ML100670650

AN2-2009-08-Draft Operating Test

ML100670650
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/07/2009
From:	Brian Larson Operations Branch IV
To:	Entergy Operations
References
Download: ML100670650 (256)

Text

A2JPM-RO-RWTMU Page 1 of 6ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2REV#: 000DATE:SYSTEM/DUTY AREA: Conduct of OperationsTASK: Determine volume of boric acid and DI water to makeup to RWTJTA#: ANO-2-RO-CHADD-NORM-110KA VALUE RO:4.3SRO:KA

REFERENCE:

2.1.23APPROVED FOR ADMINISTRATION TO:

RO: XSRO:TASK LOCATION:INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformCLASSROOM: PerformPOSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD:SIMULATE:PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:30 MinutesREFERENCE(S): OP 2104.003 Attachment EEXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

A2JPM-RO-RWTMU Page 2 of 6ADMINISTRATIVE JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion ofOP 1064.023 Attachment 6 with the examinee.JPM INITIAL TASK CONDITIONS

Initial RWT Level 92% Initial RWT concentration 2700 ppm Final RWT level 95% Final RWT Concentration 2725 ppm 'A' BAMT concentration 5965 ppmTASK STANDARD: Determine that the amount of Boric Acid needed is 8516 gallons +/- 85gallons and the amount of DI water needed is 5848 gallons +/- 58 gallonsTASK PERFORMANCE AIDS: OP 2104.003 Attachment E.

A2JPM-RO-RWTMU Page 3 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREINITIATING CUE:The CRS directs: "Given the information form initial conditions, determine the boric acid and DI water feedvolumes required using OP 2104.003 Attachment E Step 3.0.START TIME:

PERFORMANCECHECKLISTSTANDARD(Circle One) 1Enter initial RWT level.Entered 92% as initial RWTlevel.N/A SAT UNSAT 2Calculate initial RWTvolume as 466262 gallonsCalculated initial RWT volumeand entered 466262 gals.N/A SAT UNSAT 3Enter final RWT level.Entered 95% as final RWTlevel.N/A SAT UNSAT 4Calculate final RWTvolume as 480626 gallonsCalculated final RWT volumeand entered 480626 gals.N/A SAT UNSAT(C) 5Determine total feedvolume needed. Entered14364 gallons +/- 100 gallons.Calculated feed volumerequired to be added andentered 14364 gallons.N/A SAT UNSAT(C) 6Calculate concentration offeed volume. Entered3536.5 ppm boron +/-25ppm boron.Calculated concentration offeed volume and entered3536.5 ppm boron.N/A SAT UNSAT A2JPM-RO-RWTMU Page 4 of 6ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCECHECKLISTSTANDARD(Circle One)(C) 7Calculate boric acid feedvolume. Entered 8516 gal +/-100 gal.Calculate boric acid feedvolume. Entered 8516 gal.N/A SAT UNSAT(C) 8Calculate DI water feedvolume. Entered total feedvolume - boric acid feedvolume. Entered 5848 gals+/- 100 gal.Calculated DI water feedvolume and entered 5846gals.N/A SAT UNSAT ENDSTOP TIME:

A2JPM-RO-RWTMU Page 5 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS

Initial RWT Level 92% Initial RWT concentration 2700 ppm Final RWT level 95% Final RWT Concentration 2725 ppm 'A' BAMT concentration 5965 ppmINITIATING CUE:Determine the boric acid and DI water feed volumes required to raise the RWT from 92% to95% and change boron concentration to 2725 ppm using OP 2104.003 Attachment E Step 3.0.

A2JPM-RO-RWTMU Page 6 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS

Initial RWT Level 92% Initial RWT concentration 2700 ppm Final RWT level 95% Final RWT Concentration 2725 ppm 'A' BAMT concentration 5965 ppmINITIATING CUE:Determine the boric acid and DI water feed volumes required to raise the RWT from 92% to95% and change boron concentration to 2725 ppm using OP 2104.003 Attachment E Step 3.0.

ANO-2-JPM-NRC-ADMIN-PDIL Page 1 of 5ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2REV#: 001DATE:SYSTEM/DUTY AREA: Conduct of OperationsTASK: Determine limits for CEA positions using the COLR PDIL.JTA#: ANO-2-RO-OPROC-NORM-62KA VALUE RO:3.9SRO:4.2KA

REFERENCE:

2.1.25APPROVED FOR ADMINISTRATION TO:

RO: XSRO:TASK LOCATION:INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformCLASSROOM: PerformPOSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD:SIMULATE:PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:15 MinutesREFERENCE(S): OP-2102.004, Unit 2 Tech Specs, and Unit 2 COLREXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-ADMIN-PDIL Page 2 of 5ADMINISTRATIVE JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion ofOP 1064.023 Attachment 6 with the examinee.JPM INITIAL TASK CONDITIONS

The plant has been at 100% since January 1 st of this year with CEAs at the programinsertion limit. The following conditions were established on 8-1-09 at 12:00 which was 250 EFPD:Plant power was lowered to 85% power due to 'A' Main Feedwater pumpoutage for bearing replacement.Group P CEAs are full out.Group 6 CEAs are being used for ASI control and are 90" withdrawn.COLSS ASI is -.07.#1 CEAC is inoperable for Surveillance testing.#2 CEAC is operable.TASK STANDARD

Determine that CEA are inserted into the long term steady stateinsertion limits and that the 5 EFPD limit has not been exceeded.TASK PERFORMANCE AIDS: OP-2102.004, Unit 2 Tech Specs, and Unit 2 COLR ANO-2-JPM-NRC-ADMIN-PDIL Page 3 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREINITIATING CUE:It is now 8-1-09 at 19:00 (250.25 EFPD) and the SM/CRS directs "Using OP-2102.004A for the conditionsstated above determine applicable CEA insertion limits (if any) and if any time limits for the currentconfiguration have been exceeded."START TIME:PERFORMANCE CHECKLIST STANDARD(Circle One)1. Using OP-2102.004determines that the COLRmust be referenced todetermine if any limits areapplicable.Examinee correctly derivedOP-2102.004 that the COLRmust be referenced todetermine if any limits apply.N/A SAT UNSAT (C)2. Using cycle 20 COLR figure 3determines that Group 6CEA's are inserted into thelong term steady stateinsertion limit of operation.Examinee correctly derivedfrom graph based on givenvalues that Group 6 CEAs areinserted into the long termsteady state insertion limits(LTSSIL).N/A SAT UNSAT (C)3. Using Tech Spec 3.1.3.6 orOP-2102.004 determines thelimits for present CEAconfiguration.Examinee determines that thecurrent CEA configuration islimited to < 5 EFPD per 30EFPD and <14 EFPD percalendar year.N/A SAT UNSAT(C) 4. Using Tech Spec 3.1.3.6 orOP-2102.004 determines ifany time limits have beenexceed for LTSSIL.Examinee determines that .25EFPD is less than 5 EFPD andno limits have been exceeded.N/A SAT UNSAT ENDSTOP TIME:

ANO-2-JPM-NRC-ADMIN-PDIL Page 4 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS

The plant has been at 100% since January 1 st of this year with CEAs at the programinsertion limit. The following conditions were established on 8-1-09 at 12:00 which was 250 EFPD:Plant power was lowered to 85% power due to 'A' Main Feedwater pumpoutage for bearing replacement.Group P CEAs are full out.Group 6 CEAs are being used for ASI control and are 90" withdrawn.COLSS ASI is -.07.#1 CEAC is inoperable for Surveillance testing.#2 CEAC is operable.INITIATING CUE:It is now 8-1-09 at 19:00 (250.25 EFPD) and the SM/CRS directs "Using OP-2102.004A forthe conditions stated above determine applicable CEA insertion limits (if any) and if anytime limits for the current configuration have been exceeded."Applicable CEA insertion limits (If any) ______________________________________Have any time limits for the current configuration been exceeded? ___________________

NOCEA Group 6 Long Term Steady State Insertion Limits ANO-2-JPM-NRC-ADMIN-PDIL Page 5 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS

The plant has been at 100% since January 1 st of this year with CEAs at the programinsertion limit. The following conditions were established on 8-1-09 at 12:00 which was 250 EFPD:Plant power was lowered to 85% power due to 'A' Main Feedwater pumpoutage for bearing replacement.Group P CEAs are full out.Group 6 CEAs are being used for ASI control and are 90" withdrawn.COLSS ASI is -.07.#1 CEAC is inoperable for Surveillance testing.#2 CEAC is operable.INITIATING CUE:It is now 8-1-09 at 19:00 (250.25 EFPD) and the SM/CRS directs "Using OP-2102.004A forthe conditions stated above determine applicable CEA insertion limits (if any) and if anytime limits for the current configuration have been exceeded."Applicable CEA insertion limits (If any) ______________________________________Have any time limits for the current configuration been exceeded? ___________________

ANO-2-JPM-NRC-ADMIN-2P-35A Review Page 1 of 6ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2REV#: 001DATE:SYSTEM/DUTY AREA: Equipment ControlTASK: Identify Errors in a completed surveillance.JTA#: ANO-2-RO-SPRAY-SURV-22KA VALUE RO:3.7SRO:4.1KA

REFERENCE:

2.2.12APPROVED FOR ADMINISTRATION TO:

RO: XSRO:TASK LOCATION:INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:CLASSROOM: PerformPOSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD:SIMULATE:PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:15 MinutesREFERENCE(S): OP-2104.005 Supplement 1 completed formEXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-ADMIN-2P-35A Review Page 2 of 6ADMINISTRATIVE JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion ofOP 1064.023 Attachment 6 with the examinee.JPM INITIAL TASK CONDITIONS

The Containment Spray System 2P-35A QUARTERLY TEST WITH SDC SECURED hasjust been completed IAW Procedure 2104.005 Containment Spray Supplement 1.TASK STANDARD: Review the marked up copy of the surveillance and find 3 of the 4errors and determine that 2P-35A is not operable.TASK PERFORMANCE AIDS: Marked up Copy of OP-2104.005 Supplement 1.

ANO-2-JPM-NRC-ADMIN-2P-35A Review Page 3 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREINITIATING CUE:The Control Room Supervisor/Shift Manager directs determination of the operability of the Train AContainment Spray System by performing a review of completed surveillance data and circle any errors oromissionsfound.START TIME:PERFORMANCE CHECKLIST STANDARD(Circle One)1. Perform review of thesurveillance procedure results.Reviews the surveillanceprocedure provided.N/A SAT UNSAT (C)2. Discover errorsand omissionsPump D/P is out of LIMITINGRANGE FOR OPERABILITY.YES has been circled instead of NO.Axial Vibes Upper Motor Brg isout of LIMITING RANGE FOROPERABILITY.2BS-1A is not marked as full open.Pump D/P is out of LIMITINGRANGE FOR OPERABILITY.YES has been circled instead of NO.Axial Vibes Upper Motor Brg isout of LIMITING RANGE FOROPERABILITY.2BS-1A is not marked as full open(Identification of three of thefour errors required and two ofthe three must be the PumpD/P and the Axial Vibration)N/A SAT UNSATN/A SAT UNSATN/A SAT UNSATN/A SAT UNSAT (C)3. Report that 2P-35A isinoperable.Examinee determines that 2P-35A is inoperable.N/A SAT UNSAT ENDSTOP TIME:

ANO-2-JPM-NRC-ADMIN-2P-35A Review Page 4 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS

The Containment Spray System 2P-35A QUARTERLY TEST WITH SDCSECURED has just been completed IAW Procedure 2104.005 ContainmentSpray Supplement 1.INITIATING CUE:The Control Room Supervisor/Shift Manager directs determination of theoperability of the Train A Containment Spray System by performing a reviewof completed surveillance data and circle any errors or omissions found.

ANO-2-JPM-NRC-ADMIN-2P-35A Review Page 5 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS

The Containment Spray System 2P-35A QUARTERLY TEST WITH SDCSECURED has just been completed IAW Procedure 2104.005 ContainmentSpray Supplement 1.INITIATING CUE:The Control Room Supervisor/Shift Manager directs determination of theoperability of the Train A Containment Spray System by performing a reviewof completed surveillance data and circle any errors or omissions found.

PROC./WORK PLAN NO.2104.005PROCEDURE/WORK PLAN TITLE:CONTAINMENT SPRAYPAGE: 70 of 106CHANGE 56SUPPLEMENT 1PAGE 6 OF 7 3.0ACCEPTANCE CRITERIA 3.1Record values observed during 2P-35A operation AND compare againstlimiting range of values for operability.TEST QUANTITYINSTRUMENT(INCLUDETEST INST.MEASURED VALUEACCEPTABLENORMAL RANGELIMITINGRANGE FOROPERABILITYIS DATA INLIMITINGRANGE?Running SuctionPressure2PI-5677(local)32.5 psig N/A> 6 psigYES NODischarge2PI-5678(local)245.5psig N/A N/A N/APressure2PI-5622(2C17)247.5psig N/A N/A N/APumpP2PI-5678 -2PI-5677 215 psid N/A214 to245.8 psidYES NOFlow (1)2FIS-5610(2C17)2430.00 gpm N/A 2225 gpmYES NO 49 50 48Motor RunningAmps(CR-1-96-0272-07

)Ammeter at2A-304ABCAmpsAmpsAmps N/A N/A N/AUpper Motor BrgRadial #1(North) Vibes0.105in/sec 0.155in/sec 0.372in/secYES NOUpper Motor BrgRadial #2 (West)Vibes0.135in/sec 0.162in/sec 0.390in/secYES NOUpper Motor BrgAxial Vibes0.321in/sec 0.107in/sec 0.258in/secYES NO2BS-4A N/A() if closed N/AClosedYES NO2BS-1A (2)

N/A( ) if FullOpen perComponentEngineer N/AFull Open perComponentEngineerYES NO N/A2BS-1B Closure{4.3.4}InitialP505834.5 N/A N/A N/AFinal P505841.2 N/A N/A N/AFinal -Initial 6.7 N/A> 4 psidYES NO{4.3.2}(1) 2225 gpm verifies partial stroke of 2BS-1A AND full stroke of2BS-3A AND 2BS-4A(2) N/A if test not performedVibration Instrument Number _____ VIB001__________ Cal Due Date ____09/30/2009______Vibration Data Collected By ____________ Joe STA____________________________FOR TRAINING PURPOSES ONLY

A2JPM-RO-RWPPAGE 1 OF 5ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2REV#: 002DATE:SYSTEM/DUTY AREA: Radiation ControlTASK:Review RWP and determine requirements for tagging 'B' LPSI pump.JTA#: ANO-2-RO-ADMIN-NORM-62KA VALUE RO:3.5SRO:3.6KA

REFERENCE:

2.3.7APPROVED FOR ADMINISTRATION TO:

RO: XSRO: XTASK LOCATION:INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:PerformSIMULATOR:LAB:PerformPOSITION EVALUATED:

RO:SRO:ACTUAL TESTING ENVIRONMENT:SIMULATOR:PLANT SITE:LAB:TESTING METHOD:SIMULATE:PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:10 MinutesREFERENCE(S):2009-2002; RWP and survey form for 'B' HPSI pump room.EXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

A2JPM-RO-RWPPAGE 2 OF 5ADMINISTRATIVE JOB PERFORMANCE MEASUREINITIAL PLANT CONDITIONS1. 100% power steady state.2. 'B' LPSI pump must be tagged out for repair of mechanical seal.TASK STANDARD:Using RWP and attached 'B' HPSI pump room survey map: Identify 5 of the 8 following requirements to control contamination: Determine that a single set of anti-Cs are required. Prior to draining or venting any potentially contaminated system or known contaminatedsystems, notify RP.

OrNotify RP when performing activities which could change plant radiological conditions. Thisincludes venting/draining radioactive systems, performing degas or decay heat/shutdowncooling operations, or other non-routine system functions. Use non-porous mats or pads when kneeling, sitting or laying in contaminated areas. All joints between Anti-C gloves and sleeves must be taped. Once gloves have made contact with any surface inside a Contamination Area boundary,the gloves are considered contaminated and must be removed PRIOR to crossing backinto the clean area. When using temporary hoses to vent or drain a radioactive system, ensure the hose islabeled for radioactive system use only. Contact RP to verify that radiological controls areadequate. When venting or draining, monitor the rate of system drain to ensure the rate of drain doesNOT exceed the capacity of the floor drain. Upon exiting areas posted as "Contamination Area", perform a hand and foot frisk at thedesignated frisker location.TASK PERFORMANCE AIDS: RWP 2009-2002 and survey map.SIMULATOR SETUP:

NA A2JPM-RO-RWPPAGE 3 OF 5ADMINISTRATIVE JOB PERFORMANCE MEASUREInitiating CUE:The Shift Manager directs "Use the attached RWP, 2009-2002 and the survey map for 'B' HPSI room, anddetermine all radiological requirements to minimize the spread of contamination while hanging tags formaintenance on 'B' LPSI pump mechanical seal."START TIME:PERFORMANCECHECKLISTSTANDARDCIRCLE ONENOTE: Provide RWP and survey sheet.

1.Review RWP.Reviews attached RWP for requirements.N/A SAT UNSAT (C)2.Determine 5 of the 8 requirementslisted in RWP 2009-2002 to minimizethe spread of contamination.Using the survey report determined thefollowing :The 'B' LPSI area is a contamination areawhich requires a single set of anti-C's per theRWP.Prior to draining or venting any potentiallycontaminated system or knowncontaminated systems, notify RP.

OrNotify RP when performing activities whichcould change plant radiological conditions.This includes venting/draining radioactivesystems, performing degas or decayheat/shutdown cooling operations, or othernon-routine system functionsUse non-porous mats or pads when kneeling,sitting or laying in contaminated areas.All joints between Anti-C gloves and sleevesmust be taped.Once gloves have made contact with anysurface inside a Contamination Areaboundary, the gloves are consideredcontaminated and must be removed PRIOR tocrossing back into the clean area.When using temporary hoses to vent or draina radioactive system, ensure the hose islabeled for radioactive system use only.Contact RP to verify that radiological controlsare adequate.When venting or draining, monitor the rate ofsystem drain to ensure the rate of drain doesNOT exceed the capacity of the floor drain.Upon exiting areas posted as "ContaminationArea", perform a hand and foot frisk at thedesignated frisker location.N/A SAT UNSAT ENDSTOP TIME:

A2JPM-RO-RWPPAGE 4 OF 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER's COPYINITIAL PLANT CONDITIONS1. 100% power steady state.2. 'B' LPSI pump must be tagged out for repair of mechanical seal.Initiating CUE:The Shift Manager directs "Use the attached RWP, 2009-2002 and the survey map for 'B'HPSI room, and determine all radiological requirements to minimize the spread ofcontamination while hanging tags for maintenance on 'B' LPSI pump mechanical seal."

A2JPM-RO-RWPPAGE 5 OF 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE's COPYINITIAL PLANT CONDITIONS1. 100% power steady state.2. 'B' LPSI pump must be tagged out for repair of mechanical seal.Initiating CUE:The Shift Manager directs "Use the attached RWP, 2009-2002 and the survey map for 'B'HPSI room, and determine all radiological requirements to minimize the spread ofcontamination while hanging tags for maintenance on 'B' LPSI pump mechanical seal."

Arkansas Nuclear One EntergyRADIOLOGICAL WORK PERMIT RWP No.:20092002 Rev. 00 RWP Title

OPERATIONS ACTIVITIES UNIT-2

• 20092002* 1.16 Task:REACTOR OPERATION + SURVEIL Comments: RWP Type:GENERAL Close On Date

12/31/2009 Begin Date

1/1/2009 RWP Status

ACTIVE Prepared By

LACY, RUSSELL S Job Supervisor

Randall Walters Estimated Dose

880 mrem Estimated Hours

20,512.00 Actual Dose

66 mrem Actual Hours

3,563.88 Chirp Rate

ALARA ID: Stay Time Alarm (hh: mm):LocationsBuildingsElevationsRooms 354 NON-LOCKED HIGH RADIATIONAREALOW LEVEL RADWASTE BUILDING 354OUTSIDE CONTROLLED ACCESSOLD RADWASTE BUILDING ALLOUTSIDE CONTROLLED ACCESSOUTSIDE CONTROLLED ACCESS ALL NON-LOCKED HIGH RADIATIONAREAUNIT 2 AUXILIARY BUILDINGRadiological Conditions Description Value UnitSmear data is in dpm

/100 cm 2unless otherwise noted

.<1-40 K DPM/100 CM 2General area gamma dose rates are in mrem

/hour unless otherwise

<1-200MILLIREM/HOURTasks Status Description Task 1 ActiveOPERATIONS ACTIVITIES ANO-2RequirementsRequirement GroupsRequirement Descriptions N/AAdditional Instrutions Instructions 1: Instructions 2: Instructions 3:Approvals Approver TitleName Date ALARA REVIEW NICKELS , THOMAS W 12/10/2008 RWP PREPARER NICKELS , THOMAS W 12/10/2008 RP SUPERVISORMARVEL JR ,STANLEY D 12/11/2008Attachments N/A3/3/2009 8:31:28PM Page 1 of 1 Arkansas Nuclear One EntergyRADIOLOGICAL WORK PERMIT Task Number

1 RWP No.: 20092002Rev.: 00 Task Status

Active Task Description

OPERATIONS ACTIVITIES ANO-2 1.16 Task:REACTOR OPERATION + SURVEIL ALARA ID: Stay Time Alarm (hh: mm): 16:00 Estimate Dose

880.00 Chirp Rate

Estimate Hours

20,512.00Alarm Settings Hi-Rad: Yes Hi-Contamination

No Locked Hi

-Rad: No Hot Particle

No 200.00 20.00Low Gamma Dose (mrem)High Gamma Rate (mrem/hr)High Gamma Dose (mrem)Low Gamma Rate (mrem/hr)Low Beta DoseHigh Beta RateHigh Beta DoseLow Beta DoseLow Neutron DoseHigh Neutron RateHigh Neutron DoseLow Neutron Dose3/3/2009 8:32:04PM Page 1 of 4 Arkansas Nuclear One EntergyRADIOLOGICAL WORK PERMIT Task Number

