3 3 K/A # 4.2.056.AA2.02 Importance Rating 3.5 3.6 Proposed Question:

The plant is recovering from a loss of off-site power. Select the choice below which can be used as an indication that the Blackout Sequencer Operator Lockouts have reset (no longer present).

A. OL light on the associated sequencer is lit.

B. All step lights are lit on both sequencers.

C. Start of RMUW pump on associated train.

D. TD AFW pump steam supply valve opens.

Proposed Answer: C Explanation:

Technical

Reference:

ABN-602A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.ES3.OB11-1 d New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 5 Comments:

RO/SRO TEST QUESTION #: 36

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.7.015.A1.08 Importance Rating 3.3 3.4 Proposed Question:

Which limiting safety system setting provides a correction for changes in density and heat capacity of the reactor coolant system?

A. Overpower Delta T B. Power Range High Flux C. Pressurizer Low Pressure D. Overtemperature Delta T Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank INPO 9124 Modifie X

1. d New Question History: Last NRC Exam Cook 1 (WEC), 7/7/1997 Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 Comments:

Modifications: Replaced one distracter.

RO/SRO TEST QUESTION #: 37

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.5.022.A1.02 Importance Rating 3.6 3.8 Proposed Question:

The Containment internal pressure Technical Specification upper limit ensures that:

A. the containment structure is prevented from exceeding its design negative pressure differential of 5 psid with respect to the outside atmosphere.

B. peak pressure does not exceed the Containment design pressure during a LOCA.

C. excessive quantities of radioactive materials will not be released via the Containment Ventilation System.

D. the structural integrity of the containment will be maintained comparable to the original design standard for the life of the facility.

Proposed Answer: B Explanation:

Technical

Reference:

TS 3.6.4 Bases Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.CL1.OB32 d New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 2 Comments:

SRO (ONLY) TEST QUESTION #: 38

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.5.022.A2.06 Importance Rating 2.8 3.2 Proposed Question:

The containment design criteria are based on limiting the containment leakage rate under design basis accident conditions. According to the limiting containment analysis, containment pressure will:

A. exceed the containment design pressure for a short time, but the containment cooling systems will ultimately restore containment pressure below the design limit.

B. not exceed the containment design pressure initially. However, the analysis assumes a hydrogen burn that results in containment overpressure, which is ultimately controlled by the containment cooling systems.

C. exceed the containment ultimate capacity, leading to a gross failure of the containment structure.

D. not exceed the containment design pressure as long as a single train of containment cooling systems operates to perform its design function.

Proposed Answer: D Explanation:

Technical

Reference:

ERG-HP/LP BACKGROUND, FRZ-0.1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. MCO.MIF.OB102- d 1

New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments:

RO/SRO TEST QUESTION #: 39

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.4.059.A2.04 Importance Rating 2.9 3.4 Proposed Question:

ECA-2.1A/B, "Uncontrolled Depressurization of All Steam Generators," identifies that Auxiliary Feedwater flow to each Steam Generator with a narrow range level of less than 5% must be controlled at a minimum of 100 gpm. Which of the following is the reason for the minimum flow requirement?

A. Prevent Steam Generator tube dryout.

B. Ensure adequate RCS subcooling margin.

C. Maintain a verifiable cooldown rate.

D. Prevent further Steam Generator depressurization.

Proposed Answer: A Explanation:

Technical

Reference:

ECA-2.1A/B STEP 2 AND BASES Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SK1.XG1.OB103- d 1

New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments:

RO/SRO TEST QUESTION #: 40

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.5.E05.EA2.02 Importance Rating 3.7 4.3 Proposed Question:

The plant staff has transitioned from EOP-3.0A (Steam Generator Tube Rupture) to FRC-0.1A (Response to Inadequate Core Cooling) due to an identified red path.

While performing FRC-0.1A, a red path for loss of secondary heat sink occurs.

Which of the following gives the correct operator action?

A. Complete FRC-0.1A and then transition to FRH-0.1A (response to Loss of Secondary Heat Sink)

B. Complete FRC-0.1A and then return to EOP-3.0A C. Transition immediately to FRH-0.1A and upon completion return to FRC-0.1A D. Transition immediately to FRH-0.1A and upon completion return to EOP-3.0A Proposed Answer: A Explanation:

Technical

Reference:

FRC-0.1, OCA-407 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. FRC.XH2.OB404- d 1

New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

(originally #102)

SRO (ONLY) TEST QUESTION #: 41

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.2.004.A2.19 Importance Rating 2.8 3.5 Proposed Question:

During oxygen scavenging in the RCS, the CVCS demineralizers flow is:

A. maximized to aid in removal of the ammonia which is created by the evolution.

B. bypassed to prevent the creation of ammonia from the added hydrazine.

C. maximized to aid in removal of chlorides and fluorides from the RCS.

D. bypassed to prevent the removal of the added hydrazine before it can remove the oxygen.

Proposed Answer: D Explanation:

Technical

Reference:

IPO-001 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. IPO.XO1.OB900- d 6

New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments:

RO/SRO TEST QUESTION #: 42

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.4.061.A3.02 Importance Rating 4.0 4.0 Proposed Question:

Given the following:

-ECA-2.1A, Uncontrolled Depressurization of All Steam Generators, has been entered.

-SGs 1, 3, and 4 narrow range levels are 20%.

-SG 2 narrow range level is 40%.

-RCS pressure is 1200 psig and decreasing.

-RCS subcooling is 42 degrees F.

-Containment pressure is 14 psig.

-RCS cooldown rate is greater than 100 degrees F/hour.

Which one of the following actions should be taken for the given conditions?

A. Stop AFW flow to all SGs until cooldown rate is less than 100 degrees F/hour.

B. Reduce AFW flow to SGs 1, 3, and 4 to 100 gpm until cooldown rate is less than 100 degrees F/hour.

C. Stop AFW flow to SGs 1, 3, and 4 until cooldown rate is less than 100 degrees F/hour.

D. Reduce AFW flow to SG 2 to 100 gpm and stop AFW flow to SGs 1, 3, and 4 until cooldown rate is less than 100 degrees F/hour.