1 RWP No.: 20092002Rev.: 00RequirementsRequirement GroupsRequirement DescriptionsAll materials are required to be surveyed in a small articles monitor or hand frisked byRP (with RP Supervisor approval) PRIOR TO unconditional release from aRadiologically Controlled Area.Contamination ControlPrior to draining or venting any potentially contaminated system or knowncontaminated systems, notify RP.Use non-porous mats or pads when kneeling, sitting or laying in contaminated areas.A blue dot on your Dosimeter of Legal Record (DLR) is used to identify a hearingimpairment with regards to Electronic Alarming Dosimeter (EAD). IF you aredesignated as having a hearing impairment, THEN you must have an alarm amplifyingdeviceDosimetry RequirementsFOR WORK IN HIGH RADIATION AREAS- If your work conditions are in OR willcause hearing impairment (such as work in a high noise area, use of a communicationsheadset, etc.) THEN the use of an EAD amplifying device (PAM) is requiredIf an EAD dose alarm occurs: Secure Work, Immediately leave the RCA, Notify RP.If an EAD dose rate alarm occurs: Secure Work, Back out of the immediate area untilthe alarm clears, Notify others in your work crew, Immediately notify RP for furtherinstructions.Periodically check your EAD. This check should be performed more frequently inareas where your ability to hear is diminished.Whole body DLR and EAD required for entryUse Low Dose Waiting Areas whenever possible to minimize exposure.Exposure ReductionAll joints between Anti-C gloves and sleeves must be taped.Protective RequirementsEntry into Contamination Areas require Single Anti-Cs.Entry into High Contamination Areas require Double Anti-Cs .Notify RP prior to reaching across Contamination Area boundaries.Once gloves have made contact with any surface inside a Contamination Areaboundary, the gloves are considered contaminated and must be removed PRIOR tocrossing back into the clean areaOperations personnel may reach across a Contamination Area boundary without glovesONLY for the purpose of using a flashlight to illuminate an item or using a mirror toenhance the ability to inspect PROVIDED that nothing is touched.When using temporary hoses to vent or drain a radioactive system, ensure the hose islabeled for radioactive system use only. Contact RP to verify that radiological controlsare adequate.When venting or draining, monitor the rate of system drain to ensure the rate of draindoes NOT exceed the capacity of the floor drain.When work involves reaching across a Contamination Area boundary, and the onlyportion of the body that will make contact with a contaminated surface is the hands,THEN the use of cotton liners with rubber gloves or surgeon's gloves is permitted.A "Cat 3 Advanced Radworker" may enter posted High Radiation Areas IF he/she isusing a gamma sensitive RP instrument to monitor dose rates. (NOTE: An EAD isNOT an appropriate survey instrument).RP CoverageInitial / Intermittent RP coverage is required for entry in to High Radiation Areas.Notify RP when performing activities which could change plant radiological conditions

.This includes venting/draining radioactive systems, performing degas or decayheat/shutdown cooling operations, or other non-routine system functions3/3/2009 8:32:04PM Page 2 of 4 Arkansas Nuclear One EntergyRADIOLOGICAL WORK PERMIT Task Number

1 RWP No.: 20092002Rev.: 00Notify the Zone coverage RP or the on-duty shift RP of areas to be entered and work tobe performed. RP is not required to be notified for entries to the Auxiliary Building toperform routine activities that do not involve HRA, CA, overhead entry or systembreech.Tech Spec monitoring is required for entry into High Radiation Areas and isaccomplished by meeting the following criteria: A radiological brief from RP,AND anelectronic alarming dosimeter (EAD).Radiological conditions should be reviewed to ensure awareness of conditions in yourwork area. This information can be obtained from either a Status Board OR RPpersonnelRadiological ConditionsUpon exit of an RCA, whole body monitoring is required utilizing a whole bodycontamination monitor. A whole body gamma monitor must also be cleared. IF theRCA is a satelite RCA with no whole body contaminaton monitor available, THEN theradworker should: a) perform a hand and foot frisk. b) IF the frisk indicatescontamination is present, THEN contact RP. c) IF the frisk DOES NOT indicate thepresence of contamination, THEN proceed to the nearest whole body contaminationmonitorUpon exiting areas posted as "Contamination Area" , perform a hand and foot frisk atthe designated frisker location.Based on historical and current data, the airborne radioactivity is less than 30 percentof a DAC. Respiratory protection is not required unless otherwise directed by RPSupervision.Respiratory ProtectionAccess to the overhead >8 feet is allowed with provisions specified by RP. Whenaccessing overheads, then wear rubber gloves while operating valves but remove themprior to descending the ladder. Use a ladder to climb directly to the valve to beoperated. DO NOT touch any interferences or components in the overhead withoutexplicit permission by RP. Upon completion, perform a large area masslin survey ofthe ladder to determine if any cross contamination has occurred. Notify RPimmediately if the ladder is contaminated. Use your survey meter to obtain dose ratesof all areas entered.Special Radiological RequirementsAccess to the top of partial walls separating Radiation/High Radiation areas fromLocked High Radiation Areas or Very High Radiation Areas is NOT permitted on thisRWP.Prerequisites for a secondary resin transfer: A berm sufficient to contain the materialbeing tranferred is required.The resin transfer fill head is to be secured such thatchanges in pressure will not cause a spill. Pre-transfer walkdowns must be done toensure that hose connections and leak integrity is satisfactory. A resin sample must betaken and analyzed. If the total activity to be transferred is less than 5.389E02microcuries, no further review is required.Work involving alpha contamination greater than or equal to 100 dpm/100cm2 cannotbe worked on a General RWPStop Work CriteriaWork involving beta/gamma contamination greater than 5 mrad/hour/100cm2 musthave controls inplace to eliminate the potential of creating an airborne radioactivityarea or the potential to cause "clean area" contaminationAdditional Instructions Instructions 1: Instructions 2: Instructions 3:3/3/2009 8:32:04PM Page 3 of 4 Arkansas Nuclear One EntergyRADIOLOGICAL WORK PERMIT Task Number

1 RWP No.: 20092002Rev.: 00AttachmentsN/A3/3/2009 8:32:04PM Page 4 of 4 CA CA RA6 - 12 mrem/hr5 - 10 mrem/hr10- 15 mrem/hr 2015 2014 2013 2-5 mrem/hrLDWARadiation Area (RA)High Radiation Area (HRA)Locked High Radiation Area (LHRA)Low Dose Waiting Area (LDWA)RADS Telemetry DeviceDose Rates may change due to current conditions.This map is for yourinformation only. Contact aRadiation ProtectionTechnician for answers toquestions.

ANO-2-JPM-NRC-ADMIN-DNBRL Page 1 of 5ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2REV#: 001DATE:SYSTEM/DUTY AREA: Conduct of OperationsTASK: Determine if COLR DNBR limit is being met during a loss of COLSS.JTA#: ANO-2-SRO-EOPAOP-OFFNORM-233KA VALUE RO:3.9SRO:4.2KA

REFERENCE:

2.1.25APPROVED FOR ADMINISTRATION TO:

RO:SRO: XTASK LOCATION:INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformCLASSROOM: PerformPOSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD:SIMULATE:PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:15 MinutesREFERENCE(S): Unit 2 Tech Specs and Unit 2 COLREXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-ADMIN-DNBRL Page 2 of 5ADMINISTRATIVE JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion ofOP 1064.023 Attachment 6 with the examinee.JPM INITIAL TASK CONDITIONS

The plant is at 85% power, Steady State due to 2P-1A Feedwater pump is out ofservice for maintenance. COLSS has been declared inoperable due to failed power supplies. The CPC average DNBR is 2.35. The CPC average ASI is .0001 #1 CEAC is inoperable for Surveillance testing. #2 CEAC is operable.TASK STANDARD: Determine that Technical Specifications LCO 3.2.4 action b isapplicable.TASK PERFORMANCE AIDS: Unit 2 Tech Specs and Unit 2 COLR ANO-2-JPM-NRC-ADMIN-DNBRL Page 3 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREINITIATING CUE:Determine if any Tech Specs LCOs are applicable and/or actions that are required for this condition.

START TIME:PERFORMANCE CHECKLIST STANDARD(Circle One)1. Using Tech Spec 3.2.4determines that the COLRmust be referenced todetermine if TS are satisfied.Examinee correctly derivedfrom Tech Spec 3.2.4 thatsince COLSS is inoperable,the COLR graph must bereferenced to determine ifTech Spec 3.2.4 is met.N/A SAT UNSAT (C)2. Using cycle 20 COLR figuredetermines DNBR is not inthe acceptable region foroperation and that Tech SpecLCO 3.2.4.c should beentered.Examinee correctly derivedfrom graph based on givenvalues that DNBR is not in theacceptable region of operationand determined that LCO3.2.4.c is applicable for thecurrent condition.N/A SAT UNSAT (C)3. Using Tech 3.2.4 determinethat DNBR must meet therequirements of T.S 3.2.4 action bExaminee correctlydetermines the DNBR must berestored to meet therequirements of the COLRgraph within 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> to complywith Tech Spec 3.2.4 action b.N/A SAT UNSATEXAMINER's NOTE: Examinee may discuss the Tech Spec applicability at this point statingthat Tech Spec 3.2.4 LCO requires power to be lowered so that DNBR isrestored to the acceptable region within 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br />.

ENDSTOP TIME:

ANO-2-JPM-NRC-ADMIN-DNBRL Page 4 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS

The plant is at 85% power, Steady State due to 2P-1A Feedwater pump is out ofservice for maintenance. COLSS has been declared inoperable due to failed power supplies. The CPC average DNBR is 2.35. The CPC average ASI is .0001 #1 CEAC is inoperable for Surveillance testing. #2 CEAC is operable.INITIATING CUE:Determine if any Tech Specs LCOs are applicable and/or actions that are required for this condition.Applicable Tech Spec LCOs (if any) _________________________Actions required to comply with Tech Specs (if any) ______________________________Tech Spec 3.2.4 LCO Action b requires power to be lowered so that DNBR is restored tothe acceptable region within 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br />.T.S. LCO 3.2.4.cT.S. LCO 3.2.4. Action b ANO-2-JPM-NRC-ADMIN-DNBRL Page 5 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS

The plant is at 85% power, Steady State due to 2P-1A Feedwater pump is out ofservice for maintenance. COLSS has been declared inoperable due to failed power supplies. The CPC average DNBR is 2.35. The CPC average ASI is .0001 #1 CEAC is inoperable for Surveillance testing. #2 CEAC is operable.INITIATING CUE:Determine if any Tech Specs LCOs are applicable and/or actions that are required for this condition.Applicable Tech Spec LCOs (if any) _________________________Actions required to comply with Tech Specs (if any) ______________________________________________________________________________________________________

A2JPM-SRO-SFPMUPAGE 1 of 9ADMINISTRATIVE JOB PERFORMANCE MEASUREUNIT: 2 REV#: 000DATE:SYSTEM/DUTY AREA: Conduct of OperationsTASK:Review Spent Fuel Pool Makeup Calculation for ErrorsJTA#: ANO-SRO-SRO-ADMIN-NORM-197KA VALUERO:4.3SRO:4.4KA

REFERENCE:

2.1.23APPROVED FOR ADMINISTRATION TO:RO:SRO: XTASK LOCATION:INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformLAB:POSITION EVALUATED:RO:SRO:ACTUAL TESTING ENVIRONMENT:SIMULATOR:PLANT SITE:LAB:TESTING METHOD:SIMULATE: PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:15 MinutesREFERENCE(S):OP 2104.006, Attachment FEXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED INTHIS JPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:StartTime StopTimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

A2JPM-SRO-SFPMUPAGE 2 of 9ADMINISTRATIVE JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6with the examinee.JPM INITIAL TASK CONDITIONS: Plant is at 100% power. PMS computer is out of service. Initial Spent Fuel Pool Level = 401' 0" Tilt Pit Gate is installed Cask Loading Pit Gate is installed 'A' BAM tank concentration is 5950 ppmb SFP boron concentration is 2964 ppmb Cask loading pit operations has lowered the SFP level CBOT has performed actions per OP 2104.006 step 10.3. Final Spent Fuel Pool Level = 401' 4"TASK STANDARD:SRO candidates should identify the following:

1)Boron Concentration of the feed source should be 5950 NOT 4950.

(C B)2) The Feed volume (F) calculated previously was transposed into the feed volumes calc as 1788 gallonsnot the 1878 gallons correctly calculated. Therefore both the calculated Boric acid and DI water volumes are wrong.And calculate the following correct feed volumes:3) Boric acid volume calculated to be within 910 gallons to 960 gallons.

(V B)4) Determine DI water volume to be within 918 gallons to 968 gallons.

(V W)TASK PERFORMANCE AIDS:OP 2104.006, Attachment F A2JPM-SRO-SFPMUPAGE 3 of 9ADMINISTRATIVE JOB PERFORMANCE MEASUREINITIATING CUE:Chemistry has just notified the Control Room that when SPF level is raised, we need to make a single feedsolution using a combination of boric acid from the 'A' BAM tank and DI water maintaining SFP boronconcentration 2964 PPM. The SM directs, "Review for accuracy and correct any errors in the completed OP2104.006, Attachment F."START TIME:PERFORMANCE CHECKLISTSTANDARDS(Circle One)1. Reviewed the completed formOP 2104.006, Attachment F.Reviewed the completed formOP 2104.006, Attachment F. N/A SAT UNSAT2. Determined the calculatedvolume of solution to becorrect.Calculated the feed volume tobe added to the SFP, F, to be1878 gallons. N/A SAT UNSAT C3. Determined that the boronconcentration of the feedsource was in error.Recognized the boronconcentration of the feed sourcewas recorded as 4950 ppminstead of the given value of5950 ppm. N/A SAT UNSAT C4. Determined the calculatedvolume of solution used in thecalculation of the feedvolumes of boric acidRecognized that the feedvolume to be added to the SFP,F, was recorded in error as1788 gallons NOT the 1878gallons calculated on theprevious page. N/A SAT UNSATExaminer's Note: the candidate may need to be prompted to calculate the volume of Boric acid and DI water.

C5. Determined the Boron volumeto be added as calculated wasin error and determined thecorrect volume to be 910gallons to 960 gallons.Recognized the Boron volumeto be added as calculated wasin error and determined thecorrect volume to be 935.5gallons instead of the 1070.6gallons. N/A SAT UNSAT C6. Determined the DI watervolume to be added ascalculated was in error anddetermined the correct volumeto be within 918 gallons to 968gallons.Recognized the DI watervolume to be added ascalculated was in error anddetermined the correct volumeto be 942.5 gallons instead of717.4 gallons. N/A SAT UNSAT ENDSTOP TIME:

A2JPM-SRO-SFPMUPAGE 4 of 9ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS: Plant is at 100% power. PMS computer is out of service. Initial Spent Fuel Pool Level = 401' 0" Tilt Pit Gate is installed Cask Loading Pit Gate is installed 'A' BAM tank concentration is 5950 ppmb SFP boron concentration is 2964 ppmb Cask loading pit operations has lowered the SFP level CBOT has performed actions per OP 2104.006 step 10.3. Final Spent Fuel Pool Level = 401' 4"INITIATING CUE:Chemistry has just notified the Control Room that when SPF level is raised, we need to makea single feed solution using a combination of boric acid from the 'A' BAM tank and DI watermaintaining SFP boron concentration 2964 PPM. The SM directs, "Review for accuracy andcorrect any errors in the completed OP 2104.006, Attachment F."

A2JPM-SRO-SFPMUPAGE 5 of 9ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS: Plant is at 100% power. PMS computer is out of service. Initial Spent Fuel Pool Level = 401' 0" Tilt Pit Gate is installed Cask Loading Pit Gate is installed 'A' BAM tank concentration is 5950 ppmb SFP boron concentration is 2964 ppmb Cask loading pit operations has lowered the SFP level CBOT has performed actions per OP 2104.006 step 10.3. Final Spent Fuel Pool Level = 401' 4"INITIATING CUE:Chemistry has just notified the Control Room that when SPF level is raised, we need to makea single feed solution using a combination of boric acid from the 'A' BAM tank and DI watermaintaining SFP boron concentration 2964 PPM. The SM directs, "Review for accuracy andcorrect any errors in the completed OP 2104.006, Attachment F."

PROC./WORK PLAN NO.2104.006PROCEDURE/WORK PLAN TITLE:FUEL POOL SYSTEMSPAGE:1 of 9CHANGE: ATTACHMENT F PAGE 1 of 4 BORIC ACID CONCENTRATION ADJUSTMENT VOLUME DATA REFERENCE NOTE If filling Tilt Pit, this attachment should only be used to estimate time needed to complete evolution because the Tilt Pit does NOT have installed level indication.

Initial level is only estimated and can result in inaccurate calculation.

Gal/Ft.Total Volume (Gal)

CASK LOADING PIT (CLP)- Elev 358' to bottom of gate 722.4 13,726- Bottom of gate to Elev 401'6" 795.6 19,493 FUEL TILT PIT (FTP)- Elev 362' to bottom of gate 1,196.8 (1) 17,952 (1)- Bottom of gate to Elev 401'6" 1,275.3 31,244 SPENT FUEL POOL (SFP)- Elev 362' to top of racks 5,349.5 (2)84,255 (2)- Top of racks to Elev 401'6" 5,634.4 133,817 NOTES 1. Does NOT include volume occupied by tilt machine.

2. Does NOT include fuel. Includes ~ 600 ft 3 allowance for fuel racks.

Fuel Pool Makeup Volume Calculation (N/A areas NOT hydraulically connected to SFP)

F = Feed Volume L I= Level Change (in inches)

F = [(L I)(SFP Level gal

)(1 ft)]+[(L I)(CLP Level gal

)(1 ft)]+[(L I)(FTP Level gal

)(1 ft)] (1 ft) (12 in.) (1 ft) (12 in.) (1 ft) (12 in.)F =[(4 in.)(5634.4 gal)

+ [( N/A in.)(795.6 gal)

+ [(N/A in.)(1275.3 gal) 12 in. 12 in. 12 in.

F = ____1878______gallons Cask Loading Pit Makeup/Fill Volume Calculation (Gate installed, N/A elevation NOT filled)

F = Feed Volume L B = Level change (in feet) below bottom of gate L A = Level change (in feet) above bottom of gate F = [(L B)(Volume below bottom of gate in gal/ft)] + [(L A)(Volume above bottom of gate in gal/ft)]F = [__N/A____ ft.)(722.4 gal/ft)] + [(___

N/A___ ft)(795.6 gal/ft)

F = _____N/A ____gallons PROC./WORK PLAN NO.2104.006PROCEDURE/WORK PLAN TITLE:FUEL POOL SYSTEMSPAGE:2 of 9CHANGE: ATTACHMENT F PAGE 2 of 4 Fuel Tilt Pit Makeup/Fill Volume Calculation (Gate installed, N/A elevation NOT filled)

F = Feed Volume L B = Level change (in feet) below bottom of gate L A = Level change (in feet) above bottom of gate F = [(L B)(Volume below bottom of gate in gal/ft)] + [(L A)(Volume above bottom of gate in gal/ft)]

F = [_N/A ft.)(1196.8 gal/ft)] + [(__

N/A ft)(1275.3 gal/ft)

F = __ N/A _gallons Required Feed Solution Concentration Calculation C I = Initial Fuel Pool Boron Concentration =

2964 ppm C F = Final Desired Boron Concentration =

2964 ppm C W = Feed Solution Concentration =(V F x C F) - (V I x C I) F C W = (217,133 gal x 2964 ppm) - (215255 gal x 2964 ppm) (1878 gal)C W =2964 ppm IF Feed Solution will be a combination of Boric Acid and demineralized water, THEN calculate feed volume as follows:

F = Feed Volume (from volume calculation)

V B = Volume of Boric Acid to Add V W = Volume of DI Water to Add C B = Boron Concentration of feed source =

4950 ppm Calculate Feed Volumes V B = (F) x (C F) = (1788 gal) x (2964 ppm) C B (4950 ppm)V B =1070.6 gal Amount of Boric Acid to add V W = F - V B = (1788 gal) - (1070.6 gal)V W =717.4 gal Amount of DI Wate r to add PROC./WORK PLAN NO.2104.006PROCEDURE/WORK PLAN TITLE:FUEL POOL SYSTEMSPAGE:3 of 9CHANGE: ATTACHMENT F PAGE 3 of 4 IF Feed Solution will be a combination of two Boric Acid solutions, THEN calculate feed volumes as follows:

F = Feed Volume (from volume calculation)

V B1 = Volume of 1 st Boric Acid Solution to add V B2 = Volume of 2 nd boric Acid Solution to add C B1 = Boron Concentration of 1 st Boric Acid Solution =

N/A ppm C B2 = Boron Concentration of 2 nd Boric Acid Solution =

N/A ppm C F = Boron Concentration of Feed Volume (F) =

N/A ppm Calculate Feed Volumes V B1 =F x (C F - C B2) (C B1 - C B2)V B1 = (N/A gal) x (N/A ppm -N/A ppm) (N/A ppm -N/A ppm)V B1 =N/A gal Volume of Boric Acid of Concentration C B1 to add V B2 = F - V B1 = (N/A gal) - (N/A gal)V B2 =N/A gal Volume of Boric Acid of Concentration C B2 to add Definition of terms:

I = Boron Concentration of Feed Solution desired V B = Boric Acid Volume C B = Boron Concentration of Boric Acid in BAM tank V W = Demineralized Water Volume To determine ratio of volumes of Demineralized Water and Boric Acid for makeup to maintain Specified Boron concentration:

V W = C B - C F = Ratio of demineralized water to Boric Acid V B C F to obtain desired feed concentration C F.This ratio may be used to adjust the flowrate settings on Boric Acid Flow Controller (2FIC-4926) and RMW Flow Controller (2FIC-4927) to provide a Feed Solution of the desired concentration.

PROC./WORK PLAN NO.2104.006PROCEDURE/WORK PLAN TITLE:FUEL POOL SYSTEMSPAGE:1 of 9CHANGE: ATTACHMENT F PAGE 4 OF 4 IF Feed solution boron concentration AND Feed volume is known, THEN calculate Final Spent Fuel Pool boron concentration as follows:

Definition of Terms CI = Initial Fuel Pool Boron Concentration CW = Feed Solution Concentration VF = Final Volume VI = Initial Volume F = Feed Volume Final Concentration Calculation CF = Final Boron Concentration = (CW x F) + (VI x CI)

VF CF = (CW 2964 ppm x F 1788 gal) + (VI 215,255 gal x CI 2964 ppm)_________________________________________________________________________________

VF 217,133 gal CF =2964 ppm Performed By Joe_Ro Date Today's Date Supervisor ___________________________________ Date____________________________

ANO-2-JPM-NRC-ADMIN MSSVINOP Page 1 of 5ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2REV#: 001DATE:SYSTEM/DUTY AREA: Equipment ControlTASK: Verify RPS trip set point determination for inoperable MSSVJTA#: ANO-SRO-ADMIN-NORM-231KA VALUE RO:3.4SRO:4.7KA

REFERENCE:

2.2.40APPROVED FOR ADMINISTRATION TO:

RO:SRO: XTASK LOCATION:INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformCLASSROOM: PerformPOSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD:SIMULATE:PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:15 MinutesREFERENCE(S): Unit 2 Tech Spec 3.7.1.1EXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-ADMIN MSSVINOP Page 2 of 5ADMINISTRATIVE JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion ofOP 1064.023 Attachment 6 with the examinee.JPM INITIAL TASK CONDITIONS

The plant is at 90% power, 440 EFPD, Steady State. MSSV testing is in progress. One MSSV, 2PSV-1054 has been declared inoperable. The value for MTC provide by Reactor Engineering for 440 EFPD is -2.6 k/k/°F.TASK STANDARD: Determine the maximum High Linear Power Level and RPS trip setpoint to be 91.0% to comply with Technical Specification 3.7.1.1.TASK PERFORMANCE AIDS: Unit 2 Tech Specs ANO-2-JPM-NRC-ADMIN MSSVINOP Page 3 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREINITIATING CUE:Determine the Maximum High Linear Power Level and RPS Trip Set point per Tech Specs allowed for thiscondition to remain at power.PERFORMANCE CHECKLIST STANDARD(Circle One)1. Using Tech Spec 3.7.1 Table3.7-1 determines newmaximum power and RPSlinear power trip set point to be 79%.Examinee correctly derivedfrom table based on 1 MSSVinoperable, the maximumallowable linear power leveland RPS trip setpoint to be79%.N/A SAT UNSAT (C)2. Using Tech Spec 3.7.1 figure3.7-1 determines newmaximum power and RPSlinear power trip set point to be 91%.Examinee correctly derivedfrom graph based on MTC of

-2.6 k/k/°F and knowing thatone MSSV is inoperabledetermined that maximumpower and RPS linear powertrip set point should be 91.0%.N/A SAT UNSATEXAMINER's NOTE: Examinee should discuss the Tech Spec applicability at this pointstating that Tech Spec 3.7.1.1 LCO to allow power operations tocontinue provided that within 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> power is reduced to the maximumpower of 79% or as allowed by figure 3.7-1 (91%) and within 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br />,the RPS trip set point adjusted to be less than the value of 79% or asallowed in figure 3.7-1 (91%).

END ANO-2-JPM-NRC-ADMIN MSSVINOP Page 4 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS

The plant is at 90% power, 440 EFPD, Steady State. MSSV testing is in progress. One MSSV, 2PSV-1054 has been declared inoperable. The value for MTC provided by Reactor Engineering for 440 EFPD is -2.6 k/k/°F.INITIATING CUE:Determine the Maximum High Linear Power Level and RPS Trip Set point per Tech Specsallowed for this condition to remain at power.

ANO-2-JPM-NRC-ADMIN MSSVINOP Page 5 of 5ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS

The plant is at 90% power, 440 EFPD, Steady State. MSSV testing is in progress. One MSSV, 2PSV-1054 has been declared inoperable. The value for MTC provided by Reactor Engineering for 440 EFPD is -2.6 k/k/°F.INITIATING CUE:Determine the Maximum High Linear Power Level and RPS Trip Set point per Tech Specsallowed for this condition to remain at power.

ANO-2-JPM-NRC-KI Page 1 of 6ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2REV#: 001DATE:SYSTEM/DUTY AREA: Radiation Controls (A.3)TASK: Approve administration of Potassium Iodide.JTA#: ANO-SRO-EPLAN-EMERG-292KA VALUE RO:3.4SRO:3.8KA

REFERENCE:

2.3.14APPROVED FOR ADMINISTRATION TO:

RO:SRO: XTASK LOCATION:INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformCLASSROOM: PerformPOSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:CLASSROOM:TESTING METHOD:SIMULATE:PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:20 MinutesREFERENCE(S): 1903.035, Administration of Potassium IodideEXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-KI Page 2 of 6ADMINISTRATIVE JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion ofOP 1064.023 Attachment 6 with the examinee.JPM INITIAL TASK CONDITIONS

The plant is tripped from 100% power. 300 gpm LOCA in progress. Loss of Offsite power is in progress. LOCA EOP is being implemented. RDACS indicates an off site release in progress. Data indicates I-131 concentration of 5.0 E-04 ci/cc in area of work in Upper SouthPiping Penetration room. Whole body dose rates in area of work are 1Rem/hr. General Emergency has just been declared. Joe Mechanic has completed 1903.035C form, ANO Medical Questionnaire-IodineSensitivity. RP estimates that it will take approximately 15 minutes to complete emergency actionsand stop the release and all RP required controls/authorizations are complete. Air Purifying Respirator with Iodine Canister having a protection factor of 1.0 will beused in place of a SCBA due to piping interference. EOF, OSC and TSC have NOT been staffed.TASK STANDARD: Determine that KI should be administered.TASK PERFORMANCE AIDS: OP 1903.0035, Potassium Iodide Administration,completed form 1903.035C, ANO Medical Questionnaire-Iodine Sensitivity and 1903.035A,Potassium Iodide Administration.

ANO-2-JPM-NRC-KI Page 3 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREINITIATING CUE:Determine the need to issue KI, Potassium Iodide and complete necessary paperwork, using OP 1903.035.

START TIME:PERFORMANCE CHECKLIST STANDARD(Circle One)1. Review OP 1903.035,Administration of PotassiumIodide to determine criteria foradministering KI.Examinee determined thecriteria for administration of KIis 25 REM exposure toThyroid committed doseequivalent or if concentrationis unknown, the possibilityexists for receiving largeamounts of radioactiveairborne iodine.N/A SAT UNSAT (C)2. Using graph on 1903.035Attachment 1 and informationprovided in initial conditions,determine that Joe Mechanicwill exceed 25 REM duringthe maintenance evolution.Determined that expectedexposure will exceed 25 REMthreshold.N/A SAT UNSAT (C)3. Determine that Joe Mechanicis not sensitive to norexperienced an allergicreaction to Iodide.Reviewed 1903.035C formand determined that JoeMechanic was not sensitive tonor experienced an allergicreaction to Iodide.N/A SAT UNSAT4. Complete form 1903.035A.Completed all areas of form1903.035A, Potassium IodideAdministration, from initial conditions: Estimated Thyroid dosecommitment. Date. Respiratory protection. Signature of Joe Mechanicthat he chooses to receive KI.N/A SAT UNSAT ANO-2-JPM-NRC-KI Page 4 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREPERFORMANCE CHECKLIST STANDARD(Circle One)(C)5. Determine that KI may beapproved for distribution toJoe Mechanic during theUpper South Pipingpenetration work.Examinee approveddistribution of KI to JoeMechanic by signing anddating form.N/A SAT UNSAT ENDSTOP TIME:

ANO-2-JPM-NRC-KI Page 5 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS

The plant is tripped from 100% power. 300 gpm LOCA in progress. Loss of Offsite power is in progress. LOCA EOP is being implemented. RDACS indicates an off site release in progress. Data indicates I-131 concentration of 5.0 E-04 ci/cc in area of work in Upper SouthPiping Penetration room. Whole body dose rates in area of work are 1Rem/hr. General Emergency has just been declared. Joe Mechanic has completed 1903.035C form, ANO Medical Questionnaire-IodineSensitivity. RP estimates that it will take approximately 15 minutes to complete emergency actionsand stop the release and all RP required controls/authorizations are complete. Air Purifying Respirator with Iodine Canister having a protection factor of 1.0 will beused in place of a SCBA due to piping interference. EOF, OSC and TSC have NOT been staffed.INITIATING CUE:Determine if KI, Potassium Iodide should be issued and complete necessary paperwork,using OP 1903.035.

ANO-2-JPM-NRC-KI Page 6 of 6ADMINISTRATIVE JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS

The plant is tripped from 100% power. 300 gpm LOCA in progress. Loss of Offsite power is in progress. LOCA EOP is being implemented. RDACS indicates an off site release in progress. Data indicates I-131 concentration of 5.0 E-04 ci/cc in area of work in Upper SouthPiping Penetration room. Whole body dose rates in area of work are 1Rem/hr. General Emergency has just been declared. Joe Mechanic has completed 1903.035C form, ANO Medical Questionnaire-IodineSensitivity. RP estimates that it will take approximately 15 minutes to complete emergency actionsand stop the release and all RP required controls/authorizations are complete. Air Purifying Respirator with Iodine Canister having a protection factor of 1.0 will beused in place of a SCBA due to piping interference. EOF, OSC and TSC have NOT been staffed.INITIATING CUE:Determine if KI, Potassium Iodide should be issued and complete necessary paperwork,using OP 1903.035.

JOB PERFORMANCE MEASUREJPM-#-ANO-2-JPM-SRO- PAR3PAGE 1 of 5 UNIT: 2 REV#: 003 DATE:SYSTEM/DUTY AREA: Emergency PlanTASK: Issue Protective Action Recommendation to Offsite Authorities (Time Critical JPM)JTA#: ANO-SRO-EPLAN-EMERG-301KA VALUE RO:

2.4SRO: 4.4KA

REFERENCE:

2.4.44APPROVED FOR ADMINISTRATION TO: RO:SRO: XTASK LOCATION:

INSIDE CR:OUTSIDE CR:BOTH: XSUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR: PerformLAB:POSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:LAB:TESTING METHOD: SIMULATE

PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES: 5 Minutes - Read initial Conditions15 Minutes - PAR DeterminationREFERENCE(S): OP-1903.011EXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED INTHIS JPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED: DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

JOB PERFORMANCE MEASUREJPM-#-ANO-2-JPM-SRO- PAR3PAGE 2 of 5THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with theexaminee.JPM INITIAL TASK CONDITIONS:(Time Critical JPM)Unit 2 has experienced a LOCA.A General Emergency has been declaredand an Alert was previously declared.Unit 2 had been at full power for 215 days.Containment Building Pressure is 28 psia.Containment Radiation Monitors 2RY-8925-1 and 2RY-8925-2 both read 1092 R/hr.The reactor has been subcritical for 30 minutes.Off site dose estimates are projected to be 1200 mRem TEDE and 6000 mRem Child Thyroid.RDACS projects EPA Protective Action Guidelines will be exceeded in zones G and H.Wind direction is from 190.TASK STANDARD: (Time Critical 5 minutes for reading conditions 15 minutes for determining protective actionrecommendations)A PAR 1 was declared.A PAR 2 was declared.Recommend evacuating Zones G H K M N O P R U.Recommend zones I J L Q S T to go indoors and listen to the emergency broadcast for this event or remainder of the 10mile EPZ to go indoors and listen to the Emergency Broadcasts for this event.TASK PERFORMANCE AIDS: 1903.011; Attachment 6 JOB PERFORMANCE MEASUREJPM-#-ANO-2-JPM-SRO- PAR3PAGE 3 of 5INITIATING CUE:The Shift Manager directs 1.Determine the appropriate PAR for the given conditions.

2.Determine the zones to be recommended for evacuation/sheltering to the State Health Department for the givenconditions.

3.Determine the zones to be recommended to go indoors to the State Health Department for the given conditions.START TIME:PERFORMANCE CHECKLIST STANDARDS(Circle One)(C)1.(flowchart)Determine the correct PAR for thegiven conditionsUsing 1903.011 Attachments 6,PAR 1 and 2 were determined. N/A SAT UNSAT (C)2.(PAR1Table)Determine the zones that shouldbe recommended for evacuation tothe State Health Department.Using 1903.011 Attachment 6Recommend evacuating Zones G,H, K, M, N, O, P, R, U. N/A SAT UNSAT (C)3.(PAR1Table)Determine the zones that shouldgo indoors the State healthDepartment.POSITIVE CUE:NoneRecommend zones I, J, L, Q, S, Tgo indoors to go indoors and listento the emergency broadcasts for thisevent.ORrecommends remainder of the 10mile EPZ to go indoors and listento the Emergency Broadcasts N/A SAT UNSAT (C)4.JPM complete in 15 minutes.JPM complete in 15 minutes with 5minutes to read conditions.N/A SAT UNSAT ENDSTOP TIME:

JOB PERFORMANCE MEASUREJPM-#-ANO-2-JPM-SRO- PAR3PAGE 4 of 5Examiner's CopyThis is a time critical JPMInitial Conditions:Unit 2 has experienced a LOCA.A General Emergency has been declared and an Alert was previously declared.Unit 2 had been at full power for 215 days.Containment Building Pressure is 28 psia.Containment Radiation Monitors 2RY-8925-1 and 2RY-8925-2 both read 1092 R/hr.The reactor has been subcritical for 30 minutes.Off Site Dose estimates are projected to be 1200 mRem TEDE and 6000 mRem ChildThyroid.RDACS projects EPA Protective Action Guidelines will be exceeded in zones G, and H.Wind direction is from 190.INITIATING CUE:The Shift Manager directs:

1.Determine the appropriate PAR for the given conditions.

2.Determine the zones to be recommended for evacuation/sheltering to the State HealthDepartment for the given conditions.

3.Determine the zones to be recommended to go indoors to the State Health Department for thegiven conditions.Write Answer below:1) PAR(s) declaredA PAR 1 was declared.A PAR 2 was declared.2. Zones to be evacuatedor sheltered (specify)Recommend evacuating Zones G H K M N O P R U.3) Zones to go indoorsRecommend zones I J L Q S T to go indoors and listen to theemergency broadcast for this event or remainder of the 10 mile EPZ togo indoors and listen to the Emergency Broadcasts for this event.

JOB PERFORMANCE MEASUREJPM-#-ANO-2-JPM-SRO- PAR3PAGE 5 of 5Examinee's CopyThis is a time critical JPMInitial Conditions:Unit 2 has experienced a LOCA.A General Emergency has been declared and an Alert was previously declared.Unit 2 had been at full power for 215 days.Containment Building Pressure is 28 psia.Containment Radiation Monitors 2RY-8925-1 and 2RY-8925-2 both read 1092 R/hr.The reactor has been subcritical for 30 minutes.Off site dose estimates are projected to be 1200 mRem TEDE and 6000 mRem ChildThyroid.RDACS projects EPA Protective Action Guidelines will be exceeded in zones G, and H.Wind direction is from 190.INITIATING CUE:The Shift Manager directs:

1.Determine the appropriate PAR for the given conditions.

2.Determine the zones to be recommended for evacuation/sheltering to the State HealthDepartment for the given conditions.

3.Determine the zones to be recommended to go indoors to the State Health Department for thegiven conditions.Write Answer below:1. PAR(s) declared2. Zones to be evacuatedor sheltered (specify)3. Zones to go indoors

ANO-2-JPM-NRC-EOP01PAGE 1 OF 6JOB PERFORMANCE MEASUREUNIT: 2REV #: 09DATE:SYSTEM/DUTY AREA:Abnormal/Emergency OperationsTASK:Secure Containment SprayJTA#:ANO2-RO-EOPAOP-EMERG-13KA VALUERO:3.2SRO:3.7KA

REFERENCE:

026 A2.03APPROVED FOR ADMINISTRATION TO:RO: X SRO: XTASK LOCATION:INSIDE CR: XOUTSIDE CR:BOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR: PerformLAB:POSITION EVALUATED:RO:SRO:ACTUAL TESTING ENVIRONMENT:SIMULATOR:PLANT SITE:LAB:TESTING METHOD:SIMULATE: PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:15 MinutesREFERENCE(S):OP 2203.012D 2K-04 ACAEXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:StartTime StopTimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-EOP01PAGE 2 OF 6JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment6 with the examinee.JPM INITIAL TASK CONDITIONS: Containment spray actuation signal has actuated inadvertently and2K04 D-1, CSAS ACT, is in Alarm. I&C has corrected the problem. No testing is currently in progress.TASK STANDARD: CSAS is reset and CSAS actuated components are secured.TASK PERFORMANCE AIDS: EOP 2203.012D Annunciator 2K04 D1, CSAS ACTSIMULATOR SETUP:Inadvertent containment spray actuated. Containment Temperature. < 140 ° F,Pressure < 22.5 psia.

ANO-2-JPM-NRC-EOP01PAGE 3 OF 6JOB PERFORMANCE MEASUREINITIATING CUE:The CRS directs, "Reset CSAS and secure Containment Spray using ACA 2203.012D for annunciator 2D1,CSAS ACT.START TIME:PERFORMANCE CHECKLISTSTANDARDS(Circle One) 1.Step2.1Verify CSAS NOT valid.Determined that Containmentpressure less than 22.5 PSIA(PMS, SPDS or control boardindication). N/A SAT UNSATEXAMINERS NOTE: There is only one channel available on the simulator. Resetting 'B' trip path will reset all the other channelsalso.2.Step2.3Place Spray Pumps in PTL.Examiner's CUE:CRS acknowledges TS entryinto 3.0.3.On panels' 2C16/17, placedhandswitches for ContainmentSpray Pumps (2P35A and2P35B) in Pull To Lock (PTL).Observed green lights ONabove handswitches.Enter TS 3.0.3. N/A SAT UNSATEXAMINERS NOTE:There is only one channel available on the simulator. Resetting 2C23B actuation path will reset allthe other channels also.(C)3.Step2.6.12.6.22.6.32.6.4Reset CSAS on 2C23.Examiner's Note:Give examinee Key #15 whenasked.On panel 2C23B, obtained keyand placed it in trip path to be reset.Placed trip path key switch to UNLK.Depressed CSAS pushbutton fortrip path.Verified Trip Path lights reset(on 2C03) (Not a critical item)Placed trip path key switch to LK. N/A SAT UNSAT ANO-2-JPM-NRC-EOP01PAGE 4 OF 6JOB PERFORMANCE MEASUREPERFORMANCE CHECKLISTSTANDARDS(Circle One)EXAMINERS NOTE:There is only one channel available on the simulator. Resetting 2C40 actuation path will reset allthe other channels also.(C)3. Step2.6.62.6.7Reset CSAS on 2C40On 2C40, depressed CSASlockout reset pushbutton.On 2C40 verify reset lights areON.N/A SAT UNSAT (C)4.Step2.6.8Close Containment SprayHeader Isolation Valves.On panels' 2C16/17, placedhandswitches for ContainmentSpray Header Isolation valves(2CV-5612-1 and 2CV-5613-2)in CLOSE.Observed green lights ONabove handswitches. N/A SAT UNSAT (C)5.Step2.6.9Remove CNTMT Spraypumps from PTL:On panels' 2C16/17, removedhandswitches for ContainmentSpray Pumps (2P35A and2P35B) from PTL and placed innormal after stop.Observed green lights ONabove handswitches. N/A SAT UNSAT 6.Step2.6.10Exit Tech Spec 3.0.3.EXAMINER's CUE: ExitingTech Spec 3.0.3 has beenentered into the station log.Notify CRS to exit tech spec3.0.3 when both spray pumpsare taken out of PTL. N/A SAT UNSAT ENDSTOP TIME:

ANO-2-JPM-NRC-EOP01PAGE 5 OF 6JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS:Containment spray actuation signal has actuated inadvertently.2K04 D-1, CSAS ACT, is in alarm.I&C has corrected the problem.No Testing is currently in progress.INITIATING CUE:The CRS directs, "Reset CSAS and secure Containment Spray using ACA 2203.012D forannunciator D1, CSAS ACT.

ANO-2-JPM-NRC-EOP01PAGE 6 OF 6JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS:Containment spray actuation signal has actuated inadvertently.2K04 D-1, CSAS ACT, is in alarm.I&C has corrected the problem.No Testing is currently in progress.INITIATING CUE:The CRS directs, "Reset CSAS and secure Containment Spray using ACA 2203.012D forannunciator D1, CSAS ACT.

ANO-2-JPM-NRC-RCP04PAGE 1 OF 5JOB PERFORMANCE MEASUREUNIT: 2 REV#: 0DATE:SYSTEM/DUTY AREA:Reactor Coolant PumpTASK:Perform a normal RCP shutdown. (Alternate Path)JTA#: ANO-2-RO-RCP-NORM-3KA VALUERO:3.3SRO:3.1KA

REFERENCE:

003 A2.02APPROVED FOR ADMINISTRATION TO: RO:

XSRO: XTASK LOCATION:INSIDE CR:

XOUTSIDE CR:BOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformLAB:POSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:LAB:TESTING METHOD: SIMULATE:

PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:8 MinutesREFERENCE(S):OP 2103.006 Reactor Coolant Pump OperationsEXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:StartTime StopTimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-RCP04PAGE 2 OF 5JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023Attachment 6 with the examinee.JPM INITIAL TASK CONDITIONS:The unit is in Mode 3.TASK STANDARD:All RCP's secured due to 'A' RCP reverse rotation alarm.TASK PERFORMANCE AIDS:OP 2103.006 Section 8.0, OP-2203.012K for 2K11-C2 SIMULATOR SETUP:Mode 3 all RCP running.Insert Malfunction RCP2P32AREV the reverse rotation alarm will annunciate when the RCP isstopped.

ANO-2-JPM-NRC-RCP04PAGE 3 OF 5JOB PERFORMANCE MEASUREINITIATING CUE:The CRS directs, "Shut down RCP "A" using OP 2103.006 Section 8.0."Start Time:PERFORMANCE CHECKLIST STANDARDS(Circle One)(C)1.(Step 8.1)Start RCP "A" bearing oil lift pump (2P63A).On panel 2C04, placed 2HS-6084for 2P63A to START.Observed red light on; green lightOFF above 2HS-6084. N/A SAT UNSAT (C)2.(Step 8.2)Stop reactor coolant pump(2P32A).On panel 2C04, placed 2HS-4620for 2P32A to STOP.Observed green light ON; red lightOFF above 2HS-4620. N/A SAT UNSAT 3Acknowledges 2K11-C2 'A' RCPreverse rotation alarmOn panel 2K11 recognizes 'A' RCPreverse rotation alarm N/A SAT UNSAT (C)4.(Step2.2 of ACA)IF RCP 2P-32A NOT operating,THEN trip all RCPs.On panel 2C04, placed thehandswitches for the followingRCP's in STOP:

2P-32B 2P-32C 2P-32DAll RCPs must be stopped within3 minutes of receiving reverserotation alarm. N/A SAT UNSAT ENDStop Time:

ANO-2-JPM-NRC-RCP04PAGE 4 OF 5JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS:The unit is in Mode 3INITIATING CUE:The SM/CRS directs, "Shut down RCP "A" using OP 2103.006 Section 8.0."

ANO-2-JPM-NRC-RCP04PAGE 5 OF 5JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS:The unit is in Mode 3INITIATING CUE:The SM/CRS directs, "Shut down RCP "A" using OP 2103.006 Section 8.0."

ANO-2-JPM-NRC-SIT01PAGE 1 OF 7JOB PERFORMANCE MEASUREUNIT: 2 REV#: 010DATE:SYSTEM/DUTY AREA:Safety Injection SystemTASK: Perform a high pressure fill of a SIT (SIT "A") (Alternate Success Path)JTA#: ANO2-RO-ECCS-NORM-2KA VALUERO:3.3SRO:3.7KA

REFERENCE:

006 A2.03APPROVED FOR ADMINISTRATION TO: RO:

XSRO: XTASK LOCATION:INSIDE CR:

XOUTSIDE CR:BOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformLAB:POSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:LAB:TESTING METHOD: SIMULATE:

PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:

12 MinutesREFERENCE(S): OP-2104.001 Safety Injection Tank operationsEXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:StartTime StopTimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-SIT01PAGE 2 OF 7JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023Attachment 6 with the examinee.JPM INITIAL TASK CONDITIONS:HPSI pump (2P89A) is running on minimum recirculationTASK STANDARD:Safety Injection Tank (2T2A) level has been increased ~0.2% and fill is secured prior to2T-2A pressure exceeding 624 psig (Hi Hi pressure) or level exceeding 89.5% (Hi Hi level)TASK PERFORMANCE AIDS:OP 2104.001 Section 8.0 SIMULATOR SETUP:SIT 'A' level low enough to accept a 0.2% water addition and Safety Injection Tank (2T2A) pressure is<608 psig.Setup overrides to deenergize the red and green lights for 2CV 5015-1 when the handswitch isis taken to the open position and have the valve open 1%.HPSI pump (2P89A) is running on minimum recirculation. RCS PRESSURE > 1500psia.Set trigger T4= 'of4r0151' (triggered when 2HS5015-1 red light is energized).T4 - CV50151 = 0.1; fail HPSI injection MOV partially open.T4 - DO_HS_5015_G = OFF; HPSI injection MOV green light off.T4 - DO_HS_5015_R = OFF; HPSI injection MOV red light off.