Proposed Answer: B Explanation:

Technical

Reference:

ECA-2.1A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. EO2.XG4.OB900 d 001 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 43

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.2.004.A3.12 Importance Rating 3.0 2.7 Proposed Question:

TCV-129 protects the BTRS demineralizers by:

A. shutting the BTRS isolation valves at 155°F upstream of the BTRS demineralizers.

B. diverting CVCS letdown flow to the VCT which stops flow through BTRS at 155°F upstream of the BTRS demineralizers.

C. starting the BTRS chiller at 155°F upstream of the BTRS demineralizers.

D. TCV-129 does not protect the BTRS demineralizers.

Proposed Answer: B Explanation:

Technical

Reference:

SOP-106A SECTION 4.0 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.BT1.OB900 d 016 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 44

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.2.060.AA2.04 Importance Rating 2.6 3.4 Proposed Question:

Which of the following are considered as a Gaseous Radioactive Effluent Release source per the ODCM?

A. U1 Containment Purge B. Fuel Building Ventilation C. Auxiliary Building Ventilation D. U2 Condenser Off Gas Proposed Answer: A Explanation:

Technical

Reference:

ODCM Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. ADM.XA8.OB02 d 002 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

(originally #103)

SRO (ONLY) TEST QUESTION #: 45

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.4.059.A4.11 Importance Rating 3.1 3.3 Proposed Question:

Which ONE of the following Feedwater Isolation Signals (FWI) must be manually reset by pushing the FWI reset pushbuttons before the feedwater isolation valves may be opened?

A. Containment Isolation B. Safety Injection C. Hi-Hi Steam Generator Level D. P-4 coincident with Lo Tave.

Proposed Answer: D Explanation:

Technical

Reference:

SOP-302A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.MF1.OB07 - d 002 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 46

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.9.068.G.2.3.4 Importance Rating 2.5 3.1 Proposed Question:

A discharge permit is being routed to discharge Plant Effluent Holdup and Monitor Tank to Outfall 004. Which of the following Post NID QA Analysis results require that the radwaste supervisor be notified?

A. Antimony (Sb) - 1.5 E-6 uci/ml B. Cobalt (Co) - 2.3 E-7 uci/ml C. Cesium (CS) - 1.0 E-5 uci/ml D. Iodine (I) - < MDA Proposed Answer: C Explanation:

Technical

Reference:

RWS-103 ATT9 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.WP1.OB07 d 001 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 4 Comments:

RO/SRO TEST QUESTION #: 47

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.7.015.K1.03 Importance Rating 3.1 3.1 Proposed Question:

A normal reactor startup is planned for the unit following maintenance on excore nuclear instrumentation. Believing a problem may still exist, the RO is directed to closely observe source range operation throughout the evolution. Which one of the following is an indicator that the source range channel failed high during the reactor startup? Assume that the reactor trips.

A. Rod withdrawal block B. P-6 energized C. P-10 energized D. Flux Doubling Alarm is lit Proposed Answer: D Explanation:

Technical

Reference:

ALM-0064 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.EC1.OB10-2 d New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2, 9 55.43 Comments:

RO/SRO TEST QUESTION #: 48

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.5.E.16.EK1.03 Importance Rating 3.0 3.3 Proposed Question:

While responding to a loss of coolant accident, the Unit 2 Unit Supervisor directs the Reactor Operator to maintain Steam Generator level between 18% and 50% Narrow Range. Which of the following would require this level to be maintained?

A. Containment radiation 3x104 R/hr B. Containment pressure at HI-1.

C. Containment temperature 205°F D. Containment integrated dose 1.5x106 Rad Proposed Answer: D Explanation:

Technical

Reference:

EOP-0.0A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. EO0.XG2.OB405 d 017 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8, 10 55.43 5 Comments:

(originally #104)

SRO (ONLY) TEST QUESTION #: 49

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.1.001.K1.05 Importance Rating 4.5 4.4 Proposed Question:

An approach to criticality is being performed by means of control rod withdrawal. The RO stops control rod motion when the reactor is close to criticality but still subcritical.

The SR count rate should:

A. continue to increase, but at a slower rate. The startup rate should stabilize at a lower positive value.

B. continue to increase for a short time and then plateau. The startup rate should gradually decease to zero.

C. stop increasing and stabilize at its present value. The startup rate should immediately decrease to zero.

D. begin to slowly decrease. The startup rate should gradually decrease to zero from a slightly negative value.

Proposed Answer: B Explanation:

Technical

Reference:

IPO-002A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. IPO.XO2.OB900- d 012 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2, 9 55.43 Comments:

RO/SRO TEST QUESTION #: 50

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.2.022.AK3.03 Importance Rating 3.1 3.3 Proposed Question:

What are the functions of excess letdown?

A. Provides additional letdown capability during heatup, and compensates for RCP seal injection when normal letdown is unavailable.

B. Provides additional letdown capability during cooldown, and removes heat from RCP seal return when RCP #1 seal failure occurs.

C. Provides additional letdown capability when RCP #1 seal bypass is in service, and removes heat from RCP #1 seal leakoff.

D. Provides additional letdown capability during crud burst, and provides relief flowpath when RCP #1 seal bypass is in service.

Proposed Answer: A Explanation:

Technical

Reference:

OP51.SYS.CS1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.CS1.OB12- d 001 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 2 Comments:

(originally #105)

SRO (ONLY) TEST QUESTION #: 51

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.4.003.K1.01 Importance Rating 2.6 2.8 Proposed Question:

Unit 1 is operating at 50% power when a RCP Lube Oil Low Level alarm actuates.

Maintenance personnel request to enter the Containment Loop Rooms to setup a camera for remote monitoring capability. Who must approve this entry into the Containment Loop Rooms?

A. Shift Manager.

B. Radiation Protection Manager.

C. Plant Manager.

D. Either B or C.

Proposed Answer: D Explanation:

Technical

Reference:

OPD1.ADM.XAB, STA-620 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. ADM.XAB.OB13- d 1

New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2, 9 55.43 Comments:

RO/SRO TEST QUESTION #: 52

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.2.032.AK3.02 Importance Rating 3.7 4.1 Proposed Question:

A Reactor Startup is in progress with Control Bank B at 50 steps and Reactor Power at 102 CPS. Which ONE of the following is required if one Source Range Nuclear Channel fails low and why?

A. Suspend the Reactor Startup to ensure protection against rod withdrawal accidents.

B. Place the SRNI channel in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to prevent inadvertent reactor trip.

C. Verify Shutdown Margin within one hour to ensure adequate negative reactivity can be inserted to shutdown the reactor if necessary.

D. Continue the startup since SRNI channels are not required to show protection above the P-6 interlock.

Proposed Answer: A Explanation:

Technical

Reference:

TS 3.3.1 and Bases Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank Modifie

1. d New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2, 5 Comments:

(originally #106)

SRO (ONLY) TEST QUESTION #: 53

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.5.022.K3.02 Importance Rating 3.0 3.3 Proposed Question:

Which plant condition will most likely cause a RV FLANGE LKOFF TEMP HI alarm?

A. Loss of Ventilation Chillers 1, 2, 3 and 4.

B. Loss of Ventilation Chillers 7, 8 and 9.

C. Loss of power to 1PC1.

D. Loss of power to 1C1.

Proposed Answer: A Explanation:

Technical

Reference:

ALM-0053A, Window 1.1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.RC1.OB04 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 54

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.4.061.K3.02 Importance Rating 4.2 4.4 Proposed Question:

During the performance of IPO-002A the operator is directed to replace Motor Driven AFW pump fuses. These fuses restore pump auto-start on:

A. LO-LO S/G level.

B. Blackout Signal.

C. Safety Injection Signal.

D. trip of both Main Feedwater Pumps..

Proposed Answer: D Explanation:

Technical

Reference:

IPO-002A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. IPO.XO2.OB900 - d 023 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 55

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.4.061.K4.01 Importance Rating 4.1 4.2 Proposed Question:

Given the following:

o CST Level is 200,000 gallons.

o The Unit is in mode 3.

o A loss of offsite power has occurred.

o Steam is being released through the S/G PORV's.

Is the CST level sufficient and why?

A. Yes, because it is sufficient to hold the unit in mode 3 for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, followed by a cooldown to RHR entry conditions at the design rate of 25oF/hr.

B. No, because it is insufficient to hold the unit in mode 3 for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, followed by a cooldown to RHR entry conditions at the design rate of 25oF/hr.

C. Yes, because it is sufficient to hold the unit in mode 3 for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, followed by a cooldown to RHR entry conditions at the design rate of 50oF/hr.

D. No, because it is insufficient to hold the unit in mode 3 for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, followed by a cooldown to RHR entry conditions at the design rate of 50oF/hr.

Proposed Answer: C Explanation:

Technical

Reference:

TS 3.7.6 bases Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 2 Comments:

SRO (ONLY) TEST QUESTION #: 56

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.2.013.K4.12 Importance Rating 3.7 3.9 Proposed Question:

WHICH ONE (1) of the following describes the design interlock or operating practice that is used to prevent ALL automatic Safety Injection (SI) actuations following a reset of the SI signal?

A. The sixty (60) second delay timer in the SI reset circuitry.

B. Manually blocking steam line pressure and PZR pressure SI from the control board.

C. The seal-in feature of the reset circuitry disarms all subsequent SI actuations.

D. The P-4 interlock, actuated by the opening of the reactor trip breakers.

Proposed Answer: D Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank INPO 4225 Modifie

1. d New Question History: Last NRC Exam Harris 1 (WEC), 2/24/1997 Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 57

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.1.001.K4.23 Importance Rating 3.4 3.8 Proposed Question:

During a 10% step load increase, the operator observes:

• 855 MWe (stable)

• Tave - Tref error = 8°F (Tave 8°F low)

• 68% RTP (increasing)

• OTNI6/C-3 (PCIP) dark

• all controls in automatic Which of the below describes a possible response of the rod control system during this transient?

A. Rods not moving out due to the OPNI6 rod stop (C-4).

B. Rods moving out due to Rx power increasing with turbine load constant.

C. Rods not moving out to restore Tave (when Tave is 3°F low) due to Reactor power increasing.

D. Rods moving out to restore Tave (when Tave is 3°F low) due to Reactor power increasing.

Proposed Answer: C Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified X MCO.TA2.OB103 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Modification: replaced one distracter.

RO/SRO TEST QUESTION #: 58

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 3.2.013.K6.01 Importance Rating 2.7 3.1 Proposed Question:

An Engineered Safety Features (ESF) Containment Hi-3 Pressure signal occurs when:

A. 2/4 Hi containment pressure detectors sense pressure > 3.2 psig.

B. 2/4 Hi containment pressure detectors sense pressure > 18.2 psig.

C. 2/3 Hi containment pressure detectors sense pressure > 18.2 psig.

D. 2/3 Hi containment pressure detectors sense pressure > 3.2 psig.

Proposed Answer: B Explanation:

Technical

Reference:

ALM-0022A (ALB 2B, 3.10)

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.CT1.OB04-3 d X New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

Modified: altered one distracter RO/SRO TEST QUESTION #: 59

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.7.012.A1.01 Importance Rating 2.9 3.4 Proposed Question:

During the performance of OPT-309, "Unit Calorimetric", the feedwater temperature points utilized were reading 10°F LOWER than actual feedwater temperature. Power range nuclear instruments adjustments were performed per the OPT.

What is the status of the current power range indications?

A. Indicated power is LESS THAN actual power; therefore, power range instruments are set CONSERVATIVELY.

B. Indicated power is LESS THAN actual power; therefore, power range instruments are set NON-CONSERVATIVELY.

C. Indicated power is GREATER THAN actual power; therefore, power range instruments are set NON-CONSERVATIVELY.

D. Indicated power is GREATER THAN actual power; therefore, power range instruments are set CONSERVATIVELY.

Proposed Answer: D Explanation:

Technical

Reference:

LO21.SF4.XOC, OPT-309 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SF4.XOC.OB103- d 1

New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 Comments:

RO/SRO TEST QUESTION #: 60

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.8.029.A2.01 Importance Rating 2.9 3.6 Proposed Question:

Given the following conditions:

-Unit 1 is in mode 6 for a refueling outage.