ANO-2-JPM-NRC-SIT01PAGE 3 OF 7JOB PERFORMANCE MEASUREINITIATING CUE:The CRS directs, "Raise Safety Injection Tank (2T2A) level 0.2% using OP 2104.001, beginning with step8.3."START TIME:PERFORMANCE CHECKLISTSTANDARDS(Circle One) 1.Step8.3Monitor SIT level andpressure during fill.While filling SIT A, monitoredlevel to ensure level maintained< 87.9%.While filling SIT A, monitoredSIT pressure closely to ensurepressure maintained < 624 psig. N/A SAT UNSAT (C)2.Step8.4.1Open SIT (2T2A) DrainValve (2SV-5001-1).On panel 2C17, placedhandswitch for 2SV-5001-1 to OPEN.Observed red light ON abovehandswitch. N/A SAT UNSAT (C)3.Step8.4.1Open SIT (2T2A) CheckValve Bypass (2SV-5004).On panel 2C33, placedhandswitch for 2SV-5004 to OPEN.Observed red light ON abovehandswitch. N/A SAT UNSAT (C)4.Step8.4.2Throttle open HPSI Header 1Injection to RCP A Discharge(2CV-5015-1).On panel 2C17, throttled2CV-5015-1 OPEN by placinghandswitch to OPENmomentarily as required toestablish an SIT fill rate.Observed red and green lightsON above handswitch.Observed SIT (2T2A) controlboard level instrument(s): 2LIS-5008 (2C17) 2LI-5010 (2C17) 2LIS-5009 (2C16)

ORObserved SIT (2T2A) level onPMS, or SPDS computerpoint/trend display. N/A SAT UNSATExaminers note:The following step is the Alternate path portion of this JPM ANO-2-JPM-NRC-SIT01PAGE 4 OF 7JOB PERFORMANCE MEASUREPERFORMANCE CHECKLISTSTANDARDS(Circle One)(C)5.Step8.4.3.AAttempts to close HPSIHeader 1 Injection to RCP ADischarge valve.On panel 2C17, placedhandswitch for 2CV-5015-1 toCLOSE.Recognized that 2CV-5015-1would NOT close and both redand green lights aredeenergized. N/A SAT UNSAT (C)6.Step8.4.3.BStep8.4.3.CStop the level increase in2T2A SIT.On panel 2C17, placedhandswitch for A HPSI pump(2P-89A) in stopObserved 2P89A stopped.

OROn panel 2C17 placedhandswitch for SIT A DrainValve (2SV-5001-1) toCLOSED.Observed green light ON abovehandswitch.

OROn panel 2C33, placedhandswitch for SIT A CheckValve Bypass (2SV-5004) toCLOSED.Observed green light ON abovehandswitch. N/A SAT UNSAT 7.Inform CRS of failure of2CV-5015-1 to close.Examiner's Cue:Acknowledgecommunication as CRS.Direct Examinee to securefrom filling A SIT.Informed CRS that 2CV-5015-1failed to close. N/A SAT UNSAT 8.Step8.4.3.BClose SIT (2T2A) DrainValve.(if not closed previously.)On panel 2C17, placedhandswitch for SIT A DrainValve (2SV-5001-1) to CLOSE.Observed green light ON abovehandswitch. N/A SAT UNSAT ANO-2-JPM-NRC-SIT01PAGE 5 OF 7JOB PERFORMANCE MEASUREPERFORMANCE CHECKLISTSTANDARDS(Circle One) 9.Step8.4.3.CClose SIT (2T2A) CheckValve Bypass.(if not closed previously.)On panel 2C33, placedhandswitch for SIT A CheckValve Bypass (2SV-5004) toCLOSE.Observed green light ON abovehandswitch. N/A SAT UNSAT (C)10.On panel 2K07, Alarms C3,SIT Press Hi Hi or C4 LevelHi Hi NOT received.2T2A SIT High High Pressurealarm NOT received (SITpressure > 624 psig) or HighHigh level alarm NOT received(87.5%). N/A SAT UNSAT ENDSTOP TIME:

ANO-2-JPM-NRC-SIT01PAGE 6 OF 7JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS:HPSI pump (2P89A) is running on minimum recirculation.INITIATING CUE:The CRS directs, "Raise Safety Injection Tank (2T2A) level 0.2% using OP 2104.001,beginning with step 8.3."

ANO-2-JPM-NRC-SIT01PAGE 7 OF 7JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS:HPSI pump (2P89A) is running on minimum recirculation.INITIATING CUE:The CRS directs, "Raise Safety Injection Tank (2T2A) level 0.2% using OP 2104.001,beginning with step 8.3."

ANO-2-JPM-NRC-PZR01PAGE 1 OF 5JOB PERFORMANCE MEASUREUNIT: 2REV #: 001 DATE:SYSTEM/DUTY AREA:Pressurizer Pressure control Operations TASK:Equalize RCS and Pressurizer Boron JTA#:ANO2-RO-PZR-NORM-3KA VALUERO:3.7SRO:3.5KA

REFERENCE:

010 A4.01APPROVED FOR ADMINISTRATION TO:RO: XSRO: XTASK LOCATION:INSIDE CR:

XOUTSIDE CR:BOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:

SIMULATOR:Perform LAB:POSITION EVALUATED:RO:SRO: ACTUAL TESTING ENVIRONMENT:

SIMULATOR:PLANT SITE:

LAB:TESTING METHOD:

SIMULATE: PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:10 MinutesREFERENCE(S):OP 2103.005 Pressurizer OperationsEXAMINEE'S NAME:

Badge#:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED: DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

ANO-2-JPM-NRC-PZR01PAGE 2 OF 5JOB PERFORMANCE MEASUREThe examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023Attachment 6 with the examinee.JPM INITIAL TASK CONDITIONS:Chemistry reports that RCS Boron is 750 PPM and the PZR Boron is 805 PPM.TASK STANDARD:Establish boron equalization with backup heaters on and one PZR spray valve in manual withRCS pressure 2200

+/- 10 psiaTASK PERFORMANCE AIDS:OP 2103.005 section 7.1 SIMULATOR SETUP:PZR pressure controller in automatic with setpoint at 2200 psia.

ANO-2-JPM-NRC-PZR01PAGE 3 OF 5JOB PERFORMANCE MEASUREINITIATING CUE:The CRS directs, "Commence equalizing RCS and PZR boron concentration using OP 2103.005 section 7.1,'A' RCP spray valve, 2CV-4651."Start Time:PERFORMANCE CHECKLIST STANDARDS(Circle One) 1.(Step7.1.1)Verify spray valve, 2CV-4651,isolation valves 2CV-4655 AND2CV-4656 are OPEN.On panel 2C04 verified red lightsON, green lights OFF for2CV-4655 and 2CV-4656. N/A SAT UNSAT (C)2.(Step7.1.2)Place 'A' RCP spray valveMAN/AUTO select switch(2HS-4651B) to MANUAL.On panel 2C04, rotated 2HS-4651Bin the CCW direction toMANUAL. N/A SAT UNSAT (C)3.(Step7.1.3)Energize all available BackupHeaters:Place 2HS-4643 to ONPlace 2HS-4644 to ONPlace 2HS-4645 to ONPlace 2HS-4646 to ONOn panel 2C04 placed thefollowing handswitches to ON:Place 2HS-4643 to ONPlace 2HS-4644 to ONPlace 2HS-4645 to ONPlace 2HS-4646 to ON ANDObserved the red light ON andgreen light OFF above each of theabove backup heater handswitches. N/A SAT UNSATEXAMINERS NOTE:The following action may take several attempts (cycling the spray valve open and then closed) until the proper valveposition is obtained. When the handswitch is taken to the closed direction, 2CV-4651 will go completely closed.Maintaining RCS pressure 2200

+/- 10 psia may also be accomplished by placing one backup heater to Auto.The Critical portion of step 4 below is to maintain RCS pressure 2200

+/- 10 psia and this can be accomplished byeither step 4 or 5.This JPM should be stopped by examiner when determined satisfactory or unsatisfactory.(C)4.(Step7.1.4)When PZR pressure beginsincreasing, Throttle open 'A'RCP spray valve (2CV-4651)enough to stabilize pressure 2200+/- 10 psiaOn panel 2C 04, placed handswitchfor 2CV-4651 to the open positionmomentarily and then watchedPZR pressure stabilize at 2200

+/- 10psia. N/A SAT UNSAT 5.(Step7.1.5)IF necessary to maintain pressure+/- 10 psia of setpoint,THEN place one Backup Heaterbank in AUTO

.On panel 2C 04, placed handswitchfor one backup heater to auto asnecessary to maintain RCS pressure 2200+/- 10 psia. N/A SAT UNSAT ENDStop Time:

ANO-2-JPM-NRC-PZR01PAGE 4 OF 5JOB PERFORMANCE MEASUREEXAMINER'S COPYINITIAL CONDITIONS:Chemistry reports that RCS Boron is 750 PPM and the PZR Boron is 805 PPM.INITIATING CUE:The CRS directs, "Commence equalizing RCS and PZR boron concentration using OP2103.005 section 7.1, 'A' RCP spray valve, 2CV-4651."

ANO-2-JPM-NRC-PZR01PAGE 5 OF 5JOB PERFORMANCE MEASUREEXAMINEE'S COPYINITIAL CONDITIONS:Chemistry reports that RCS Boron is 750 PPM and the PZR Boron is 805 PPM.INITIATING CUE:The CRS directs, "Commence equalizing RCS and PZR boron concentration using OP2103.005 section 7.1, 'A' RCP spray valve, 2CV-4651."

ANO-2-JPM-NRC-VCTMUPAGE 1 OF 7JOB PERFORMANCE MEASUREUNIT: 2 REV#: 010DATE:SYSTEM/DUTY AREA:Chemical and Volume Control SystemTASK:Perform Manual Makeup to the VCTJTA#:ANO2-RO-CHADD-NORM-111KA VALUERO:3.6SRO:3.7KA

REFERENCE:

004 A4.15APPROVED FOR ADMINISTRATION TO:RO: XSRO: XTASK LOCATION:INSIDE CR:

XOUTSIDE CR:BOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformLAB:POSITION EVALUATED:RO:SRO:ACTUAL TESTING ENVIRONMENT:SIMULATOR:PLANT SITE:LAB:TESTING METHOD:SIMULATE: PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:20 MinutesREFERENCE(S):OP 2104.003 Chemical AdditionEXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:StartTime StopTimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-VCTMUPAGE 2 OF 7JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment6 with the examinee.JPM INITIAL TASK CONDITIONS: Plant is operating at 100%.OP 2104.003 Attachment L is completed through step 2.1. Boron 2 PMS program has been completed.TASK STANDARD: Manual blended make-up to the VCT at the correct blend ratio has beenestablished.TASK PERFORMANCE AIDS: Copy of OP 2104.003 Attachment L and Plant Monitoring system print outof required boric acid and waterSIMULATOR SETUP:VCT level at 60%. 2CVC-68 is throttled open(0.65) and 2CVC-83 is closed ANO-2-JPM-NRC-VCTMUPAGE 3 OF 7JOB PERFORMANCE MEASUREINITIATING CUE:The SM/CRS directs, "Raise VCT level to 75% using OP 2104.003 Attachment L beginning with step 2.2."START TIME:PERFORMANCE CHECKLISTSTANDARDS(Circle One) 1.Step2.3Verify 2CVC 68 is open and2CVC83 is closed.Examiner Cue:WCO reports than 2CVC68 isOPEN and 2CVC83 isCLOSED.Contact WCO and directOPENING of 2CVC68 andCLOSING of 2CVC83. N/A SAT UNSATExaminer's note:The Boric Acid and DI water flow rates should be set up to be approximately 1 to 5 ratio with 1 partBoric Acid and 5 parts DI water.The actual blend ratio to maintain RCS boron concentration is 1 to 5.6 but the last 50 gallons ofaddition should be DI water to flush the makeup line and this will equate to a 1 to 5 ratio make up rate.2.Step2.4Set Boric Acid Makeup FlowController (2FIC-4926) todesired flow rate.On Panel 2C09, set Boric AcidMakeup Flow Controller(2FIC-4926) to desired flow rate.Flow rate adjusted to ~ 1 / 5blend ratio. N/A SAT UNSAT 3.Step2.4Place 2FIC-4926 in eitherMANUAL or AUTOMATICmode.On Panel 2C09, placed2FIC-4926 to either MANUAL orAUTOMATIC mode. N/A SAT UNSAT 4.Step2.5Set Reactor Makeup WaterFlow controller (2FIC-4927) todesired flow rate.On Panel 2C09, set ReactorMakeup Water Flow Controller(2FIC-4927) to desired flow rate.Flow rate adjusted to ~ 1 / 5blend ratio. N/A SAT UNSAT 5.Step2.5Place 2FIC-4927 in eitherMANUAL or AUTOMATICmode.On Panel 2C09, placed2FIC-4927 in either MANUAL orAUTOMATIC mode. N/A SAT UNSAT ANO-2-JPM-NRC-VCTMUPAGE 4 OF 7JOB PERFORMANCE MEASUREPERFORMANCE CHECKLISTSTANDARDS(Circle One) 6.Step2.6Reset Boric Acid Makeup FlowTotalizer (2FQI-4926) to zero.On Panel 2C09, on (2FQI-4926)depressed the reset pushbutton. (Function pushbutton F3)Observed 2FQI-4926 indicatingzero. N/A SAT UNSAT 7.Step2.6Reset Reactor Makeup WaterFlow Totalizer (2FQI-4927) tozero.On Panel 2C09, on (2FQI-4927)depressed the reset pushbutton. (Function pushbutton F3)Observed 2FQI-4927 indicatingzero. N/A SAT UNSAT (C)8.Step2.7Open VCT Makeup Isol Valve.On Panel 2C09, placedhandswitch for VCT Makeup IsolValve (2CV-4941-2) to OPEN.Observed red light ON, greenlight OFF above handswitch for2CV-4941-2. N/A SAT UNSAT 9.Step2.8Verify a Reactor MakeupPump running.On Panel 2C09, verifiedhandswitch for one ReactorMakeup Pump (either 2P109Aor 2P109B) in START.Observed red light ON andgreen light OFF abovehandswitch for selected pump. N/A SAT UNSAT (C)10.Step2.9Start one BAM pump.On Panel 2C09, placedhandswitch for one BAM Pump(either 2P39A or 2P39B) toSTART.Observed red light ON andgreen light OFF abovehandswitch for selected pump N/A SAT UNSAT 11.Step2.10Open the associated BAMpump recirc valve.On Panel 2C09, opened theBAM Pump recirc valveassociated with the running BAMpump (either 2CV-4903-2 or2CV-4915-2).Observed red light ON andgreen light OFF for valve opened. N/A SAT UNSAT ANO-2-JPM-NRC-VCTMUPAGE 5 OF 7JOB PERFORMANCE MEASUREPERFORMANCE CHECKLISTSTANDARDS(Circle One)(C)12.Step2.11Place Boric Acid Makeup ModeSelector switch (2HS-4928) toMANUAL.On Panel 2C09, placed 2HS-4928 to MANUAL. N/A SAT UNSAT (C)13.Step2.12Verify Boric Acid Makeup FlowControl Valve (2CV-4926)opens to maintain desired flowrate.On Panel 2C09, verified2CV-4926 opens to control flowat ~ 1 / 5 of water flow rate.Observed flow indicated on2FIC-4926.Critical step is the steady flowrate after adjustment of 1 to4.6 to 5.4 of the water flow rate N/A SAT UNSAT (C)14.Step2.13Verify Reactor Makeup WaterFlow Control Valve (2CV-4927)opens to maintain desired flowrate.On Panel 2C09, verified2CV-4927 opens to control flowat ~ 5 times acid flow rate.Observed flow indicated on2FIC-4927.Critical portion is the steadywater flow rate to 4.6 to 5.4times the acid flow rate. N/A SAT UNSATEXAMINER'S NOTE: JPM may be terminated when above step is complete.

END ANO-2-JPM-NRC-VCTMUPAGE 6 OF 7JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS:Plant is operating at 100%.OP 2104.003 Attachment L is completed through step 2.1. Boron2 program has been usedto determine the correct amounts of Boric acid and water.INITIATING CUE:The SM/CRS directs, "Raise VCT level to 75% using OP 2104.003 Attachment L beginningwith step 2.2 using 'A' Bamt."

ANO-2-JPM-NRC-VCTMUPAGE 7 OF 7JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS:Plant is operating at 100%.OP 2104.003 Attachment L is completed through step 2.1. Boron2 program has been usedto determine the correct amounts of Boric acid and water.INITIATING CUE:The SM/CRS directs, "Raise VCT level to 75% using OP 2104.003 Attachment L beginningwith step 2.2 using 'A' Bamt."

ANO-2-JPM-NRC-ELECXTPAGE 1 OF 7JOB PERFORMANCE MEASUREUNIT: 2REV #: 001 DATE:SYSTEM/DUTY AREA:A. C. Electrical Distribution TASK:Perform Synchronized Cross Connect of 480 VAC load-centers 2B1 and 2B2 (Alternate Path)

JTA#:ANO2-RO-480VAC-NORM-15KA VALUERO:3.3SRO:3.1KA

REFERENCE:

062 A4.01APPROVED FOR ADMINISTRATION TO:RO: XSRO: XTASK LOCATION:INSIDE CR:

XOUTSIDE CR:BOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:

SIMULATOR:Perform LAB:POSITION EVALUATED:RO:SRO: ACTUAL TESTING ENVIRONMENT:

SIMULATOR:PLANT SITE:

LAB:TESTING METHOD:

SIMULATE: PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:12 MinutesREFERENCE(S):OP 2107.001 Electrical System OperationEXAMINEE'S NAME:

Badge#:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED: DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-ELECXTPAGE 2 OF 7JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023Attachment 6 with the examinee.JPM INITIAL TASK CONDITIONS:Non-Vital 4160VAC busses energized. 2B1 and 2B2 are energized. Maintenance must be performedon 2B2 transformer.TASK STANDARD:Cross connect 480VAC non-vital busses 2B1 and 2B2 with 2B1 supplying and 2B2 supply breakersopen. Maintain 2B1 amperage less than 130 amps.TASK PERFORMANCE AIDS:OP 2107.001 Section 12.0.

SIMULATOR SETUP:Any power level or mode.All Non-Vital 4160VAC and 480VAC Busses energized.REMOTE malfunction 480CURR2B2 value = 15REMOTE malfunctions 480CURR2B1 (value = 25) and 480CURR2B2 (value = 35) are set fortrigger 2.Conditional triggerT2 should be set for the handswitch to 2A-202 Normal after open (IC4G02CS)

ANO-2-JPM-NRC-ELECXTPAGE 3 OF 7JOB PERFORMANCE MEASUREINITIATING CUE:The SM/CRS directs, "Cross Connect 2B1 and 2B2 and separate 2B2 from 2A2 using OP 2107.001section 12.0."START TIME:PERFORMANCE CHECKLISTSTANDARDS(Circle One)Examiner's note:If the initial plant conditions are in Mode 3, 4 or 5, then the first step is N/A.

1.(Step 12.1)Check that OperationsManager approval obtained.EXAMINER'S CUE:"The Operations Managerhas given permission toperform Cross Connect of2B1 and 2B2."Ask if Operations Manager hasgiven approval to cross connect2B1 and 2B2 at power. N/A SAT UNSAT (C)2.(Step 12.2)Determine combined load of2B1 an 2B2 is less than 130amps when cross connected.On Panel 2C10, summed thecurrent reading of 2B1 and 2B2.Observed that the summed loadis less than 130 amps. N/A SAT UNSATExaminer's Note Step 12.3 in procedure is not applicable for this JPM as both busses remainedenergized.(C)3.(Step 12.4)Synchroscope switch insertedin 2B1/2B2 cross-tie slot andplaced in ON.On Panel 2C10, PlacedSynchroscope switch into2B1/2B2 cross-tie slot androtated clockwise to the ONposition. N/A SAT UNSAT 4.(Step 12.5)Observed that theSynchroscope is at the 12o'clock position.On Panel 2C10, Observed thatthe Synchroscope is at the 12o'clock position with theSynchroscope switch in the ONposition. N/A SAT UNSAT ANO-2-JPM-NRC-ELECXTPAGE 4 OF 7JOB PERFORMANCE MEASUREPERFORMANCE CHECKLISTSTANDARDS(Circle One)(C)5.(Step 12.6)Close the 2B1/2B2 Cross Tiebreaker.On panel 2C10, rotate the CrossTie handswitch for 2B1/2B2clockwise.Observed that the Green lightturns OFF and the Red lightturns ON above the Cross Tiehandswitch. N/A SAT UNSAT (C)6.(Step12.7.1)Open normal supply breakeron 2B2, 480VAC bus.On Panel 2C10, rotate thenormal feeder supply breaker on2B2 counter clockwise to theopen position. (2B212)Observed that the RED lightwent OFF and the GREEN lightwent ON. N/A SAT UNSAT (C)7.(Step12.7.2)Open Transformer feederbreaker from 2A2 to 2B2.On Panel 2C10, rotate thetransformer feeder breaker on2A2 to 2B2 counter clockwise tothe open position. (2A202)Observed that the RED lightwent OFF and the GREEN lightwent ON. N/A SAT UNSATExaminers Note:The following it the Alternate path portion of this JPM ANO-2-JPM-NRC-ELECXTPAGE 5 OF 7JOB PERFORMANCE MEASUREPERFORMANCE CHECKLISTSTANDARDS(Circle One)(C)7.(Step 12.8)Verify that the amperageindicated on 2B1 is less than130 amps.EXAMINERS CUE:"AO has been directed tosecure non-essential loadson 2B1 and 2B2 to reduceloading on 2B1 and 2B2 toless than 130 amps."EXAMINERS NOTE:Direct operator in simulatorinstructor's station to reduceloading on 2B1 and 2B2 sothatloading is less than 130amps (use REMOTEmalfunctions 480CURR2B1and 480CURR2B2).Observed that the summed loadis greater than 130 amps.Direct the AO or inform CRS ofneed to reduce non-essentialloads on 2B1 and 2B2 so thatcombined loading is less than130 amps.ORUn-crosstie 2B1 and 2B2 usingthe appropriate section of2107.001.Either of the above must becompleted within 10 minutesof the crosstie of 2B-1 and 2B-

2. N/A SAT UNSAT 8.(Step 12.9)Turn sync switch to OFF.On Panel 2C10, turn sync switchcounter clockwise to the OFFposition. N/A SAT UNSATExaminer's Note:Step 12.10 in procedure is not applicable for this JPM as both busses remained energized and theloads removed to reduce amperage on 2B1 will remain deenergized.