-Off-load of fuel is 55 % complete and ongoing.

-Containment purge and exhaust is in service.

-The instrument department has just reported that the current HI and HI-HI setpoints for CONTAINMENT EXHAUST RADIATION MONITOR were incorrectly set two decades HIGH.

Based on this information, the required action is to:

A. suspend core off-load until the containment purge and exhaust valves are closed.

B. suspend core off-load until the correct setpoints are entered.

C. continue core off-load and direct HP to perform continuous air monitoring of the containment.

D. continue core off-load and verify purge exhaust directed through the charcoal filter bank.

Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 1342 Modified New Question History: Last NRC Exam North Anna 1 (WEC), 1/26/1996 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments:

RO/SRO TEST QUESTION #: 61

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.6.062.A2.09 Importance Rating 2.7 3.0 Proposed Question:

Current flow to ground is limited in a neutral grounding transformer by:

A. the reflected impedance of the secondary into the primary.

B. a series current limiting resistor.

C. a protective overcurrent relay.

D. a circuit breaker Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.AC2.OB900 d

- 002 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments:

RO/SRO TEST QUESTION #: 62

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 2 2 K/A # 4.5.E.11.EK3.02 Importance Rating 3.5 4.0 Proposed Question:

In ECA-1.1A, "Loss of Emergency Coolant Recirculation", after the RWST is empty (12%) and any ECCS pumps taking suction from the RWST are stopped, the SGs are depressurized. Step 31 states: "Depressurize all intact SGs to inject accumulators as necessary". Choose the answer below that describes the intent of Step 31.

A. The SGs are depressurized quickly in order to have the accumulator contents increase the recirc sump inventory.

B. The core is kept covered by depressurizing all intact SGs slowly, extending the time to depletion of the accumulators.

C. The SGs are depressurized, one at a time, to inject the accumulators one at a time.

D. The accumulators are injected so that nitrogen to them can be isolated.

Proposed Answer: B Explanation:

Technical

Reference:

ECA-1.1A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SM1.XGG.OB104 d 005 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 2, 5 Comments:

(originally #107)

SRO (ONLY) TEST QUESTION #: 63

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.2.011.A2.04 Importance Rating 3.5 3.7 Proposed Question:

Unit 1 is in the following configuration: RCS pressure is 300 psig, Tavg is 300°F, and Train "A" RHR is in the shutdown cooling mode. At this point, pressurizer level starts decreasing rapidly with flow controller FK-121 fully open.

Select the correct action to be taken if pressurizer level continues to decrease.

A. Unisolate the Safety Injection Accumulators.

B. Reduce letdown flow - transfer to the 45 gpm orifice.

C. Dispatch an operator to rack in the breakers to the non-operating CCP and one SIP.

D. Reset containment isolation Phase A and B.

Proposed Answer: C Explanation:

Technical

Reference:

ABN-108 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.RC1.OB30 - d 032 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments:

RO/SRO TEST QUESTION #: 64

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 1 K/A # 3.5.026.A3.01 Importance Rating 4.3 4.5 Proposed Question:

A large break LOCA has occurred on Unit 1. Given the following conditions:

- Containment pressure is 22 psig

- Containment Spray failed to automatically initiate

- Manual pushbutton actuation for Containment Spray was also unsuccessful Which ONE of the following describes the required operator actions following manual start of Containment Spray Pumps?

A. Verify CS Heat Exchanger Outlet valves are OPEN; manually OPEN Chemical Additive Tank Discharge valves.

B. Manually OPEN CS Heat Exchanger Outlet valves; manually OPEN Chemical Additive Tank Discharge valves.

C. Manually OPEN CS Heat Exchanger Outlet valves; verify Chemical Additive Tank Discharge valves are OPEN.

D. Verify CS Heat Exchanger Outlet valves are OPEN; verify Chemical Additive Tank Discharge valves are OPEN.

Proposed Answer: B Explanation:

Technical

Reference:

SOP-204A, FRZ-0.1A Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 65

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.4.055.A3.03 Importance Rating 2.5 2.7 Proposed Question:

Unit 1 is at 100% power with CEV 1-02 running, CEV 1-01 in standby, and CEV 1-03 off. While conducting a CEV lineup verification, you discover 1CV-0235 CNDSR VAC PMP 1-01 SUCT PRESS SW 2970A/2971A/2972A HP RT VLV closed, and the instrument air line between 1PS-2971A and 1CV-235 is disconnected. If Main Condenser vacuum decreases to 23" with this alignment, how will CEV operation be affected?

A. CEV 1-02 will eventually trip.

B. CEV 1-01 will start on low vacuum, and 1-HV-2956 will open.

C. CEV 1-01 will NOT start on low vacuum, and 1-HV-2956 will NOT open.

D. CEV 1-01 will start on low vacuum, but 1-HV-2956 will NOT open.

Proposed Answer: D Explanation:

Technical

Reference:

M1-2211, SH 02 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.CV1.OB106- d 003 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 66

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.8.029.A4.04 Importance Rating 3.5 3.6 Proposed Question:

While lifting a fuel assembly from the Reactor vessel lower core plate, audible Source Range indication inside Containment is lost and cannot be corrected. Which of the following actions are correct for this situation?

A. Movement of the fuel assembly must cease immediately. Containment evacuation is required.

B. Core alterations may continue as long as the criticality alarm is NOT alarming.

Containment evacuation is NOT required.

C. Movement of the fuel assembly shall continue to place it in a safe location.

Containment evacuation is required.

D. Core alteration may continue as long as Containment Integrity is met.

Containment evacuation is NOT required.

Proposed Answer: C Explanation:

Technical

Reference:

TS 3.9; RFO-102, RFO-302 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. RFO.SYE.OB404 d 002 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 67

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.7.012.G.2.2.22 Importance Rating 3.4 4.1 Proposed Question:

While in mode 4 with one Control Bank rod indicating at 9 steps, what is the basis for requiring both Source Range Nuclear Instrument Reactor Trip System channels operable?

A. SRNI RTS channels are not required to be operable below mode 2.

B. They provide core protection against a rod withdrawal accident.

C. They provide core protection against a rod ejection accident.

D. They provide protection to ensure the integrity of the fuel under all possible overpower conditions.

Proposed Answer: B Explanation:

Technical

Reference:

TS SECTION 3.3.1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank Modifie

1. d New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 Comments:

SRO (ONLY) TEST QUESTION #: 68

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.7.016.K1.10 Importance Rating 3.1 3.1 Proposed Question:

Which of the following conditions would require entering a CPSES Technical Specification Limiting Condition for Operation action with the plant in hot standby?

A. Opening the outer door to the Personnel Air Lock to enter Containment B. Containment pressure at 1.2 psig C. Containment air temperature 123°F D. One train of Electric Hydrogen Recombiners inoperable Proposed Answer: C Explanation:

Technical

Reference:

TS 3.6.5 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.CY1.OB900- d 25 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2, 9 55.43 Comments:

RO/SRO TEST QUESTION #: 69

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.2.006.K2.02 Importance Rating 2.5 2.9 Proposed Question:

Upon loss of all a/c power while operating in mode 1 at 100% power, how will the SIS Accumulator Isolation Valves respond?

A. SIS Accumulator Isolation Valves are air operated and are not affected by loss of a/c.

B. They will fail open.

C. They will fail shut.

D. They will remain in the same position they were in before the loss of a/c.

Proposed Answer: D Explanation:

The SIS Accumulator Isolation Valves are motor operated and will not change positions on loss of their 480v power supply.

Technical

Reference:

Drawings M1-0262, M1-2262, E1-0005, E1-0009 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank Modifie

1. d New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 3, 7 55.43 Comments:

RO/SRO TEST QUESTION #: 70

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.4.035.K3.01 Importance Rating 4.4 4.6 Proposed Question:

Due to a malfunction with the S/G Blowdown Mixed Bed Demineralizer Outlet Radiation Valve, S/G Blowdown flow has isolated. What effect does this have on Reactor power if the unit is operating at 80% RTP?

A. Reactor power increases approximately 5%.

B. Reactor power decreases approximately 2%.

C. Reactor power remains the same.

D. Reactor power decreases initially, and slowly rises back to original value.

Proposed Answer: B Explanation:

Technical

Reference:

DBD-ME-0239 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.SB1.OB06-1 d New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 71

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.7.016.K3.08 Importance Rating 3.5 3.7 Proposed Question:

Unit 1 is operating at 100% power with all control systems in their normal alignment when the Pressurizer Pressure Instrument selected for control to the Pressurizer Master Pressure Controller fails high. Which of the below actions will occur?

(assume no operator actions)

A. PCV-455A will open and not re-close.

B. PCV-456 will open and not re-close.

C. PCV-456 will open and re-close at 2185 psig.

D. PCV-455A will open and re-close at 2185 psig.

Proposed Answer: D Explanation:

Technical

Reference:

LO21.MCO.TA3.LP Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. MCO.TA3.OB102 d

- 24 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 72

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 1 1 Group # 3 3 K/A # 4.2.028.AA2.14 Importance Rating 2.6 2.8 Proposed Question:

WHICH ONE (1) of the following conditions would result in an increase in indicated pressurizer level?

A. The reference leg cools down due to a decrease in containment temperature.

B. Pressurizer liquid temperature increases.

C. A leak in the reference leg of the controlling pressurizer level transmitter.

D. Containment pressure increases to 0.3 psig; containment temperature remains constant.

Proposed Answer: C Explanation:

Technical

Reference:

LO21.GFE.FF1.LN Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.PP1.OB08- d 28 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

(originally #108)

SRO (ONLY) TEST QUESTION #: 73

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 1 1 K/A # 2.1.19 Importance Rating 3.0 3.0 Proposed Question:

Given the following Unit 1 plant conditions:

o A reactor trip and safety injection have occurred.

o RCS pressure is stable at 420 psig.

o Over the last hour the cold leg temperatures have decreased to 240oF as follows:

60 minutes ago - 350oF 45 minutes ago - 315oF 30 minutes ago - 285oF 15 minutes ago - 260oF Now - 240oF Which ONE of the following would be the appropriate procedure in response to the current state of the Integrity CSF?

A. FRP-0.2A B. FRP-0.1A C. FRP-0.3A D. CSF is satisfied Proposed Answer: B Explanation:

Technical

Reference:

Integrity CSF diagram Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 5 Comments:

(originally #109)

SRO (ONLY) TEST QUESTION #: 74

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.7.073.K4.01 Importance Rating 4.0 4.3 Proposed Question:

If the S/G Blowdown Mixed Bed Demineralizer Outlet Radiation Monitor was to lose power, what effect would this have on the S/G Blowdown System?

A. The Control Room would not receive warning of S/G Blowdown Demineralizer resin exhaustion.

B. The radiation valve would close and all S/G Blowdown flow stops.

C. The radiation valve will be unable to perform its intended function.

D. The Control Room would receive a S/G Blowdown Panel trouble alarm and the system will continue to operate.

Proposed Answer: B Explanation:

Technical

Reference:

E1-0040, Sh 97, ALM-3200 att 3 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.SB1.OB09-2 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 4 Comments:

RO/SRO TEST QUESTION #: 75

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.8.086.K4.01 Importance Rating 3.1 3.7 Proposed Question:

A fire has been reported in the Aux. Building. The Fire Brigade has responded and is using the Fire Protection Hose Stations to fight the fire. Which ONE of the following describes the response of the fire pumps to decreasing fire header pressure?

A. The diesel driven pumps start at 142 psig and the electric fire pump starts if pressure is not raised above 120 psig in 10 seconds.

B. One diesel driven fire pump starts at 148 psig and the electric fire pump starts at 120 psig.

C. The electric fire pump starts at 142 psig and one diesel driven fire pump starts in 10 seconds if pressure is not above 140 psig.

D. The electric fire pump starts at 142 psig; one diesel driven fire pump starts at 120 psig; the other diesel driven fire pump starts in 10 seconds if pressure is not raised above 120 psig.