9.(Step 12.11)Notified AO to monitor 2B1transformer during crossconnected operation andmaintain temperature less than 220°C.EXAMINER'S CUE:"AO has been notified tomonitor 2B1 transformer andnotify the control room iftemperature exceeds 220°Cduring cross connectedoperations."Notify AO to monitor 2B1transformer during crossconnected operation andmaintain temperature less than 220°C. N/A SAT UNSAT ENDSTOP TIME:

ANO-2-JPM-NRC-ELECXTPAGE 6 OF 7JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS:Non-Vital 4160VAC busses energized. 2B1 and 2B2 are energized. Maintenance must beperformed on 2B2 transformer.INITIATING CUE:The SM/CRS directs, "Cross Connect 2B1 and 2B2 and separate 2B2 from 2A2 using OP 2107.001 section 12.0."

ANO-2-JPM-NRC-ELECXTPAGE 7 OF 7JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS:Non-Vital 4160VAC busses energized. 2B1 and 2B2 are energized. Maintenance must beperformed on 2B2 transformer.INITIATING CUE:The SM/CRS directs, "Cross Connect 2B1 and 2B2 and separate 2B2 from 2A2 using OP 2107.001 section 12.0."

ANO-2-JPM-NRC-CPC02PAGE 1 OF 6JOB PERFORMANCE MEASUREUNIT: 2REV #: 3 DATE:SYSTEM/DUTY AREA:Core Protection Calculators/COLSS TASK:Determine DNBR/LPD limits with COLSS out of service JTA#:ANO2-RO-EOPAOP-OFFNORM-234KA VALUERO:3.9SRO:3.9KA

REFERENCE:

015 A3.03APPROVED FOR ADMINISTRATION TO:RO: XSRO: XTASK LOCATION:INSIDE CR:

XOUTSIDE CR:BOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:

SIMULATOR:Perform LAB:POSITION EVALUATED:RO:SRO: ACTUAL TESTING ENVIRONMENT:

SIMULATOR:PLANT SITE:

LAB:TESTING METHOD:

SIMULATE: PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:10 MinutesREFERENCE(S):OP-2203.043 Loss of COLSSEXAMINEE'S NAME:

Badge#:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start TimeStop TimeTotal TimeSIGNED: DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-CPC02PAGE 2 OF 6JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023Attachment 6 with the examinee.JPM INITIAL TASK CONDITIONS:The plant is at 100%. COLSS has been declared inoperable due to MUX 'C' and 'D' failures.TASK STANDARD:DNBR/LPD limits have been calculated to within limits established.TASK PERFORMANCE AIDS:OP-2203.043 ATT A SIMULATOR SETUP:Fail the COLSS program. Insert malfunction XSPCOLSSMXD ('D' MUX failure) andXSPCOLSSMXC ('C' MUX failure)

ANO-2-JPM-NRC-CPC02PAGE 3 OF 6JOB PERFORMANCE MEASUREINITIATING CUE: The CRS directs you to determine DNBR/LPD within limits by completing AOP2203.043, Loss of COLSS, ATT A.START TIME:PERFORMANCE CHECKLISTSTANDARDS(Circle One)NOTES:Steps may be performed in various orders. Examinee will1. obtain data2. derive average3. derive limitTo obtain readings on CPC "B" and "C" the CPC/CEAC selector button must be selected to CPC (backlit) 1.(Step1 A.)Obtain operable CPC channelvalues (PID 406)EXAMINER NOTE:Approximate 100% value for DNBRA-1.761B-1.730C-1.708D-1.737At operable CPC modules on2C03 obtained CPC channelvalues (PID 406) byMAIN MENU <ENTER>CHANNEL CHECK (3) <ENTER>

ORMAIN MENU <ENTER>STANDARD O.M. (1) <ENTER>POINT ID (P) <ENTER>

4 <ENTER0 <ENTER>6 <ENTER>ANDEntered the 406 values foroperable channels A-D on pg 1step 1.A. of ATT AN/A SAT UNSAT (C) 2.(Step 1 A)Determine DNBR AverageOn ATT A step 1.A. determinedDNBR Average by adding theoperable channel DNBR readingspreviously obtained and dividingby # operable channels.DNBR average calculated to be1.7 to 1.8N/A SAT UNSAT (C)3.(Step 1 B)Determine DNBR LimitOn ATT A step 1.B. determinedDNBR limit by subtracting 0.12from average obtained in step 1.A.DNBR limit calculated to be 1.55to 1.65N/A SAT UNSAT ANO-2-JPM-NRC-CPC02PAGE 4 OF 6JOB PERFORMANCE MEASUREPERFORMANCE CHECKLISTSTANDARDS(Circle One) 4.(Step 2 A)Obtain operable CPC channelvalues (PID 179)EXAMINER NOTE:Approximate 100% value for LPDA-14.69B-14.41C-14.37D-14.26At operable CPC modules on2C03 obtained CPC channelvalues (PID 179) byMAIN MENU <ENTER>CHANNEL CHECK (3) <ENTER>

ORMAIN MENU <ENTER>STANDARD O.M. (1) <ENTER>POINT ID (P) <ENTER>

1 <ENTER7 <ENTER>9 <ENTER>ANDEntered the 179 values foroperable channels A-D on page 1step 2.A. of ATT AN/A SAT UNSAT (C)5.(Step 2 A)Determine LPD averageOn ATT A step 2.A, determinedLPD Average by adding theoperable channel LPD readingspreviously obtained and dividingby # operable channels.LPD average calculated to be14.3 to 14.6N/A SAT UNSAT (C)6.(Step 2 B)Determine LPD limitOn ATT A step 2.B. determinedLPD limit by adding 0.16 toaverage obtained in step 2.A.LPD limit calculated to be 0.1 to0.2 greater than the average.N/A SAT UNSAT ENDSTOP TIME:

ANO-2-JPM-NRC-CPC02PAGE 5 OF 6JOB PERFORMANCE MEASUREEXAMINER'S COPYJPM INITIAL TASK CONDITIONS:The plant is at 100%. COLSS has been declared inoperable due to MUX 'C' and 'D'failures.INITIATING CUE:The CRS directs you to determine DNBR/LPD within limits by completing AOP 2203.043,Loss of COLSS, ATT A.

ANO-2-JPM-NRC-CPC02PAGE 6 OF 6JOB PERFORMANCE MEASUREEXAMINEE'S COPYJPM INITIAL TASK CONDITIONS:The plant is at 100%. COLSS has been declared inoperable due to MUX 'C' and 'D'failures.INITIATING CUE:The CRS directs you to determine DNBR/LPD within limits by completing AOP 2203.043,Loss of COLSS, ATT A.

ANO-2-JPM-NRC-CCW02PAGE 1 OF 5JOB PERFORMANCE MEASUREUNIT: 2 REV#: 011DATE:SYSTEM/DUTY AREA:Component Cooling Water SystemTASK:Shift Running CCW pumpsJTA#: ANO-2-RO-CCW-NORM-10KA VALUERO:3.3SRO:3.1KA

REFERENCE:

008 A4.01APPROVED FOR ADMINISTRATION TO: RO:

XSRO:TASK LOCATION:INSIDE CR:

XOUTSIDE CR:BOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SIMULATOR:PerformLAB:POSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:LAB:TESTING METHOD: SIMULATE:

PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:10 MinutesREFERENCE(S): OP-2104.028 Component Cooling Water System OperationsEXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:StartTime StopTimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-CCW02PAGE 2 OF 5JOB PERFORMANCE MEASURETHE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023Attachment 6 with the examinee.JPM INITIAL TASK CONDITIONS:2P-33B running in a normal configuration. Component Cooling water loops are cross tied.Maintenance requests that 2P-33A be started and ran in single pump operation for PMT after pumprebuild.TASK STANDARD:2P33A running supplying CCW and 2P33B & 2P-33C in PULL-TO-LOCK.TASK PERFORMANCE AIDS:OP 2104.028 Section 18.2.5 SIMULATOR SETUP:Any power level or mode.2P-33B CCW pump in service with CCW loops cross tied.

ANO-2-JPM-NRC-CCW02PAGE 3 OF 5JOB PERFORMANCE MEASUREINITIATING CUE:The CRS directs, "Start 2P-33A and secure 2P-33B for PMT run following maintenance using OP 2104.028Step 18.2.5."START TIME:PERFORMANCE CHECKLISTSTANDARDS(Circle One) 1.(Step 18.2.5 A& B)Contact AO to vent 2P-33A.Examiner CUE:AO reports casing ventedand 2CCW-1001 closed.Using telephone or radio,contacted AO and directed himto vent 2P-33A Casing, using2CCW-1001. N/A SAT UNSAT(C) 2.(Step 18.2.5 C)Verify 2P-33C handswitch(2HS-5234) in PTL.On panel 2C14, placed 2P-33Chandswitch in Pull-To-Lock. N/A SAT UNSAT(C) 3.(Step 18.2.5 D)Start 2P-33A.On panel 2C14, took 2P-33Ahandswitch to START andreleased handswitch.Observed red light ON abovehandswitch. N/A SAT UNSAT(C) 4.(Step 18.2.5 E)Place 2P-33B handswitch(2HS-5228) to PTL.On panel 2C14, placed 2P-33Bhandswitch in Pull-To-Lock.Observed 2K-12 PUMP 2P-33A/B/C LOCKED alarm. N/A SAT UNSAT 5.(Step 18.2.5 F)Observe normal flow anddischarge pressure.Examiner CUE:Operator reports dischargepressure 110 psig locally.On panel 2C14, observed CCWflow between 2000 to 3000 gpm.Directed operator to observedischarge pressure between 100to 120 psig locally. N/A SAT UNSAT ENDSTOP TIME:

ANO-2-JPM-NRC-CCW02PAGE 4 OF 5JOB PERFORMANCE MEASUREEXAMINER's COPYJPM INITIAL TASK CONDITIONS:2P-33B running in a normal configuration.Maintenance requests that 2P-33A be started and ran in single pump operation for PMTafter pump rebuild.INITIATING CUE:The CRS directs, "Start 2P-33A and secure 2P-33B for PMT run following maintenance using OP 2104.028 Step 18.2.5."

ANO-2-JPM-NRC-CCW02PAGE 5 OF 5JOB PERFORMANCE MEASUREEXAMINEE's COPYJPM INITIAL TASK CONDITIONS:2P-33B running in a normal configuration.Maintenance requests that 2P-33A be started and ran in single pump operation for PMTafter pump rebuild.INITIATING CUE:The CRS directs, "Start 2P-33A and secure 2P-33B for PMT run following maintenance using OP 2104.028 Step 18.2.5."

JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-AACLS REV 08PAGE 1 of 7SYSTEM/DUTY AREA:Diesel Generator System (Alternate Success Path)TASK:Start up the AAC diesel generator manually locally during a Loss of Offsite PowerJTA # :ANO2-AO-AACDG-OFFNORM-18KA VALUERO:4.0SRO:4.3KA

REFERENCE:

064 A4.01APPROVED FOR ADMINISTRATION TO: RO:

XSRO: XTASK LOCATION: INSIDE CR:OUTSIDE CR:

XBOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SimulateSIMULATOR:LAB:POSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANTSITE:LAB:TESTING METHOD: SIMULATE:

PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:20 minutesREFERENCE(S)OP 2104.037, Exhibit 1EXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:DATE:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start Time:

StopTime:Total Time:Signature indicates this JPM has been compared to its applicable procedure by a qualified individual(not the examinee) and is current with that revision.SIGNED:DATE:

JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-AACLS REV 08PAGE 2 of 7THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023Attachment 6 with the examinee.This is an alternate success path JPM.JPM INITIAL TASK CONDITIONS:The following conditions exist:The reactor has tripped due to a loss of off-site power.Both emergency diesel generators are tied to their respective buses.An attempt to start the AACDG from the Control Room to energize 4160v Non-vital bus 2A1 wasunsuccessful.TASK STANDARD:The AAC Diesel has been started and is at 4160 V and 900 rpm with the output breaker (2A-1001) closed.The 480V bus 2B16 has been powered from the AAC diesel generator.TASK PERFORMANCE AIDS:OP 2104.037 Exhibit 1 JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-AACLS REV 08PAGE 3 of 7INITIATING CUE:The CRS provides the following direction:Start the AAC Diesel Generator using OP 2104.037 Exhibit 1 and bring the unit up to rated speed and voltagecarrying house loads.START TIME:EXAMINER'S NOTE:Provide examinee with copy of 2104.037, Exhibit 1If asked about the conditions of the alarms, tell the examinee that the only alarm in is H-3, GENERATORCIRCUIT BREAKER OPEN.If asked if 125 VDC is available, tell them that the indications for bus availability are as seen (assumes noactual maintenance in progress)PERFORMANCE CHECKLISTSTANDARDS(Circle One)(C)1.(Step1.1)Place "Local/Remote" switch inLOCAL.POSITIVE CUE:"Local/Remote" switchindicates LOCAL.On panel 2C-440, placed the"Local/Remote" switch inLOCAL. N/A SAT UNSAT 2.(Step1.2)Start the AAC Diesel using thelocal start switch.EXAMINER'S NOTE:Provide the following cueafter ~ 35 seconds when thelocal start switch is taken toSTART.EXAMINER'S CUE:There has been NO changein AAC diesel generatorfrequency or noise level.On panel 2C-440 turned thelocal control switch CW to start. N/A SAT UNSATExaminer's NOTE:Go to the AAC diesel engine room.

3.(Step2.1)Open the pre-lube pumpsolenoid (2SV-7224) for >10seconds.EXAMINER'S CUE:Air noise is heard.On the south side of the engineat the generator end, rotated themanual operator of 2SV-7224CW to open for >10 seconds. N/A SAT UNSAT JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-AACLS REV 08PAGE 4 of 7 (C)4.(Step2.2)Open EITHER of the air startsolenoid valves: - 2SV-7222 OR - 2SV-7223EXAMINER'S CUE:Engine speed and noiselevel increases.On the south side of the engineat the generator end, rotated themanual operator of one of the airstart solenoid valves CW to open.Looked for an increase in enginenoise and/or discharge of oil andair from the air start motors. N/A SAT UNSAT 5.(Step2.3)Close the air start solenoidvalve that was opened.On the south side of the engineat the generator end, rotated themanual operator for the air startsolenoid valve CCW to close. N/A SAT UNSAT 6.(Step2.3)Close the pre-lube solenoid(2SV-7224).After > 10 seconds on the southside of the engine at thegenerator end, rotated themanual operator of 2SV-7224CCW to close. N/A SAT UNSAT 7.(Step 3)Verify the AAC DieselGenerator is at rated speedand voltage.EXAMINER'S CUE:Frequency indicates 60 Hzand voltage indicates 4160V.On panel 2C-440, observedgenerator frequency at 60 Hzand voltage at 4160V. N/A SAT UNSAT JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-AACLS REV 08PAGE 5 of 7EXAMINER'S NOTE:When the examinee inspects the condition of 2A-1001, provide the NEGATIVE CUE first to indicate thatthe breaker has NOT automatically closed. Once the action has been taken to close the breaker, providethe POSITIVE CUE.(C)8.(Step4.1)Verify the AAC GeneratorOutput Breaker (2A-1001) isCLOSEDEXAMINER'S CUE:The green breaker OPENlight is lit.ANDThe white breaker springcharging light is lit.EXAMINER'S CUE:The Red breaker CLOSEDlight is lit.Observed breaker positionindication on the door of 2A-1001.Rotated breaker local controlswitch for 2A-1001 to theCLOSE position. N/A SAT UNSATTRANSITION NOTE:Go to the upstairs area of the switchgear room.

9.(Step4.2)Verify the London Feed toMCC 2B161 breaker 2B16-A1is OPEN.EXAMINER'S CUE:Green OPEN light is lit on2B16-A1 and mechanicalposition indicator showinggreen openObserved the mechanicalposition indicator breaker for2B16-A1 to show green openand the green breaker positionindication light is lit. N/A SAT UNSAT 10.(Step4.3)Verify Load Center 2B16Supply from the AAC diesel(2B16-B1) is CLOSED.EXAMINER'S CUE:Red CLOSED light is lit on2B16-B1 and mechanicalposition indicator showingred closed.Observed the mechanicalposition indicator breaker for2B16-B1 to show red closed andthe red breaker positionindication light is lit. N/A SAT UNSAT ENDSTOP TIME:

JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-AACLS REV 08PAGE 6 of 7Examiner's CopyJPM INITIAL TASK CONDITIONSThe following conditions exist:The reactor has tripped due to a loss of off-site power.Both emergency diesel generators are tied to their respective buses.An attempt to start the AACDG from the Control Room to energize4160v Non-vital bus 2A1 was unsuccessful.INITIATING CUE:The CRS provides the following direction:Start the AAC Diesel Generator using OP 2104.037 Exhibit 1.Bring the unit up to rated speed and voltage carrying house loads.

JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-AACLS REV 08PAGE 7 of 7Examinee's CopyJPM INITIAL TASK CONDITIONSThe following conditions exist:The reactor has tripped due to a loss of off-site power.Both emergency diesel generators are tied to their respective buses.An attempt to start the AACDG from the Control Room to energize4160v Non-vital bus 2A1 was unsuccessful.INITIATING CUE:The CRS provides the following direction:Start the AAC Diesel Generator using OP 2104.037 Exhibit 1.Bring the unit up to rated speed and voltage carrying house loads.

JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-XFCEAREV 10PAGE 1 of 7SYSTEM/DUTY AREA:Control Element Drive Mechanism Control SystemTASK:Transfer a CEA to the hold busJTA # :ANO2-RO-CEDM-OFFNORM-12KA VALUERO:3.7SRO:3.9KA

REFERENCE:

001 A2.14APPROVED FOR ADMINISTRATION TO: RO:

XSRO: XTASK LOCATION: INSIDE CR:OUTSIDE CR:

XBOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SimulateSIMULATOR:LAB:POSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANTSITE: XLAB:TESTING METHOD: SIMULATE:

PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:20 minutesREFERENCE(S)OP 2105.009, Exhibit 1EXAMINEE'S NAME:Badge #:EVALUATOR'S NAME:DATE:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:Start Time:

StopTime:Total Time:Signature indicates this JPM has been compared to its applicable procedure by a qualified individual(not the examinee) and is current with that revision.SIGNED:DATE:

JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-XFCEAREV 10PAGE 2 of 7THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023Attachment 6 with the examinee.PM INITIAL TASK CONDITIONS:The following conditions exist:1. The Plant is at 100% power.2. 2K10-H1 "CEDMCS COIL VOLTAGE HI" is in alarm3. 2K20-H3 "CEDMCS TIMER FAILURE" is locked in alarmTASK STANDARD:CEA 47 held by Upper Gripper on the HOLD bus with CEDM power switch CKT BKR FOR CEA 47 OPENEDTASK PERFORMANCE AIDS:4. PowerPoint XFCEA Pictures.ppt located in "In Plant JPM" folder5. OP 2105.009 Exhibit 16. Stop watch for timing subgroup transfer within 30 seconds.

JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-XFCEAREV 10PAGE 3 of 7INITIATING CUE:The CRS provides the following direction:1. Place the affected CEA subgroup on the hold bus using 2105.009, Exhibit 1START TIME:PERFORMANCE CHECKLIST STANDARDS(Circle One)EXAMINERS NOTE:Alarm lights may be either "RED" or "GREEN". POSITIVE CUES must be supplied to provide expectedplant indications.(C)1.(Step 1)Check Timer Failure Alarm (TFA) lamps.EXAMINER'S CUE:Red light "ON" for CEA #47 ORCheck Card Status Monitor lightsto determine affectedsubgroup/CEA.EXAMINER'S CUE:Card status monitor light flashingfor CEA #47 subgroup.On CEDMCS Cabinet (2C72) BayA and Bay B supervisory panels,checked TFA lamps.Observed red light ON for CEA

1. 47.OROn CEDMCS Cabinets 2C71 and2C72, checked CEA Card StatusMonitor lights.Observed card status monitor lightfor CEA #47 subgroup flashing N/A SAT UNSAT 2.(Step 2.1)Locate the affected SubgroupNumber and SubgroupMaintenance SwitchEXAMINER'S CUE:Maintenance switch #12 on 2C72for CEA 047 is pointing down.On 2C71 identified the correctsubgroup number for CEA 47.On 2C72 located maintenanceswitch #12 for that subgroup. N/A SAT UNSATEXAMINERS NOTE:Do not allow examinee to open the cabinet door to 2C-71. Once they have located the correct door,show them the picture of the voltage readings which indicate ~60 VDC.

3.(Step 2.2)Check positive and negative HoldBus voltages >50 VDC.POSITIVE CUE:Voltage meters indicate ~60 VDCAT back of panel 2C-71, observedHold Bus Voltages (positive &negative) > 50 VDC on bus voltagemeters. N/A SAT UNSAT JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-XFCEAREV 10PAGE 4 of 7Examiner Note:When the CEA is transferred to the Upper Gripper start the timer for the 30 second critical time to complete thetransfer to the Hold Bus.Examiner Note:Do not allow examinee to open the Card Status Monitor door. When the examinee has located the correct door,show them the picture of the ACTM cards.

4.(Step 2.3)Open the Card Status MonitordoorEXAMINER'S CUE:LG ENGD and ABNM VOLTlights illuminatedOpened doorObserved the lower gripper lightand ABN VOLT light illuminated. N/A SAT UNSAT (C)5.(Step 2.4)Operate the MAN TRANSFERtoggle switch on the ACTM cardfor CEA 47 to transfer it to theUpper Gripper.EXAMINER'S CUE:UG ENGD light illuminates andLower Gripper lightextinguishes when the MANTRANS switch on the ACTMcard is operatedPushed up on the MANUALTRANSFER toggle switchObserved the Lower Gripper lightextinguishes and the Upper Gripperlight illuminates & ABN VOLTlight remains illuminated. N/A SAT UNSAT (C)6.(Step 2.5)Operate Subgroup Maint Switchto place CEA #47 on hold bus.EXAMINER'S CUE:Subgroup maintenance switch#12 is pointing up.On front of 2C72 Bay "B"Supervisory Panel, located andraised subgroup maintenanceswitch #12 to the ON positionwithin 30 seconds of completingthe previous step.Within 30 seconds after operationof the MANUAL TRANSFERswitch, operated subgroupmaintenance switch. N/A SAT UNSATEXAMINERS NOTE:Do not allow examinee to open the cabinet door to 2C-71. Once they have located the correct door,show them the picture of the voltage readings which indicate ~45 VDC.