Proposed Answer: C Explanation:

Technical

Reference:

SOP-904 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.FP1.OB106-001 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 76

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 1 1 K/A # 2.1.22 Importance Rating 2.8 3.3 Proposed Question:

Consider the following conditions:

- The plant is currently shutdown

- Reactor power = 0%

- Tc = 360F and steady

- Keff = .90

-All reactor head closure bolts are fully tensioned The procedure governing the current mode is:

A. IPO-003B B. IPO-001B C. IPO-007B D. IPO-010B Proposed Answer: C Explanation:

Technical

Reference:

TS table 1.1-1, IPO-007B Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 5 Comments:

(originally #110)

SRO (ONLY) TEST QUESTION #: 77

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.8.086.K4.03 Importance Rating 3.1 3.7 Proposed Question:

The Unit 2 Safeguards PEO has reported that the 2-02 Diesel Generator Starting Air Compressor is extremely warm. If a fire were to occur on this component a local......

A. ionization smoke detector would detect the fire and initiate the deluge system.

B. thermal detector would detect the fire and provide alarms.

C. thermal detector would detect the fire and initiate the deluge system.

D. ionization smoke detector would detect the fire and provide alarms.

Proposed Answer: D Explanation:

Technical

Reference:

ABN-901 att1 & 5 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.FP1.OB303 - d 001 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 78

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 2 2 K/A # 3.3.010.K5.02 Importance Rating 2.6 3.0 Proposed Question:

The pressurizer is being maintained at 2000 psia and 636 °F when one of the Power-Operated Relief Valves (PORVs) starts to leak to the Pressurizer Relief Tank (PRT).

The PRT pressure is maintained at 5 psig. The TEMPERATURE of the fluid immediately downstream of the PORV is approximately:

A. 220°F B. 240°F C. 230°F D. 250°F Proposed Answer: C Explanation:

The process is isenthalpic and the fluid downstream of the PORV is at the same pressure as the PRT. Assume Containment pressure is 15 psia. Convert PRT pressure from psig to psia:

-PRT pressure = 5 psig + 15 psi = 20 psia.

-From Steam Table 2 (or the Mollier Diagram),

-Tsat (20 psia) = 228 °F (approx. 230 °F).

Technical

Reference:

OP51.SYS.PP1.LN Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.PP1.OB09-7 d New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 Comments:

RO/SRO TEST QUESTION #: 79

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 3 3 K/A # 3.8.008.A2.04 Importance Rating 3.3 3.5 Proposed Question:

Unit 4 is operating at 100% power in normal alignment when the following events occur:

-A rupture develops in a RCP thermal barrier.

-ONE of the CCW PRMS monitors has just gone into alarm.

-CCW head tank level indicates 81%.

-CCW surge tank level reads 100%.

-CCW flow from RCP thermal barriers has increased to 110 gpm.

Which one of the following describes current condition of the CCW head tank vent valve, and RCP thermal barrier outlet?

A. CCW head tank vent is open. RCP thermal barrier outlet is closed.

B. CCW head tank vent is open. RCP thermal barrier outlet is open.

C. CCW head tank vent is closed. RCP thermal barrier outlet is closed.

D. CCW head tank vent is closed. RCP thermal barrier outlet is open.

Proposed Answer: D Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 5100 Modified New Question History: Last NRC Exam Turkey Point 4 (WEC), 8/7/1998 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 5 Comments:

RO/SRO TEST QUESTION #: 80

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 3 3 K/A # 3.4.045.K1.06 Importance Rating 2.6 2.6 Proposed Question:

When testing Main Steam Isolation Valve #1 (MSIV-1) from the control room, which of the following conditions will actuate the "MSIV #1 TEST FAILED" alarm?

A. MSIV-1 fails to reach 90% open in 10 seconds or less.

B. MSIV-1 fails to reach 90% open in 20 seconds or less.

C. MSIV-1 closes 10% and fails to return to full open.

D. MSIV-1 closes more than 10% during the test.

Proposed Answer: B Explanation:

Technical

Reference:

OP51.SYS.MR1.OB20 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.MR1.OB20-1 d New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 2,9 55.43 Comments:

RO/SRO TEST QUESTION #: 81

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 1 1 K/A # 2.1.6 Importance Rating 2.1 4.3 Proposed Question:

The Unit 1 crew is in EOP-3.0A, Steam Generator Tube Rupture, due to a tube rupture on Steam Generator #3 when the STA reports that CET temperatures indicate 1250 °F. The crew transitions from EOP-3.0A to respond to the high CET temperatures when the BOP reports that all AFW flow has been lost and only the ruptured Steam Generator #3 has a level above 5% Narrow Range. Which of the following gives the correct operator action?

A. Complete FRC-0.1A and then transition to FRH-0.1A (response to Loss of Secondary Heat Sink)

B. Complete FRC-0.1A and then return to EOP-3.0A C. Transition immediately to FRH-0.1A and upon completion return to FRC-0.1A D. Transition immediately to FRH-0.1A and upon completion return to EOP-3.0A Proposed Answer: B Explanation:

Technical

Reference:

FRC-0.1, ODA-407 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. FRC.XH2.OB404- d 2

New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

(originally #111)

SRO (ONLY) TEST QUESTION #: 82

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 3 3 K/A # 3.4.076.K2.01 Importance Rating 2.7 2.7 Proposed Question:

Which of the following components is powered from the safeguards 6.9 KV buses?

A. CW pumps B. RCPs C. HDPs D. SSW pumps Proposed Answer: D Explanation:

Technical

Reference:

E1-0003, E1-0004 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.AC2.OB03 -

004 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 83

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 3 3 K/A # 3.4.045.K4.47 Importance Rating 4.0 4.3 Proposed Question:

The Technical Specification basis for the P-4 interlock is:

A. The P-4 interlock anticipates a loss of heat sink.

B. The P-4 interlock protects against severe challenges to the electrical distribution system resulting from fluctuating steam pressures.

C. The P-4 interlock is not required by Technical Specifications.

D. The P-4 interlock protects the reactor from excessive cooldown.

Proposed Answer: C Explanation:

Technical

Reference:

TS 3.3.1 bases Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 Comments:

SRO (ONLY) TEST QUESTION #: 84

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 4 4 K/A # 2.4.43 Importance Rating 2.8 3.5 Proposed Question:

An ALERT was upgraded to a SITE AREA EMERGENCY at 2 pm. What is the LATEST time allowed to report this change to the NRC?

A. 3:30 pm B. 2:15 pm C. 2:30 pm D. 3:00 pm Proposed Answer: D Explanation:

Technical

Reference:

10 CFR 50.72 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 1, 5 Comments:

(originally #112)

SRO (ONLY) TEST QUESTION #: 85

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 3 2 K/A # 3.5.028.K5.02 Importance Rating 3.4 3.9 Proposed Question:

The following conditions exist:

-The plant was operating at 100% power, when a Large Break LOCA to Containment occurred

- Containment Hydrogen is 1%

-Water level in the Reactor Core is 50% (half the fuel is exposed)

Which ONE of the following will make hydrogen conditions in containment worse?

A. Water level in the reactor core increasing from 50% to 90% level B. Instrument air leak to containment C. Excessive leakage from containment thru the Containment Vacuum Breakers D. Exit Thermocouples at 1800 degrees F and rising Proposed Answer: D Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 10850 Modified New Question History: Last NRC Exam Kewaunee 1 (WEC), 12/18/1997 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 Comments:

RO/SRO TEST QUESTION #: 86

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 3 2 K/A # 3.5.028.K6.01 Importance Rating 2.6 3.1 Proposed Question:

The temperature of the air mixture in the containment hydrogen recombiners is controlled by:

A. cycling the recombiner electric heaters on and off to maintain temperature in the proper band.

B. regulating the air flow at the discharge of the recombiner used to preheat the inlet flow.

C. varying the power to the recombiner electric heaters.

D. regulating the air flow at the inlet of the recombiner.

Proposed Answer: C Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 5355 Modified New Question History: Last NRC Exam Salem 1 (WEC), 1/22/1996 Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 87

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 1 1 K/A # 2.1.16 Importance Rating 2.9 2.8 Proposed Question:

Select the statement that describes why portable radios should not be used in "Radio Free Zones.

A. Radio transmission interferes with security radios in the event of a security plan implementation.

B. Radio frequencies may inadvertently interfere with CENTREX equipment.

C. Radios are useless in these areas due to signal reception difficulties.

D. Radios produce electromagnetic interference (EMI) that may cause inadvertent equipment operation.

Proposed Answer: D Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 5417 Modified New Question History: Last NRC Exam Salem 1 (WEC), 1/22/1996 Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

RO/SRO TEST QUESTION #: 88

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 1 1 K/A # 2.1.18 Importance Rating 2.9 3.0 Proposed Question:

The NRC must be notified in writing within 30 days if a licensed operator is convicted of a felony. Which of the following is responsible for notifying the NRC of the conviction?

A. The licensed individual.

B. The Manager, Operations.

C. The Plant Manager.

D. Vice President, Nuclear Operations.

Proposed Answer: A Explanation:

Technical

Reference:

STA-501 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified ADM.XA7.OB01-2 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

RO/SRO TEST QUESTION #: 89

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 1 1 K/A # 2.1.24 Importance Rating 2.8 3.1 Proposed Question:

Given drawing E1-0057 Sheet 16, determine which of the following signals will generate an open signal to Fan 9 Isolation Damper 1-HV-5953.

A. Energizing the 42 relay.

B. Energizing the 1-HX-5952 relay.

C. Energizing the 1-42AX/5952 relay.

D. Energizing the 74 relay.

Proposed Answer: B Explanation:

Technical

Reference:

E1-0057 sheet 16 Proposed references to be provided to applicants during examination:

E1-0057 sheet 16 Learning Objective:

Question Source: Bank # CPSES Modified SYS.HV2.OB07-1 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

RO/SRO TEST QUESTION #: 90

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 2 2 K/A # 2.2.3 Importance Rating 3.1 3.3 Proposed Question:

Identify the unit difference of the Process Sampling System.

A. Unit 1 sample coolers are supplied by Train A CCW while Unit 2 sample coolers are supplied by Train B CCW.

B. Unit 2 sampling valves all fail open.

C. Unit 1 sample hood purge flow is directed to FDT #3.

D. Spent Fuel Pool demineralizers sample is taken on Unit 1 side.

Proposed Answer: D Explanation:

Technical

Reference:

OP51.SYS.PA2.OB21 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.PA2.OB21-1 d New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 7 Comments:

RO/SRO TEST QUESTION #: 91

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 2 2 K/A # 2.2.22 Importance Rating 3.4 4.1 Proposed Question:

With Unit 2 operating in MODE 2, which one of the following renders an Auxiliary Feedwater Pump INOPERABLE?

A. Leaving AFWT speed control (2-SK-2452A) at 0% output.

B. AFW suction lined up to Station Service Water.

C. Safeguards Bus 2EA2 powered from alternate transformer XST2 (2EA2-2 closed).

D. A flow control valve from the motor driven pumps fully shut while transferring from AFW to the Main Feed Bypass Control valves.

Proposed Answer: A Explanation:

Technical

Reference:

TS 3.7.5 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.AF1.OB29 -

005 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 Comments:

SRO (ONLY) TEST QUESTION #: 92

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 2 2 K/A # 2.2.23 Importance Rating 2.6 3.8 Proposed Question:

The plant is operating at 100% power. The TDAFW Pump is being started up for testing. While the pump is operating, a significant break develops in one of the steam supply lines to the pump. The control room responds to MCB alarms and fire panel alarms and isolates the leak by closing both HV-2452-1 and HV-2452-2 (TDAFWP Steam Supplies). The steam supply is further isolated by closing the manual Isolation Valves for steam supplies. Under these conditions, the plant:

A. can continue to operate as long as the remaining AFW pumps are verified to be OPERABLE within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and at least once per 31 days.