6.(Step 2.6)Check positive and negative HoldBus voltages.EXAMINER'S CUE:Voltage meters indicate 44 VDCAT back of panel 2C-71, observedHold Bus Voltages (positive &negative) decreased 10 VDCfrom initial reading on bus voltagemeters. N/A SAT UNSAT JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-XFCEAREV 10PAGE 5 of 7 (C)7.(Step 2.7)Open the disconnect switch for CEA #47.EXAMINER'S CUE:Green light ON, red light OFF.At front of panel 2C71 located andpulled downward on CEA #47"Power Switch" disconnect.Observed green light ON, red light OFF. N/A SAT UNSAT ENDSTOP TIME:

JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-XFCEAREV 10PAGE 6 of 7EXAMINER'S COPYJPM INITIAL TASK CONDITIONS:The plant is at 100%.2K10-H1 "CEDMCS COIL VOLTAGE HI" is in alarm2K20-H3 "CEDMCS TIMER FAILURE" is locked in alarmINITIATING CUE:The CRS directs you to place the affected CEA subgroup on the hold bus using2105.009, Exhibit 1 JOB PERFORMANCE MEASUREJPM# ANO-2-JPM-NRC-XFCEAREV 10PAGE 7 of 7EXAMINEE'S COPYJPM INITIAL TASK CONDITIONS:The plant is at 100%.2K10-H1 "CEDMCS COIL VOLTAGE HI" is in alarm2K20-H3 "CEDMCS TIMER FAILURE" is locked in alarmINITIATING CUE:The CRS directs you to place the affected CEA subgroup on the hold bus using2105.009, Exhibit 1

20 40 0 60 80POSITIVE VOLTAGE 1 20 40 0 60 80D-C VOLTSD-C VOLTSOUTPUTNEGATIVE VOLTAGE 1OUTPUT 0 40 20 60 80 0 40 20 60 80 A B CF407F408F409POSITIVE VOLTAGE 1 OUTPUTNEGATIVE VOLTAGE 1 OUTPUTPOSITIVE OUTPUT ADJUSTNEGATIVE OUTPUT ADJUST CAUTION HIGH VOLTAGED-C VOLTSD-C VOLTS JOB PERFORMANCE MEASUREANO-2-JPM-NRC-69RELREV. 0PAGE 1 of 7UNIT: 2 REV#: 0DATE:SYSTEM/DUTY AREA:Liquid Radwaste and Boron Management SystemTASK:Perform a release of 2T-69A Boric Acid Condensate TankJTA#:ANO2-WCO-LRWBMS-NORM-2KA VALUERO:3.3SRO:3.1KA

REFERENCE:

068 A4.02APPROVED FOR ADMINISTRATION TO: RO:

XSRO: XTASK LOCATION:INSIDE CR:OUTSIDE CR:

XBOTH:SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):PLANT SITE:SimulateSIMULATOR:LAB:POSITION EVALUATED: RO:SRO:ACTUAL TESTING ENVIRONMENT: SIMULATOR:PLANT SITE:LAB:TESTING METHOD: SIMULATE:

PERFORM:APPROXIMATE COMPLETION TIME IN MINUTES:20 MinutesREFERENCE(S):OP-2104.014 LRW and BMS Operations Sup. 3EXAMINEE'S NAME:Badge#:EVALUATOR'S NAME:THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:SATISFACTORY:UNSATISFACTORY:PERFORMANCE CHECKLIST COMMENTS:StartTime StopTimeTotal TimeSIGNED:DATE:SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

JOB PERFORMANCE MEASUREANO-2-JPM-NRC-69RELREV. 0PAGE 2 of 7THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023Attachment 6 with the examinee.JPM INITIAL TASK CONDITIONS:1. 2T-69A Boric Acid Condensate Tank level is 90%.2. 2104.014 Sup. 1 Liquid Radwaste Release permit for 2T-69A has been submitted and completed.3. 2P-47A Boric Acid Condensate pump is running.4. 2RE-2330 radiation monitor is OPERABLE.5. Maximum flow rate from Pre-Release report based on number of Circ pumps running is 250 gpm.6. 2CV-2330A and 2CV-2330B were both tested in Supplement 1 of 2104.014.TASK STANDARD:A 2T-69A Boric Acid Condensate Tank release has been commenced using OP-2104.014 Sup. 3.TASK PERFORMANCE AIDS:OP-2104.014 Sup. 3 JOB PERFORMANCE MEASUREANO-2-JPM-NRC-69RELREV. 0PAGE 3 of 7INITIATING CUE:The SM/CRS directs, "Commence a 2T-69A Boric Acid Condensate Tank release using OP-2104.014 Sup. 3."START TIME:

_____________PERFORMANCE CHECKLIST STANDARDS(Circle One)TRANSITION NOTE:Proceed to the 335 elevation of the Aux Bldg by the WCO desk.

1.(Step 3.1)Check 2CV-2312 closed andmagnetic tag installed.EXAMINER'S CUE:Red light off, green light on.Red "CLOSED" magnetic tag isinstalled on 2HS-2312.Valve stem is fully down.Observed red "CLOSED" magnetic taginstalled on 2HS-2312.

AND EITHER:At 2C-112 panel, observed red light off,green light on.

ORLocally, observed valve stem fully down.N/A SAT UNSAT 2.(Step 3.1)Check 2CV-2318 closed andmagnetic tag installed.EXAMINER'S CUE:Red light off, green light on.Red "CLOSED" magnetic tag isinstalled on 2HS-2318.Valve stem is fully down.Observed red "CLOSED" magnetic taginstalled on 2HS-2318.

AND EITHER:At 2C-112 panel, observed red light off,green light on.

ORLocally, observed valve stem fully down.N/A SAT UNSATEXAMINERS NOTE:Step 3.2 is not applicable due to using 2P-47A and Step 4 is not applicable due to releasing 2T-69A (C)3.(Step 5)Verify 2P-47A pump is running.EXAMINER'S CUE:Red light on, green light off.

OR2PI-2317 indicates 65 psig.Either:At 2C-112 panel, observed red light on,green light off.

ORAt 2C-112 panel, observed pressure on 2PI-2317.N/A SAT UNSAT 4.(Step 6.1)Remove magnetic tag from 2CV-2318.EXAMINER'S CUE:Red "CLOSED" magnetic tag isremoved from 2HS-2318.Removed red "CLOSED" magnetic tagfrom 2HS-2318.N/A SAT UNSAT JOB PERFORMANCE MEASUREANO-2-JPM-NRC-69RELREV. 0PAGE 4 of 7PERFORMANCE CHECKLIST STANDARDS(Circle One)(C)5.(Step 6.2)Open 2P-47A discharge valve 2CV-2318.EXAMINER'S CUE:Red light on, green light off.At 2C-112 panel, placed 2HS-2318 toOPEN.N/A SAT UNSAT 6.(Step 6.3)Place magnetic tag near 2CV-2318.EXAMINER'S CUE:Red "OPEN-DUMP" magnetic tagis near 2HS-2318.Placed red "OPEN-DUMP" magnetic tagnear 2HS-2318.N/A SAT UNSAT (C)7.(Step 7.1)Verify tank release valves open.EXAMINER'S CUE:2HS-2330 is position 1 or 3. Redlight on, green light off for 2CV-2330A and 2CV-2330B.At 2C-112 panel, verified 2HS-2330 inposition "1" or "3" and Red light isilluminated for 2CV-2330A and 2CV-2330B.N/A SAT UNSAT 8.(Step 8)Check no release flow exists.EXAMINER'S CUE:Control room states, "2FR/RR-2331 recorder indicates 0 gpm."Contacted the Control room by radio orphone to verify no flow exists on 2FR/RR-2331.N/A SAT UNSATTRANSITION NOTE:Proceed to the 326 elevation area by the Squeeze valve.(C)9.(Step 9)Open 2BM-35.EXAMINER'S CUE:Valve stem is fully extended.Opened valve by turning handwheel CCWuntil resistance felt.N/A SAT UNSAT (C)10.(Step 10)Throttle 2BM-80A to one turn open.EXAMINER'S CUE:Valve is one turn open.Flow noise is heard.Closed valve by turning handwheel CWuntil resistance felt.Reopened valve ~ 1 turn.N/A SAT UNSAT JOB PERFORMANCE MEASUREANO-2-JPM-NRC-69RELREV. 0PAGE 5 of 7PERFORMANCE CHECKLIST STANDARDS(Circle One) 11.(Step 10)Verify flow less than or equal to 75 gpm.EXAMINER'S CUE:Flow is 60 gpm.Contacted Control room by radio or phoneto verify flow less than or equal to 75 gpm.N/A SAT UNSAT ENDSTOP TIME:

______________

JOB PERFORMANCE MEASUREANO-2-JPM-NRC-69RELREV. 0PAGE 6 of 7EXAMINER'S COPYJPM INITIAL TASK CONDITIONS:2T-69A Boric Acid Condensate Tank level is 90%.2104.014 Sup. 1 Liquid Radwaste Release permit for 2T-69A has been submitted and completed.2P-47A Boric Acid Condensate pump is running.2RE-2330 radiation monitor is OPERABLE.Maximum flow rate from Pre-Release report based on number of Circ pumps running is 250 gpm.2CV-2330A and 2CV-2330B were both tested in Supplement 1 of 2104.014.INITIATING CUE:The SM/CRS directs, "Commence a 2T-69A Boric Acid Condensate Tank release using OP-2104.014 Sup. 3."

JOB PERFORMANCE MEASUREANO-2-JPM-NRC-69RELREV. 0PAGE 7 of 7EXAMINEE'S COPYJPM INITIAL TASK CONDITIONS:2T-69A Boric Acid Condensate Tank level is 90%.2104.014 Sup. 1 Liquid Radwaste Release permit for 2T-69A has been submitted and completed.2P-47A Boric Acid Condensate pump is running.2RE-2330 radiation monitor is OPERABLE.Maximum flow rate from Pre-Release report based on number of Circ pumps running is 250 gpm.2CV-2330A and 2CV-2330B were both tested in Supplement 1 of 2104.014.INITIATING CUE:The SM/CRS directs, "Commence a 2T-69A Boric Acid Condensate Tank release using OP-2104.014 Sup. 3."

Appendix D Scenario 1Form ES-D-1Revision 1Page 1 of 27Facility: ANO-2Scenario No.: 1 (New)Op-Test No.: 2009-1Examiners:Operators:Initial Conditions:100% MOL, All Engineered Safety Features systems are in standby. Gland Seal pressure control valve2PCV-0231 is jacked closed. Green Train Maintenance Week. The 'B' Charging pump seal water pumpis in hand and has been running for 30 min.Turnover:100%. 260 EFPD. EOOS indicates 'Minimal Risk'. 2PCV-0231 jacked closed, manually control sealsteam pressure. Green Train Maintenance Week. 'C' Charging pump will be removed from service forrepack. Place 'B' Charging pump in service and secure 'C' Charging pump. Steps 8.1.1 and 8.1.2 arecomplete.EventNo.Malf. No.EventType*EventDescription 1N (ATC)N (BOP)N (SRO)Place 'B' Charging pump in service and secure 'C'Charging pump.

2XSG2PT10411 I (BOP)I (SRO)'A' Steam generator safety channel pressure transmitterfails low. Tech Spec for SRO.

3 XCVLDNHXOUI (ATC)I (SRO)Letdown Temperature control valve input fails low.

4CVC2P36BFALC (ATC)C (SRO)'B' Charging pump supply breaker trips due to a motorfault.5RCSLOCATCB N (BOP)R (ATC)N (SRO)Shutdown required due to15 gpm Reactor Coolantsystem leak on 'B' cold leg. Tech Spec for SRO.

6MRGTRPLOCKOFAILSU3M (ALL)Main Turbine Generator trip causing a reactor trip and aStartup #3 transformer lockout causing naturalcirculation of the RCS.

7CV15042C (BOP)C (SRO)#2 Emergency Diesel Generator service water outletvalve fails to open. This will result in de-energizinggreen train vital 4160VAC(2A-4) and vital 480VAC (2B-6).8RCSLOCATCBM (ALL)Reactor Coolant system 'B' cold leg leakage ramps upto 225 gpm over 10 minutes.

9 HPISI10AC (BOP)C(SRO)2P-89A Safety injection pump shaft shear.* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajorTotal malfunctions. = 8, Malfunctions after EOP entry = 2, Abnormal events = 4, Major transient = 2,EOPs with substantive actions =1, EOP Contingencies = 0, Critical tasks = 2.

Appendix D Scenario 1Form ES-D-1Revision 1Page 2 of 27Scenario #1 Objectives 1)Evaluate individual ability to operate safety related equipment.

2)Evaluate individual response to a failure of a Steam Generator Safety Channel Pressuredetector.3)Evaluate individual response to a failure of a Letdown temperature controller.

4)Evaluate individual response to a failure of a Coolant Charging pump.

5)Evaluate individual response to a small Reactor Coolant system leak.

6)Evaluate individual ability to perform a reduction in plant power.

7)Evaluate individual ability to respond to Degraded Electrical power.

8)Evaluate individual ability to mitigate a LOCA.

9)Evaluate individual response to a failure of cooling water to an Emergency Diesel Generator.

10)Evaluate individual ability to monitor operation of Emergency Core Cooling Equipment.

SCENARIO #1 NARRATIVESimulator session begins with the plant at 100% power steady state Gland seal regulator,2PCV-0231 is jacked closed.When the crew has completed their control room walk down and brief, the ATC and BOP will shiftlead charging pumps. The candidate will start the 'B' Charging pump and secure 'C' Chargingpump using OP 2104.002 section 8.1.After the 'B' Charging pump is placed in service and 'C' Charging pump is secured or cued by leadexaminer, the 'A'Steam Generator pressure safety channelpressure instrument, 2PT-1041-1, will faillow. This will trip one of the four PPS trip channels for low SG pressure trip and MSIS. Alarms forMSIS pre-trip, RPS channel trip/pre-trip, and channel 'A' operator insert (2C03) trip and pre-triplights will be lit. The SRO will refer to the ACA 2203.012D and tech specs 3.3.1.1, 3.3.2.1, 3.3.3.5and 3.3.3.6 for guidance. The BOP will place Channel 'A' PPS in bypass for point 11, SG pressurelow, point 19, 'A' SG delta-P for EFAS 1, and point 20, 'B' SG delta-P for EFAS 2 formaintenance and trouble shooting. The crew will have one hour to place these points in bypassbefore exceeding the tech spec LCO.After the 'A' PPS channel is placed in bypass and cued by lead examiner, the Letdown heatexchanger temperature input will fail low. The ATC will report that LETDOWN HX 2E29OUTLET TEMP HI alarm is in and the letdown heat exchanger temperature is reading low on thehand indicating controller but the computer point and control board indication are reading higherthan normal. The SRO will direct the ATC to take manual control of the Letdown heat exchangertemperature control valve and manually control temperature. The SRO will also refer to the ACAfor letdown radiation monitor flow low 2K12 J1 RADMONITOR FLOW LO and restore letdownradiation monitor flow.After the ATC has taken manual control of the letdown temperature control valve, the 'B' CoolantCharging Pump (CCP) will trip. The SRO will enter AOP 2203.036, Loss of Charging. The SROwill direct the ATC to manually start a standby CCP. The SRO should refer to the TRM anddetermine no LCOs are applicable.

Appendix D Scenario 1Form ES-D-1Revision 1Page 3 of 27SCENARIO #1 NARRATIVE (continued)When a backup Charging pump has been started or at the lead examiner's cue, a 15 gpm RCS leakwill start. The SRO will enter the excess RCS leakage AOP, OP 2203.016. ATC and BOP willperform RCS Leak rate determinations. The SRO will enter Tech Spec 3.4.6.2. The SRO will directto ATC to maintain pressurizer level within 5% of set point by starting additional charging pumpsas needed. The SRO will also direct the ATC to isolate letdown to determine the leak location.After the crew has determined the leak is not in letdown, they will restore letdown and the crew willperform a plant shutdown.After the ATC has completed the required reactivity manipulation or cued by lead examiner, a MainTurbine Trip will occur and the crew will verify the reactor has tripped. When the reactor tripsStart up transformer #3 will lock out. The RCPs and Circulating Water pumps lose power whichwill cause natural circulation conditions in the RCS and require steaming to atmosphere. DuringSPTAs, the BOP will report that #2 EDG service water outlet valve is not open requiring the #2EDG to be secured locally.The Crew will implement Standard Post Trip Actions (SPTA), OP 2202.001. After the reactor tripsthe RCS leakrate will ramp to 225 gpm over 10 minutes.The SRO will diagnose a loss of coolant accident and enter EOP 2202.003, Loss of CoolantAccident (LOCA).The ATC will cool down the RCS using the atmospheric dump valves. The BOP will override andopen the Service Water to Component Cooling Water and Auxiliary Cooling Water valves. TheATC will control RCS pressure to recover pressurizer level. The BOP will take manual control ofEmergency Feedwater flow and restore steam generator levels to normal.Post SIAS, the 'A' High Pressure Safety Injection (HPSI) pump will shear the shaft (red train) andthe 'B' high pressure safety injection pump (green train) will not be available due to loss of power.The BOP will start the 'C' HPSI pump to satisfy the required HSPI flow requirements.

Appendix D Scenario 1Form ES-D-1Revision 1Page 4 of 27Simulator Instructions for Scenario 1Reset simulator to MOL 100% power IC steady state.Ensure that AACG is secured and annunciators clear.Place MINIMAL RISK and Green Train Maintenance Week signs on 2C11.Ensure 'C' HPSI pump in standby aligned to Red trainEnsure 'C' CCP is the lead charging pump and aligned to Green train.Ensure 2PCV0231, Gland sealing steam pressure control valve failed closed.Ensure T1, T2, T3, T4, & T5 set to false.T6 = Reactor TripEventNo.Malf. No.Value/RampTimeEventDescription 1Place 'B' Charging pump in service and secure 'C'Charging pump.

2XSG2PT10411Trigger = T1 0'A' Steam generator safety channel pressure transmitterfails low.

3 XCVLDNHXOUTrigger = T2 80Letdown Temperature control valve input fails low.

4CVC2P36BFALTrigger = T3TRUE 'B' Charging pump supply breaker trips due to a motorfault.5RCSLOCATCBTrigger = T4 15.0 gpmReactor Coolant system leak on 'B' cold leg.

6MRGTRPLOCKOTrigger = T5FAILSU3Trigger = T6TRUETRUEMain Turbine Generator trip causing a reactor trip and aStartup #3 transformer lockout causing natural circulationof the RCS.

7CV15042Trigger = T5 0#2 Emergency Diesel Generator service water outlet valvefails to open.

8RCSLOCATCB CUED 225RAMP=10 MINReactor Coolant system leak on 'B' cold leg (225 gpmramped over 10 Minutes).

9 HPISI10A 02P-89A Safety injection pump shaft shear.

Appendix D Scenario 1Form ES-D-1Revision 1Page 5 of 27Simulator Operator CUEsAt T=0BOP will place 'B' Charging pump in service and secure 'C' Chargingpump.CUE: When 'B' charging pump is started, report as WCO that 'B' Charging pump post startchecks are satisfactory.CUE: When 'C' charging pump is secured, report as WCO that 'C' Charging pump post stopchecks are satisfactory.Cued byleadexaminerTrigger T1'A' Steam generator safety channel pressure transmitter fails low.CUE: When contacted as the WWM, then report that I & C planner will begin planning work onfailed pressure instrument.Cued byleadexaminerTrigger T2Letdown Temperature control valve input fails low.CUE: If crew has taken manual control of 2TIC-4815, then WCO reports that CCW flow on 2FIS-5261 is indicating normal which is less than 200 gpm but not on the low peg. If the crew has nottaken manual control of 2TIC-4815, then report there is no flow indicated on 2FIS-5261.CUE: If crew has restored rad monitor flow, then report flow is 1 gpm other wise report 0 gpm.CUE: When contacted as the WWM, then report that I & C planner will begin planning work onfailed temperature controller.Cued byleadexaminerTrigger T3'B' Charging pump supply breaker trips due to a motor fault.Cue: When contacted as the WCO, then report that the breaker for 'B' Coolant Charging Pump isin a 'tripped free' condition.Cue: If asked, then report that the motor for 'B' Coolant Charging Pump is hot to touch and thepaint is discolored, but no fire or smoke is evident.Cue: If requested to vent 'B' Charging pump, then report that a solid stream of water was observedwhen venting the suction to 'B' Charging Pump from 2CVC-1099/1100.Cue: If requested, then report that seal water pump is running for requested charging pump.Cued byleadexaminerTrigger T415 gpm Reactor Coolant system leak on 'B' cold leg.Cue: If requested, then report that seal water pump is running for requested charging pump.Cued byleadexaminerTrigger T5 andreactor tripMain Turbine trip and Startup #3 transformer lockout.

Appendix D Scenario 1Form ES-D-1Revision 1Page 6 of 27CUE: If requested, then report #2EDG is locked out locally.CUE: If contacted, then act as Chemistry and respond as requested.CUE: If contacted as WCO, then open the #2EDG SW outlet valve and report that 2CV-1504-2 isopen.CUE: If contacted as AO, then place #2 EDG back to AUTO and report action taken.Reactor TripReactor Coolant system 'B' cold leg leakage ramps up to 225 gpmover 10 minutes.2P-89A Safety injection pump shaft shear.CUE: if requested as WCO, then report that 'A' HPSI pump shaft is sheared.CUE: if requested as WCO, then report that 'C' HPSI pump post start checks are satisfactory.

Appendix D Scenario 1Form ES-D-2Revision 1Page 7 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 1Event

Description:

ATC places 'B' Charging pump in service and secure 'C' Charging pump.TimePositionApplicant's Actions or BehaviorT=0 SRODirect the ATC to place 'B' Charging pump in service and secure 'C'Charging pump.Refer to TRM 3.1.2.4 and determine entry is not required.ATCReview OP 2104.0028 section 8.1.ANY8.1.3 IF shifting from 2P-36B to 2P-36C, OR shifting from 2P-36C to 2P-36B,THEN perform the following:A. Refer to TRM 3.1.2.4.ATCB. Place 2P-36A handswitch (2HS-4832-1) to STOP.ATC8.1.4Place selected CCP handswitch in START.CUE: When 'B' charging pump is started, report as WCO that 'B' Charging pump poststart checks are satisfactory.ANY8.1.5Check Charging Flow goes up 43 to 45 gpm (2FIS-4863).ATC8.1.6Place CCP Select switch (2HS-4868) to positioncorresponding to selected lead pump:2P-36A (PMP B&C)2P-36B (PMP C&A)2P-36C (PMP A&B)ANY8.1.7Check Charging flow lowers 43 to 45 gpm (2FIS-4863).CUE: When 'C' charging pump is secured, report as WCO that 'C' Charging pump poststop checks are satisfactory.ATC8.1.8 IF 2P-36A previously placed in STOP,THEN place 2P-36A handswitch (2HS-4832-1) inAUTO.ATC8.1.9Place selected pump handswitch to AUTO.

Appendix D Scenario 1Form ES-D-2Revision 1Page 8 of 27ANY8.1.10 Perform the following for off-going pump configuration:A. Verify previous lead pump stops.