B. can continue to operate, but the steam supplies must be restored to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

C. can continue to operate for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by which time the break must be repaired and the pump returned to operable status, or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN in the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

D. must be shut down to HOT STANDBY within the next six hours and to HOT SHUTDOWN within the following six hours.

Proposed Answer: C Explanation:

Technical

Reference:

TS 3.7.5 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.AF1.OB29 -

010 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 Comments:

SRO (ONLY) TEST QUESTION #: 93

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 2 2 K/A # 2.2.11 Importance Rating 2.5 3.4 Proposed Question:

With regard to Temporary Modifications (TMs), select the correct statement from the following:

A. The Operations Manager shall approve all TMs.

B. For TMs on systems that are in the custody of Operations, the Shift Manager shall approve the TM after installation.

C. If SORC did not review an expedited TM prior to installation, then a post-installation review of the TM shall be required.

D. When a TM requires a 10CFR 50.59 evaluation, the SORC shall approve the TM within 30 days of installation.

Proposed Answer: C Explanation:

Technical

Reference:

STA-602, Sect 6.15.6 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified ADM.XA1.OB605-004 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 3 Comments:

SRO (ONLY) TEST QUESTION #: 94

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 3 3 K/A # 2.3.2 Importance Rating 2.5 2.9 Proposed Question:

Given the following:

-A point source in the auxiliary building is generating the following radiation field:

-500 mRem/hr at two (2) feet.

-125 mRem/hr at four (4) feet.

- 32 mRem/hr at eight (8) feet.

TWO (2) options exist to complete a mandatory assignment near this radiation source:

-OPTION 1: Operator X can perform the assignment in thirty minutes working at a distance of FOUR (4) feet from the point source.

-OPTION 2: Operators Y and Z, using a special extension tool can perform the same task in 75 minutes at a distance of EIGHT (8) feet from the point source.

WHICH ONE (1) of the following choices is the preferred option to complete the assignment, per the facility ALARA plan?

A. Option 1 as it results in the lowest total dose.

B. Option 1 as it results in the lowest individual dose.

C. Option 2 as it results in the lowest total dose.

D. Option 2 as it results in the lowest individual dose.

Proposed Answer: A Explanation:

Technical

Reference:

EPP-305, STA-651 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # INPO 4399 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 12 55.43 4 Comments:

SRO (ONLY) TEST QUESTION #: 95

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 3 3 K/A # 2.3.4 Importance Rating 2.5 3.1 Proposed Question:

After fuel handling tools and equipment have contacted the refueling water they must:

A. remain wetted or be relubricated prior to their next usage.

B. be flushed with demineralized water to remove boric acid before their next usage.

C. be considered as radioactively contaminated and either not be touched or protective clothing used before touching.

D. be flushed with demineralized water to remove radioactive contamination before touching.

Proposed Answer: C Explanation:

Technical

Reference:

RFO-302 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified RFO.FH5.OB100

- 008 New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 12 55.43 4 Comments:

SRO (ONLY) TEST QUESTION #: 96

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 4 4 K/A # 2.4.39 Importance Rating 3.3 3.1 Proposed Question:

You are a licensed Reactor Operator on dayshift, working on outage tagouts in the Work Control Center. You do not have assigned responsibilities in the Emergency Response Organization (ERO). A transient occurs that results in the declaration of an ALERT Emergency and activation of the Evacuation Alarm. To which of the following locations do you report?

A. The Technical Support Center (TSC).

B. The Emergency Operations Facility (EOF).

C. The Control Room.

D. The Operations Support Center (OSC).

Proposed Answer: C Explanation:

Technical

Reference:

CPSES/EP Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 5 Comments:

RO/SRO TEST QUESTION #: 97

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 4 4 K/A # 2.4.46 Importance Rating 3.5 3.6 Proposed Question:

During refueling operations, radiation levels increase to alarm setpoint in the Spent Fuel Pool area. Which one of the choices below is a correct response to the present conditions?

A. Close the AB 810 roll-up door B. Bypass and isolate the SFP demineralizers.

C. Ensure fuel transfer car is in Containment..

D. Begin makeup to the pool.

Proposed Answer: A Explanation:

Technical

Reference:

ABN-908 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified RFO.SYE.OB201

- 003 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5, 7 Comments:

SRO (ONLY) TEST QUESTION #: 98

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 4 4 K/A # 2.4.47 Importance Rating 3.4 3.7 Proposed Question:

Given the following conditions:

- The crew is performing a reactor startup.

- The RO has just pulled the control rods several steps and is waiting for source range counts to stabilize.

Assuming the reactor is very close, but not yet critical, source range counts should:

A. stop increasing and stabilize immediately, with SUR dropping to zero.

B. begin to slowly decrease, with SUR gradually decreasing to zero.

C. continue to increase, but at a slower rate, with SUR stabilizing at a lower positive value.

D. continue to increase for a short period of time, then plateau, with SUR decreasing to zero.

Proposed Answer: D Explanation:

Technical

Reference:

IPO-002, SECTION 5.2 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank CPSES Modifie

1. SYS.EC1.OB13-3 d New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 5 Comments:

RO/SRO TEST QUESTION #: 99

ES-401 Written Examination Question Worksheet Form ES-401-6 (R8, S1)

Examination Outline Cross-reference: Level RO SRO Tier # 3 3 Group # 4 4 K/A # 2.4.25 Importance Rating 2.9 3.4 Proposed Question:

Mechanical Maintenance has a work package to repack the isolation valve for the Fire Hose Station on the west wall of the Main Control Room located just outside the kitchen area. What compensatory actions, if any, must be taken?

A. Station a continuous Fire Watch in the Control Room.

B. Place a gated wye with sufficient length of fire hose on the hose station on the east wall of the Control Room within one hour.

C. Place a gated wye with sufficient length of fire hose on the hose station at the foot of the steps between Unit #1 Cable Spread Room and the Control Room within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

D. Station a Fire Watch to make hourly patrols in the Control Room .

Proposed Answer: B Explanation:

Technical

Reference:

STA-738 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # CPSES Modified SYS.FP1.OB501 -

006 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 5 Comments:

SRO (ONLY) TEST QUESTION #: 100