BOPB. Stop off-going pump Room cooler:2P-36A (2VUC-7A)2P-36B (2VUC-7B)2P-36C (2VUC-7C)

BOPC. Close off-going pump Room cooler Service WaterInlet valve:2P-36A (2CV-1500-1)2P-36B (2CV-1502-2)2P-36C (2CV-1501-5)

BOPD. Verify on-coming pump Room cooler in Normal-After-Start.

BOPE. Verify on-coming pump Room cooler Service WaterInlet valve open:2P-36A (2CV-1500-1)2P-36B (2CV-1502-2)2P-36C (2CV-1501-5)ANYDirect the WCO to perform the following:8.1.11 WHEN CCP secured > 10 minutes,THEN perform ONE of the following:Place associated Seal Water Pump handswitch inAUTO.Verify associated Seal Water Pump handswitch inHAND.- Verify handswitch status entered on Shift ReliefSheet.Termination criteria: When 'B' charging pump is placed in service and 'C' charging pump issecured or at lead examiner's discretion.

Appendix D Scenario 1Form ES-D-2Revision 1Page 9 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 2Event

Description:

'A' Steam Generator pressure transmitter, 2PT1041-1, on Channel 'A' fails low.TimePositionApplicant's Actions or BehaviorCued byLeadExaminerANYAnnounce annunciators:2K04-A4 CH A RPS/ESF/PRETRIP/TRIP2K04-B3 PPS Channel TRIP2K04-E4 MSIS PRETRIPANYReport A SG low pressure pretrip/trip on PPS insert.

BOPCompare all four channels and report 2PI-1041-1 indicates zero.

SROImplement Annunciator Corrective Action 2203.012D.2K04-A4 CH A RPS/ESF/PRETRIP/TRIP applicable actions:

2.1Refer to PPS insert on 2C03 to determine cause.

2.2Compare all Channels to validate alarm.

2.6 IF channel failed,THEN refer to Tech Specs 3.3.1.1, 3.3.2.1, 3.3.3.5,3.3.3.6, and TRM 3.3.1.1.2K04-B3 PPS Channel TRIP applicable actions:

2.1Determine which RPS or ESFAS trips have occurred onPPS inserts.

2.3 IF channel failed,THEN refer to Tech Specs 3.3.1.1 and 3.3.2.1 and TRM3.3.1.1.2K04-E4 MSIS PRETRIP applicable actions:

2.3 IF channel failed,THEN place in bypass using 2105.001, CPC/CEACOperations.

2.4Refer to Tech Spec 3.3.2.1.

Appendix D Scenario 1Form ES-D-2Revision 1Page 10 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 2Event

Description:

'A' Steam Generator pressure transmitter, 2PT1041-1, on Channel 'A' fails low.TimePositionApplicant's Actions or Behavior SROEnter Tech Spec3.3.1.1, 3.3.2.1, 3.3.3.5, and 3.3.3.6.Direct BOP to bypass bistable points for the associated functional units:A SG PRESS low (Bistable 11)A SGP - EFAS 1 (Bistable 19)A SGP - EFAS 2 (Bistable 20)SRO must enter Tech Specs 3.3.1.1, 3.3.2.1, 3.3.3.5, and 3.3.3.6.

BOPBypass the points 11, 19, and 20 on Channel A:

11.1Refer to Tech Spec 3.3.1.1, 3.3.2.1, 3.3.3.5, 3.3.3.6and TRM 3.3.1.1.

11.2Circle channel and functional units (points) to bebypassed below:Channel to be bypassed:A B C DPoints to be bypassed:1 2 3 4 5 6 7 8 9 10 11 12 13 16 17 18 19 20 11.3Enter appropriate Tech Spec/TRM actions.

11.4Verify points to be bypassed NOT bypassed in ANYother channel.

11.5Place desired points in BYPASS for selected channelon 2C23.ANYVerify annunciator 2K04-C3 PPS CHANNEL BYPASSEDVerify correct channels in bypass.

SROContact work management.Cue: When contacted as the WWM, then report that I & C planner will begin planningwork on failed pressure instrument. Termination Criteria: Affected channel points placed in bypassor at lead examiner'sdiscretion.

Appendix D Scenario 1Form ES-D-2Revision 1Page 11 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 3Event

Description:

Letdown Temperature control valve input fails low.TimePositionApplicant's Actions or BehaviorATCAnnounce alarmLETDOWN HX 2E29 OUTLET TEMP HI andreport temperature.

SROImplement Annunciator Corrective Action 2203.012L.ANY2.1 Check temperature on 2TIC-4815 and Computer Point (T4805).Examiners note: Temperature is reading accurately on the control boardindication and the computer point.ATC2.2 Verify letdown flow (2FIS-4801) within 10 gpm of charging flow (2FIS-4863).ANYDirect WCO to locally perform the following:2.3 Locally verify CCW flow through Letdown Heat Exchanger (2FIS-5261).CUE: If crew has taken manual control of 2TIC-4815 then WCO reports that CCW flow on2FIS-5261 is indicating normal which is less than 200 gpm but not on the low peg. Ifthe crew has not taken manual control of 2TIC-4815 then report there is no flowindicated on 2FIS-5261.ANY2.4 IF Loop 2 CCW temperature high,THEN reduce temperature using Component Cooling Water SystemOperation (2104.028).Examiners Note: Loop 2 CCW temperature is not expected to be high.ATC2.5 IF Letdown HX Temperature Controller (2TIC-4815) NOTcontrolling inAUTOMATIC,THEN perform the following:2.5.1Place 2TIC-4815 in MANUAL.2.5.2Raise CCW flow.

SROEstablish a control band for letdown heat exchanger outlet.ANYReport 2K12 J1 RADMONITOR FLOW LO SRODirect actions of 2K12 J1 RADMONITOR FLOW LO:ANYDirect WCO to perform the following:2.2 Locally check flow on 2FIS-4807.CUE: If crew has restore rad monitor flow report flow is 1 gpm other wise report 0 gpm.ANY2.3 Verify letdown flow (2FIS-4801) > 28 gpm.ANY2.4 Verify L/D to Rad Monitor (2CV-4804) open. Termination Criteria: When the letdown temperature controller has been placed in manualand temperature is in the directed band or at discretion of leadexaminer.

Appendix D Scenario 1Form ES-D-2Revision 1Page 12 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 4Event

Description:

'B' Charging pump supply breaker trips due to a motor fault.TimePositionApplicant's Actions or BehaviorCued byLeadExaminerATCAnnounce 2K12-B3 Charging low flow alarm.Announce that 'B' CCP has tripped and both red and green lights are out.

SROEnter and direct the actions of AOP, OP-2203.036, Loss of charging.ATC1. Check Charging flow path as follows: Suction source aligned to VCT, RWT, or BAMT. Charging Header Isolation valve(2CV-4840-2) open.ATC 2.IF lead Charging pump stoppedAND green indicating light OFF,THEN start backup Charging pump.ATC 3.Check for adequate Charging pump operation as follows:Charging header flow 40 to 45 gpm.Charging Pump Discharge header pressure greater than RCSpressure.Charging Pump Discharge pressure and flow stable.ANY 4.Check for indications of Charging header rupture: VCT level drop. Aux Building or CNTMT radiation level rise. Waste Tanks 2T20A/B level rise. CNTMT Sump level rise. Aux Building sump level rise.Examiner Note: There will be no indications of a Charging Headerrupture and the SRO should proceed to step 9.

SRODirect Waste Control Operator to vent the suction of 'B' CCP.9. Locally check affected Charging pump for gas binding usingAttachment B,Charging Pump Venting.

Appendix D Scenario 1Form ES-D-2Revision 1Page 13 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 4Event

Description:

'B' Charging pump supply breaker trips due to a motor fault.TimePositionApplicant's Actions or BehaviorCue: If requested to vent 'B' Charging pump, then report that a solid stream of waterwas observed when venting the suction to 'B' Charging Pump from 2CVC-1099/1100.Cue: If asked report that the motor for 'B' Coolant Charging Pump is hot to touch andthe paint is discolored, but no fire or smoke is evident.Cue: When contacted as the WCO, then report that the breaker for 'B' CoolantCharging Pump is in a 'tripped free' condition.

SRO10. IF Charging pumps were NOT gas bound, THEN GO TO Step 17.(B charging pump will not be gas bound)ATCExaminer Note: All of the following steps may be satisfied and onlyneed to be checked by the ATC with exception of the following:Recording charging header data andRestoring Letdown (which may need to be restored if itisolated on high temperature).17. Restore Charging and Letdown as follows:A. Verify Charging Pump Header Isolation valve (2CV-4840-2)open.B. Verify VCT Outlet valve(2CV-4873-1) open.C. Verify RWT to Charging Pump Suction valve (2CV-4950-2)closed.D. Verify at least ONE Charging pump running, refer to 2104.002,Chemical and Volume Control

.1) Record charging header data using 2202.010, StandardAttachment 44, Charging Header Data.E. Check for adequate Charging pump operation as follows:Charging header flow 40 to 45 gpm.Charging Pump Discharge header pressure greater thanRCS pressure.Charging Pump Discharge pressure and flow stable.F. Restore Letdown, refer to 2104.002, Chemical and VolumeControl.Cue: If requested report that seal water pump is running for requested charging pump.

SROG. Exit this procedure. (SRO will exit the loss of Charging Appendix D Scenario 1Form ES-D-2Revision 1Page 14 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 4Event

Description:

'B' Charging pump supply breaker trips due to a motor fault.TimePositionApplicant's Actions or Behaviorprocedure.)

SRORefer to ACA 2K12 C2 Pumps not available from independent bussesand/or ACA 2K04 A2 SIAS inop.

2.1Refer to TRMs 3.1.2.3 and 3.1.2.4.

SRORefer to TRM 3.1.2.4 and determine entry is not required IAW the TRMbases.The SRO may direct the ATC to place 'C' CCP on the GREEN side IAW2104.002 CHEMICAL AND VOLUME CONTROL. Termination Criteria: When backup CCP started or at discretion of lead examiner.

Appendix D Scenario 1Form ES-D-2Revision 1Page 15 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 5Event

Description:

15 gpm Reactor Coolant system leak on 'B' cold leg.TimePositionApplicant's Actions or BehaviorCued byLeadExaminerANYReport the following indications:Containment dew point risingPressurizer Level lowing.Letdown flow lowering.

SROPerform the following actions:Assess Critical parametersDetermine RCS leak is present and enter Excess RCS LeakageAOP.SROEnter and direct the actions of AOP, OP-2203.016 Excess RCS Leakage

1. Open Placekeeping page.ANY*2. Check PZR level controlled within 5% of setpoint.(The SRO may direct the ATC to start Backup Charging pumps asnecessary to maintain PZR level within 5% of setpoint)Cue: If requested report that seal water pump is running for requested charging pump.ANY*3. Check PZR level maintained within 10% of setpoint.ATC*4. Maintain VCT level 60 to 75%, refer to 2104.003, ChemicalAddition.ANY*5. Determine RCS leakrate by ANY of the following: Computer LKRT programs. Check PZR level stable and use Charging and Letdownmismatch minus Controlled Bleed Off. Check Letdown isolated and estimate RCS leak rate by totalCharging flow minus Controlled Bleed Off. CNTMT Sump level rate of rise.

Appendix D Scenario 1Form ES-D-2Revision 1Page 16 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 5Event

Description:

15 gpm Reactor Coolant system leak on 'B' cold leg.TimePositionApplicant's Actions or BehaviorANY6.IF RCS leakage greater than 44 gpmAND in Mode 1 OR 2, THEN perform the following:

A.Trip Reactor.

B.GO TO 2202.001, Standard Post Trip Actions.

SRODirect the Shift Manager to perform the following step:*8. Refer to 1903.010,Emergency Action Level Classification.

SRO*9.IF location of leak is known,THEN perform the applicable following steps (10.A through 10.J):CNTMTstep 10.APrimary to SecondaryLeakagestep 10.BQuench Tankstep 10.C RDTstep 10.DRCP Sealsstep 10.ECCW Systemstep 10.FCVCSstep 10.GSIT inleakagestep 10.HVacuum Degasifierstep 10.IRCS Samplestep 10.JExaminers note: Leak location will be known and only step 10.A shouldbe performed.ANYNote: If this step entered from step 9, then only perform substep foridentified leak path.

10.A. Check the following CNTMT parameters stable or lowering:Humidity (Dewpoint temperature) Sump level Temperature Pressure BOP 10.A. Perform the following:1) Attempt to locate leak in CNTMT by monitoring CAMSsuction points and CNTMT Area Radiation monitors.Examiner note: This action is a long term action and they may notchange CAMS suction points during this drill.

Appendix D Scenario 1Form ES-D-2Revision 1Page 17 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 5Event

Description:

15 gpm Reactor Coolant system leak on 'B' cold leg.TimePositionApplicant's Actions or BehaviorATC2) Verify leak NOT in Letdown line inside CNTMT byperforming the following:a) Isolate Letdown by verifying at least ONE LetdownIsolation valve closed:-4820-2-4821-1-4823-2 (least preferred) b)IF RCS leakage NOT stopped, THEN letdown may berestored at discretion of SM using 2104.002, Chemicaland Volume Control.Examiners Note: Isolating Letdown will not isolate the leak and Letdownshould be restored to service.

SRO*11. Check leakage within allowable limits, refer to TS 3.4.6.2,Reactor Coolant System Leakage.SRO must enter Tech Spec 3.4.6.2ALL*11. Perform the following:A. Continue efforts to locate and isolate leak.

B. IF plant shutdown required,THEN perform EITHER of the following using 2102.004,Power Operations:

1) IF leakage greater than 10 gpm, THEN perform RCSboration using2104.003, Chemical Addition,Attachment R, RCS Boration from the RWT or BAMT.

2) IF RCS leakage less than 10 gpm,THEN perform RCS boration using2104.003, Chemical Addition,Exhibit 3, Normal RCS Boration atPower.Examiners Note: The ATC should start a shutdown using 2104.003,Chemical Addition, Attachment R Termination Criteria: When reactivity manipulations are satisfied or at the discretion of thelead examiner.

Appendix D Scenario 1Form ES-D-2Revision 1Page 18 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformerlockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outletvalve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.TimePositionApplicant's Actions or BehaviorCued byLeadExaminerANYReport Reactor Tripped SROEnter and implement EOP 2202.001, Standard Post Trip Actions.

SRO 1.Notify Control Board Operators to monitor safety functions usingExhibit 7, CBO Reactor Trip Checklist.

2.Open Safety Function Tracking page.ReactivitycontrolsafetyfunctionATC 3.Check Reactivity Control established as follows:A. Reactor power lowering._____B. ALL CEAs fully inserted.VitalAuxiliariessafetyfunction BOP 4.Check Maintenance of Vital Auxiliaries satisfied:A. Main Turbine tripped.B. Generator Output breakers open.C. Exciter Field breaker open.D. At least ONE 6900v AC bus energized.(Not met)E. At least ONE 4160v Non-vital AC bus energized.F. BOTH 4160v Vital AC buses energized.G. BOTH DGs secured. (Both DGs will be running, performcontingency to secure #2 EDG

)H. At least ONE 125v Vital DC bus energized:2D01 - SPDS point E2D012D02 - SPDS point E2D02 Appendix D Scenario 1Form ES-D-2Revision 1Page 19 of 27

______Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformerlockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outletvalve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.TimePositionApplicant's Actions or Behavior SRODirect Inside AO perform the following:G. IF ANY DG running AND SW NOT aligned,THEN locally stop DG by unlocking and placing "ENGINECONTROL" handswitch in LOCKOUT:(#2 EDG will be locked out due to no service waterEvent #7)Cue: If requested report #2EDG is locked out locally.

RCSInventoryControlSafetyfunctionATC 5.Check RCS Inventory Control established as follows:A. PZR level:10 to 80%.Trending to setpoint.(May not met due to LOCA Event#8, perform contingency)B. RCS MTS 30°F or greater.

RCSInventoryControlSafetyfunction SRODirect the following as necessary:A. Perform as necessary:

1) IF SIAS actuated on PPS inserts, THEN GO TOStep 6.2) Verify PZR Level Control system restoring level to setpoint.

RCSPressureControlSafetyfunctionATC 6.Check RCS Pressure Control:1800 to 2250 psia.Trending to setpoint

. (May not met due to LOCA Event #8,perform contingency)

Appendix D Scenario 1Form ES-D-2Revision 1Page 20 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformerlockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outletvalve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.TimePositionApplicant's Actions or Behavior SRODirect the following actions as necessary:

6.Perform as necessary:D. IF RCP 2P32A or 2P32B stopped,THEN verify associated PZR Spray valve in MANUAL andclosed.(This step should be directed)

E. IF RCS pressure lowers to 1650 psia or less,THEN perform the following:(This step may be directed)1) Verify SIAS actuated on PPS inserts.

2)GO TO Step 7.F. Verify PZR Pressure Control system restoring pressure tosetpoint.G. IF ALL RCPs stopped AND RCS pressure greater than 2250psia, THEN initiate Aux spray usingAttachment 27, PZR Spray Operation.ATCD. IF RCP 2P32A or 2P32B stopped,THEN verify associated PZR Spray valve in MANUAL andclosed.ATC 7.Check Core Heat Removal by forced circulation:A. At least ONE RCP running. (Not met due to SU #3 lockout,perform contingency)Core HeatRemovalsafetyfunction.ANYPerform contingency:A. IF ALL RCPs stopped,THEN perform the following:1) Verify BOTH PZR Spray valves in MANUAL and closed.

2)GO TO Step 8.

Appendix D Scenario 1Form ES-D-2Revision 1Page 21 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformerlockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outletvalve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.TimePositionApplicant's Actions or BehaviorRCS HeatRemovalSafetyFunctionANY 8.Check RCS Heat Removal:A. Check SG available by BOTH of the following:At least ONE SG level 10 to 90%.FW maintaining SG level. (Not met due to SU #3 lockout,perform contingency)B. Check MFW in RTO. (Not met due to SU #3 lockout, performcontingency)C. Check Feedwater line intact by the following:SG level stable or rising.NO unexplained step changes or erratic FW flow.NO unexplained step changes or erratic Condensate flow.D. Check Condensate Pump discharge header pressure < 753 psig.E. Check SG pressure 950 to 1050 psia.F. Check RCS T C 540 to 555°F.ANYA. Perform the following:

1)IF SG level lowering,THEN verify EFAS actuated.ANYB. Verify EITHER of the following:BOTH MFW pumps tripped.SG levels controlling at setpoint Appendix D Scenario 1Form ES-D-2Revision 1Page 22 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformerlockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outletvalve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.TimePositionApplicant's Actions or BehaviorContainmentSafetyFunctionATC 9.Check CNTMT parameters:A. Temperature and Pressure:Temperature less than 140°F.Pressure less than 16 psia.B. Check CNTMT Spray pumps secured.C. NO CNTMT radiation alarms or unexplained rise in activity:1) CAMS alarms:"CNTMT PART/GAS RAD HI/LO" annunciator(2K10-B6) clear.2) RCS leakage alarms:"AREA RADIATION HI/LO" annunciator (2K11-B10)clear."PROC LIQUID RADIATION HI/LO" annunciator(2K11-C10) clear.3) Check the following radiation monitors trend stable:CNTMT AreaMSProcess LiquidD. NO secondary system radiation alarms or unexplained rise inactivity: 1) "SEC SYS RADIATION HI" annunciator (2K11-A10) clear.2) Secondary Systems Radiation monitors trend stable:Main Steam linesSG SampleCondenser Off Gas SRO10. Notify STA to report to control room.11. Verify NLOs informed of Reactor trip.12. Verify Reactor trip announced on Plant page.13. Notify SM to refer to Technical Specifications and 1903.010,Emergency Action Level Classification.

Appendix D Scenario 1Form ES-D-2Revision 1Page 23 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformerlockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outletvalve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.TimePositionApplicant's Actions or Behavior SRO14. Direct control board operators to acknowledge ALL annunciatorsand announce ALL significant alarms.

SRO15. Check ALL safety function acceptance criteria satisfied.(All safetyfunctions are not satisfied, perform contingency)15. IF ANY safety function acceptance criteria NOT satisfied,THEN perform the following:A. Notify control room staff ofsafety functions NOT satisfied.

B.GO TO Exhibit 8,Diagnostic Actions.

SRODiagnose Loss of Coolant Accident EOP, 2202.003 SROEnter and Implement Loss of Coolant Accident EOP, 2202.003 SRO* 1. Confirm diagnosis of LOCA as follows:A. Check SFSC acceptance criteria satisfied every 15minutes.(Normally performed by the STA)B. Refer to Standard Attachment 20,Break Identification Chart.C. Verify SG Sample valves open.D. Direct Chemistry to sample BOTH SGs for activity.

E. IF SGs indicate primary to secondary leakage within TS limits,THEN continue with this procedure using SG with lowest leakrate for cooldown.Cue: If contacted act as Chemistry respond as requested.

SRO* 2. Notify SM to refer to Technical Specifications and 1903.010,Emergency Action Level Classification.

SRO3. Open Placekeeping page.

SRO4. Record present time:Time __________ANY5. Verify SIAS and CCAS actuated on PPS inserts.

Appendix D Scenario 1Form ES-D-2Revision 1Page 24 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformerlockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outletvalve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.TimePositionApplicant's Actions or BehaviorANY6. Notify Control Board Operators to perform the following:

A.Monitor floating steps.B. Verify actuated ESFAS components using 2202.010, Exhibit 9,ESFAS Actuation.

SROExaminer note: The SRO should pull up the floating step forperforming a cooldown and direct the actions of the cooldown step.Step 1 of the unisolated LOCA section.1. Perform controlled cooldown to 275°F T C as follows:ANYA. Check RCS T C greater than 275°F.ATCB. Reset Low PZR Pressure andLow SG Pressure setpoints during cooldown anddepressurization.ANYC. Verify maximum of ONE RCP running in EACH loop.ATCD. IF RCP 2P32A or 2P32B stopped,THEN verify associated PZR Spray valve in MANUAL andclosed.ATCE. Monitor cooldown rate as follows:Record RCS T C and PZR temperature using StandardAttachment 8, RCS Cooldown Table.Plot RCS pressure versus RCS T C using StandardAttachment 1,P-T Limits every 15 minutes.ATCF. Initiate RCS cooldown usingSDBCS bypass valves or ADVs.ANYG. Verify EFW or AFW capable of feeding SGs.ANYH. Secure running MFW pump.

CRITICAL STEPFloatingstep for acooldownMustcommencea cooldown>40 degreesper hour within 30min. ofenteringLOCAprocedureANYI. Close ALL MFW Block valves.

Appendix D Scenario 1Form ES-D-2Revision 1Page 25 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformerlockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outletvalve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.TimePositionApplicant's Actions or Behavior SROExaminer note: The SRO should pull up the floating step for restoringESF and Non/ESF systems and direct the actions of the step. Step 9 ofthe entry section for LOCA OP-2202.003.9. Restore ESF/Non-ESF systems post-SIAS as follows:ANYA. Verify at least ONE SW pump running on EACH loop.ANYB. Verify DG SW Outlet valves open.(Not met on #2 EDG,perform contingency)Examiner note: The Crew should have the WCO open the Service water outlet valve for #2EDGthen have the AO remove the EDG from Lockout to allow it to start, but mayelect to start the Alternate AC generator to supply 2A-4 vital 4160V bus orcross-tie 2B-5 and 2B-6 vital 480 volt busses using floating step 21 from theentry section of 2203.003 LOCA. One of these actions should be completed torestore auxiliary spray capability (RCS pressure control)ANYDirect Non-licensed operators to perform the following:B. IF SW Outlet valve can NOT be opened from Control Room,THEN locally perform the following for affected DG:1) Open DG SW Outlet valve:"2DG-1 SW OUTLET"2CV-1503-1"2DG-2 SW OUTLET"2CV-1504-22) Monitor DG "SCAV AIR TEMP":I-2931I-2981 3) IF DG "SCAV AIR TEMP" rises to 170°F, THEN stop DGby unlocking and placing "ENGINE CONTROL" switch inLOCKOUT:Cue: If contacted as WCO then open the #2EDG SW outlet valve and report that 2CV-1504-2 is open.Cue: If contacted as AO, then place #2 EDG back to AUTO and report action taken.ANYC. Verify SW pump suction aligned to Lake.

Appendix D Scenario 1Form ES-D-2Revision 1Page 26 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformerlockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outletvalve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.TimePositionApplicant's Actions or BehaviorANYD. Check 4160v Non-vital bus 2A1 or 2A2 energized from offsitepower.ANYE. Check BOTH 4160v Vital buses2A3 AND 2A4 energized from offsite.(Not met due to Startup#3 lockout, perform contingency)ANYE. Perform the following:

2) IF EITHER 4160v Vital bus energized from DG,THEN perform the following:a) Verify ONE SW pump running on train supplied by DG.

b) GO TO Step 9.G.ANYG. Check SW to CCW restored.(Not met, perform contingency)ANYG. IF CCW available,THEN restore SW to CCW, refer to Exhibit 5, CCW/ACW/SWAlignment.ANYH. Check ACW restored. (Not met, perform contingency)ANYH. Restore SW to ACW, refer to Exhibit 5, CCW/ACW/SWAlignment.ANYI. Maintain SW header pressure greater than 85 psig.Termination criteria: When the Crew has commenced a cooldown or at discretion of leadexaminer.

Appendix D Scenario 1Form ES-D-2Revision 1Page 27 of 27Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 9Event

Description:

2P-89A Safety injection pump shaft shear.TimePositionApplicant's Actions or BehaviorANYRecognizes and announces failure of 'A' HPSI pump due to shaft shear.Cue: As waste control operator if requested report that 'A' HPSI pump shaft is sheared.

SRODirect BOP start 'C' HPSI pump (2P89C).

CRITICAL STEP BOPOn 2C17, remove the hand switch for 'C' HPSI pump (2P89C) fromPTL and verified 2P-89C started and discharge pressure indicated (ifpressure < 1450psia, verified flow to RCS) or #2 EDG restored and 'B'HPSI pump (2P-89) is running.2P-89C or 2P-89B must be started prior to reaching 10 0F Margin toSaturation.Termination criteria: Termination criteria: When 'B' or 'C' HPSI pump is started or at thediscretion of the lead examiner.

Appendix D Scenario 2Form ES-D-1Revision 1Page 1 of 26Facility: ANO-2Scenario No.: 2 (New)Op-Test No.: 2009-1Examiners:Operators:Initial Conditions:100% MOL, All Engineered Safety Features systems are in standby. Gland Seal steam pressure controlvalve 2PCV-0231 jacked closed. RED Train Maintenance Week. 2T-6A Boric Acid Make up tank isaligned for acid reducing shut down chemistry for Unit 1Turnover:100%. 260 EFPD. EOOS indicates 'Minimal Risk'. 2PCV-0231 jacked closed, manually control sealsteam pressure. RED Train Maintenance Week. 2T-6A Boric Acid Make up tank is aligned for acidreducing shut down chemistry for Unit 1 refueling outage that starts next week.Evolution scheduled: Drain Containment Sump to 50% level. Steps 20.1.1 and 20.1.2 of OP-2104.014have been completed.EventNo.Malf. No.EventType*EventDescription 1CV20601 DO_HS_2060_G DO_HS_2060_RC (BOP)C (SRO)Containment sump drain valve breaker trips duringnormal drain evolution. Tech Spec for SRO 2 SW2P-4AC (BOP)C (SRO)2P-4A Service water pump breaker trips 3XRCCHAPLVLI (ATC)I (SRO)'A' Pressurizer level channel fails High. Tech Spec for SRO 4R (ATC)N (BOP)N (SRO)System Dispatcher call with a request to reduce powerto ~ 850MWe(~80%) within 30 min.

5CV10101 SGAMSIVBEFM (ALL)'A' Steam Generator MSIV 2CV-1010-1 fails closed.Then 2 minutes after trip an Excess Steam Demandoutside containment commences.

6CEA38STUCKCV48731CVC2P39BC (ATC)C (SRO)Control Element Assembly #38 remains fullywithdrawn when the reactor trips. The VCT outlet willnot close and 2P-39B will trip when the reactor trips.

7ESFCCAS2C (BOP)C (SRO)Green train Containment coolers fail to automaticallyactuate.* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajorTotal malfunctions. = 6, Malfunctions. after EOP entry = 2, Abnormal events = 3, Major transient = 1,EOPs with substantive actions =1, EOP Contingencies = 1, Critical tasks = 2.

Appendix D Scenario 2Form ES-D-1Revision 1Page 2 of 26Scenario #2 Objectives 1)Evaluate individual response to a failure of a containment isolation valve.

2)Evaluate individual ability to operate safety related equipment.

3)Evaluate individual response to a failure of a Service Water pump.

4)Evaluate individual response to a failure of a Pressurizer level control channel.

5)Evaluate individual ability to perform a reduction in plant power.

6)Evaluate individual response to a stuck out CEA after a Reactor Trip.

7)Evaluate individual response to a failed closed Main Steam Isolation Valve.

8)Evaluate individual ability to mitigate an Excess Steam Demand Outside containment.

9)Evaluate individual ability to monitor operation of Engineered Safety Features equipment.

SCENARIO #2 NARRATIVESimulator session begins with the plant at 100% power steady state Gland seal regulator,2PCV0231 is jacked closed and 2T-6A is aligned for acid reducing chemistry.When the crew has completed their control room walk down and brief, The BOP will drain theContainment sump to the Auxiliary building sump using the normal drain method. When the BOPattempts to close 2CV-2060-1 its supply breaker will trip. The BOP should ensure the series sumpdrain valve 2CV-2061-2 is closed and sump level is stable. The SRO will determine that Tech Spec3.6.3.1 is applicable and will enter Tech Spec 3.6.3.1.After the Crew has entered the appropriate Tech Spec, verified sump level is stable or cued by leadexaminer; the 'A' Service Water Pump (2P-4A) breaker will trip open. The SRO will enter AOP,2203.022 Loss of Service Water. The SRO will direct the BOP to start 2P-4B Service Water Pump.After the 'B' Service Water pump is placed in service or cued by lead examiner, the in servicePressurizer (PZR) control channel level instrument will fail high. This will result in letdown goingto maximum flow, the two backup CCP's will automatically stop, all PZR heaters energizing andactual PZR level lowering. AOP 2203.028, PZR Systems Malfunctions, will be entered and actionsdirected by the SRO. The ATC will take the letdown flow controller to manual and control PZRlevel. The ATC will also verify that the other level control channel is reading correctly and selectthat channel for control and place the PZR low level cutoff switch to the unaffected channel. TheSRO will enter Tech Spec 3.3.3.6 Post Accident Instrumentation. When the auto and manual signalsare matched, the ATC will place the letdown flow controller to automatic.

Appendix D Scenario 2Form ES-D-1Revision 1Page 3 of 26SCENARIO #2 NARRATIVE (continued)After the ATC has placed 'B' Channel pressurizer level control in service and restored letdown toautomatic, The Pine Bluff Systems Operations Center (SOC) will call the Control Room with aTransmission Loading Relief (TLR) to reduce plant output by 200MWe. The SOC will also reportthat all limits of EN-DC-199 are still met. If Contacted, Unit 1 will be unable to maneuver due toICS maintenance.After the ATC has completed the required reactivity manipulation or cued by lead examiner,2CV-1010-1 'A' Steam Generator Main Steam Isolation Valve will fail closed. The crew willverify the reactor is tripped.The Crew will implement Standard Post Trip Actions (SPTA), OP 2202.001. When the reactortrips one CEA will remain withdrawn which requires emergency boration. The VCT outlet willremain open and 2P-39B Boric Acid Makeup pump will trip when started. Reactivity control willnot be satisfied. During SPTAs, an Excess Steam Demand event outside of Containment willcommence. The Crew will manually actuate Main Steam Isolation Signal (MSIS) or verify that aMain Steam Isolation signal automatically actuates. The Crew will secure and/or verify thatEmergency Feedwater (EFW) is not feeding 'A' Steam generator. The ATC will secure twoReactor coolant Pumps when RCS pressure goes below 1400 psia.The SRO will diagnose Functional Recovery due to reactivity control not being met and enter OP2202.009, Functional Recovery.The crew will manually control Reactor Coolant Temperature once the 'A' SG boils dry using theupstream Atmospheric Dump Valve on 'B' SG. The ATC will control RCS pressure using normalspray.

Appendix D Scenario 2Form ES-D-1Revision 1Page 4 of 26Simulator Instructions for Scenario 2Reset simulator to MOL 100% power IC stead state.Ensure that AACG is secured and annunciators clear.Place MINIMAL RISK and RED Train Maintenance Week signs on 2C11.Swing ESF equipment aligned to the RED train.'B' CCP lead charging pump.2PCV0231, Gland sealing steam pressure control valve failed closed.2T-6A aligned for acid reducing shut down chemistry (CV49201 Value = 0, 2P-39A running with therecirc open, 2P-39A discharge valve closed CVC40A = 0)Ensure CVC40A = 0T1, T2, T3, T4, set to false.T1 set to OE3C0601T5 set to Reactor trip.EventNo.Malf. No.Value/RampTimeEventDescription 1CV20601 DO_HS_2060_G DO_HS_2060_RTrigger = T1 0.0Containment isolation valve 2CV-2060-1 breaker trips.

2 SW2P-4ATrigger = T2 0.02P-4A Service water pump breaker trips.

3XRCCHAPLVLTrigger = T3 100Control Channel "A" Pressurizer Level fails High.

4System Dispatcher call with a TLR to reduce power to ~850MWe within 30 min.

5CV10101 SGAMSIVBEFTrigger = T4 0 1.5/Delay =2 min.'A' Steam Generator MSIV 2CV-1010-1 fails closed.Then 2 minutes after trip an Excess Steam Demandoutside containment commences.

6CEA38STUCKCV48731CVC2P39BTrigger = 5 forCVC2P39B only 0%1 TrueControl Element Assembly #38 remains fully withdrawnwhen the reactor trips. The VCT outlet will not close and2P-39B will trip when the reactor trips.

7ESFCCAS2 TrueGreen train Containment coolers fail to automatically ormanually actuate.

Appendix D Scenario 2Form ES-D-1Revision 1Page 5 of 26Simulator Operator CUEsAt T=0Trigger T1Containment isolation valve 2CV-2060-1 tripped its supply breakerduring normal drain evolutionCue: When contacted as the WWM, then report that electrical planner will begin planning worktrouble shoot 2CV-2060-1.Cue: If asked report that the breaker for 2CV-2060-1 2B51-B2 is trip free and breaker 2B51-H3 isclosed.Cued byleadexaminerTrigger T22P-4A Service water pump breaker trips.Cue: If asked report that the motor for 'A' Service Water Pump is hot to touch, but no fire orsmoke is evident.Cue: If requested when 'B' Service Water pump is started, report as AO that 'B' Service Waterpump post start checks are satisfactory.Cue: When contacted as the WWM, then report that the electrical planner will begin planningwork on failed pump.Cued byleadexaminerTrigger T3Control Channel "A" Pressurizer Level fails High.Cue: When contacted as the WWM, then report that I & C planner will begin planning work onfailed level instrument.Cued byleadexaminerSystem Dispatcher call with a TLR to reduce power to ~ 850MWewithin 30 min.Cue: Call as the Pine Bluff Systems Operations Center (SOC) with a Transmission Loading Relief(TLR) to reduce plant output to ~850 MWe (lower output by 200 MWe) within 30 min. The SOCwill also report that all limits of EN-DC-199 are satisfied.Cue: If contacted as Unit 1 report that the plant is within 60 days of a refueling outage and can notlower power.Cued byleadexaminerTrigger T4'A' Steam Generator MSIV 2CV-1010-1 fails closed.Reactor Trip Trigger T5'A' Steam Generator Safety valve 2PSV-1002 sticks openReactor TripControl Element Assembly #38 remains fully withdrawn when thereactor trips. The VCT outlet will not close and 2P-39B will trip whenthe reactor trips.Cue: If contacted as the AO to open 2CVC-40A (2P-39A discharge valve), then report that is stuckclosed and will not open.Cue: If contacted as the WCO to locally close 2CV-4873-1 VCT outlet valve, then delay locallyclosing the valve until after Functional recovery procedure has been entered.ContainmentCoolingactuation.Green train Containment coolers fail to automatically or manuallyactuate.

Appendix D Scenario 2Form ES-D-2Revision 1Page 6 of 26Op-Test No.: 2009-1 Scenario No.: 2 Event No.: 1Event

Description:

Draining the Containment sump beginning with step 20.1.3.TimePositionApplicant's Actions or Behavior BOP20.1.3 Open the following valves to drain CNTMT sump:Containment Sump Isolation valve (2CV-2060-1)Containment Sump Isolation valve (2CV-2061-2)ANY*20.1.4 Using level indication or corresponding computer points,monitor the following to prevent overflow:Aux Building sump (2LIS-2000 or 2LIS-2000B)In service Waste tank:- 2T-20A (2LIS-2010)- 2T-20B (2LIS-2012)

BOP*20.1.5 Cycle 2CV-2061-2 as necessary to prevent overflowingAux Building sump.

BOP20.1.6 WHEN draining is complete,THEN close the following valves:2CV-2061-22CV-2060-1 BOPReport to the SRO that 2CV-2060-1 lights are out and suspect the breakeris tripped.ANYVerify that Containment Sump level is not trending down.Cue: If asked report that the breaker for 2CV-2060-1 2B51-B2 is trip free and breaker 2B51-H3is closed.

SRORefer to Tech Specs and enter Tech Spec 3.6.3.1 and determine that 2CV-2060-1 must be isolated within 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br />Examiner note: SRO must Tech Spec 3.6.3.1 due to 2CV-2060-1 SROContact work management.Cue: When contacted as the WWM, then report that electrical planner will begin planning worktrouble shoot 2CV-2060-1.Termination criteria: When Tech Spec 3.6.3.1 is entered and 2CV-2061-2 is closed or at leadexaminer's discretion.

Appendix D Scenario 2Form ES-D-2Revision 1Page 7 of 26Op-Test No.: 2009-1 Scenario No.: 2 Event No.: 2Event

Description:

2P-4A Service water pump breaker trips.TimePositionApplicant's Actions or BehaviorCued byleadexaminerANYReport 2K06-B5 "2P4A BREAKER TRIP" SROEnter and direct actions of AOP, 2203.022 Loss of Service Water*1. Check the following criteria satisfied:A. Breaker trip annunciators clear (2K06-B5/2K05-B4, B5).(Perform contingency)

SRO A.GO TO Step 7.SRO7. Check "2P4A BREAKER TRIP" annunciator (2K06-B5) clear.(Perform contingency)

BOPA. IF 2P4B aligned to Loop 1,THEN verify 2P4B running.Examiner note: BOP will verify a suction source and start 2P-4BCue: If asked report that the motor for 'A' Service Water Pump is hot to touch, but no fire orsmoke is evident.Cue: If requested when 'B' Service Water pump is started, report as AO that 'B' Service Waterpump post start checks are satisfactory.

SROContact work management.Cue: When contacted as the WWM, then report that the electrical planner will begin planningwork on failed pump.Termination criteria: When 'B' service water pump is placed in service or at lead examiner'sdiscretion.

Appendix D Scenario 2Form ES-D-2Revision 1Page 8 of 26Op-Test No.: 2009-1 Scenario No.: 2 Event No.: 3Event

Description:

'A' Pressurizer level channel fails High. Tech Spec for SROTimePositionApplicant's Actions or BehaviorCued byleadexaminerANYAnnounce alarm 2K10-J6 CNTRL CH 1 LEVEL HIGH.Report 2LI-4627-2 and 2LR-4625 indicate normal.Letdown flow high.

SRODirect the ATC to place letdown flow controller to manual and lower flowto control pressurizer level.ATCPlace 2HIC-4817 to manual and lower letdown flow to control pressurizerlevel.SROEnter and implement PZR Systems Malfunctions AOP 2203.028 SRO6. Check the following PZR level annunciators clear:"CNTRL CH 1/2 LEVEL LO" 2K10-G6/G7"CNTRL CH 1/2 LEVEL HI"2K10-J6/J7(Annunciators not clear, implement contingency)ANY6. Perform the following:A. Compare PZR level instruments to determine the affectedchannel.ATC C. IF selected control channel failed, THEN perform the following:1) Place Letdown Flow controller (2HIC-4817) in MANUAL.ATC2) Place PZR Level Channel Select switch (2HS-4628) tounaffected channel.ATC3) Place PZR Low Level Cutoff select switch (2HS-4642) tounaffected channel.ANY 4)Verify PZR heaters and Normal Spray operating to restoreRCS pressure 2025 to 2275 psia.ATC 5) WHEN Letdown Flow controller (2HIC-4817)automaticAND manual signals match, THEN place Letdown Flowcontroller in AUTO.

Appendix D Scenario 2Form ES-D-2Revision 1Page 9 of 26Op-Test No.: 2009-1 Scenario No.: 2 Event No.: 3Event

Description:

'A' Pressurizer level channel fails High. Tech Spec for SROTimePositionApplicant's Actions or BehaviorExaminer Note: The ATC may elect to take manual control of thepressurizer level controller (2LIC-4627), match the auto and manualsignals then place the pressurizer level controller (2LIC-4627) toautomatic.

SROE. Refer to TS 3.3.3.5, Remote Shutdown Instrumentation and3.3.3.6, Post-Accident Instrumentation.Examiner note: SRO must enter Tech Spec 3.3.3.6 Post AccidentInstrumentation.

SROContact work management.Cue: When contacted as the WWM, then report that I & C planner will begin planning work onfailed level instrument. Termination Criteria: PZR level control selected to channel 2 in auto control or at leadexaminer's discretion.

Appendix D Scenario 2Form ES-D-2Revision 1Page 10 of 26Op-Test No.: 1 Scenario No.: 2 Event No.: 4Event

Description:

System Dispatcher call with a TLR to reduce power to ~ 850MWe within 30 min.Crew will perform a plant shutdownTimePositionApplicant's Actions or BehaviorCue: Call as the Pine Bluff Systems Operations Center (SOC) with a Transmission LoadingRelief (TLR) to reduce plant output to ~850 MWe (lower output by 200 MWe) within 30 min.The SOC will also report that all limits of EN-DC-199 are satisfied and the reliability of Offsitepower is not impacted.Cued byleadexaminer SROImplement 2107.001 attachment S SRO 1.1IF notified by the SOC, TOC or Woodlands dispatcher that aTLR has been issued for ANO,THEN perform the following:1.1.1 Conduct Reactivity Brief for requested downpower.ALL1.1.2 Unit designated to reduce power, commence powerreduction using respective Power Operations procedure.Cue: If contacted as Unit 1 report that the plant is within 60 days of a refueling outage and cannot lower power.

SRO1.1.3 Notify Operations Management.Examiner note: 2107.001 attachments step 1.1.4 and 1.15 are normally completed by theShift Manager and are not expected to be completed by the Control Room Supervisor.1.1.4 IF power reduction requested is greater than 25 MWe,THEN inform Site Duty Manager to perform thefollowing:A. Perform required notifications per Notifications ofOff-Normal Situations/Corporate Duty Managerresponsibilities (EN-OM-128).B. Notify NRC Resident.1.1.5 IF notified by the Dispatcher of any off site disturbancethat may affect the reliability of Offsite Power,THEN perform a Risk assessment using guidance inCOPD-24.1.1.6 Verify with Pine Bluff SOC that requirements of ENS-DC-199, Off-Site Power Supply Design Requirements,off-site post-trip voltage and frequency limits still met.Examiner note: The following steps are the applicable steps from 2102.004 Poweroperation to perform a power reduction to 80%

Appendix D Scenario 2Form ES-D-2Revision 1Page 11 of 26Op-Test No.: 1 Scenario No.: 2 Event No.: 4Event

Description:

System Dispatcher call with a TLR to reduce power to ~ 850MWe within 30 min.Crew will perform a plant shutdownTimePositionApplicant's Actions or Behavior SRO11.6 Notify the following of intent to reduce power:ChemistryReactor EngineeringRadiation ProtectionLittle Rock DispatcherWoodlands DispatcherATC11.7 IF power reduction NOT rapid,THEN perform the following:Determine amount of boric acid required for power reductionfrom Reactivity curves (located in Plant Data book) OR Unit2 Shift Relief Sheet (1015.016).IF NOT otherwise specified by Reactor Engineering,THEN determine desired rate of load change usingAttachment A of this procedure.Examiner note: This down power is not considered a rapid powerreduction.ATC11.8 Commence Power reduction by performing the following asnecessary:Boration using Normal Borate Mode to Charging pumpsuction (unless directed otherwise by Abnormal OperatingProcedure) Refer to Chemical Addition (2104.003).CEA insertion using CEDMCS Control System Operation(2105.009), Exhibit 3 CEDMCS Operations (normally forASI control).ANY*11.9 Lower Turbine load as necessary to hold Tave within +/- 2°F ofprogram Tref using Exhibit 1, TAVE VS TREF.ANY*11.10 Throttle Condensate recircs as necessary to maintain 650-750psig Condensate Pump Discharge pressure:2CV-06622CV-0663PowerreductionATC* 11.12 Maintain ASI by performing the following:IF power reduction rapid,THEN maintain ASI (PID 268) within Core Operating LimitsReport (COLR) limits using CEA Group 6 or Group P. IF power reduction NOT rapid,THENmaintain ASI at desired value using CEA Group 6 andGroup P per Attachment A. (QASI trip setpoint +/- 0.48)

Appendix D Scenario 2Form ES-D-2Revision 1Page 12 of 26Op-Test No.: 1 Scenario No.: 2 Event No.: 4Event

Description:

System Dispatcher call with a TLR to reduce power to ~ 850MWe within 30 min.Crew will perform a plant shutdownTimePositionApplicant's Actions or BehaviorANY*11.13 IF power change exceeds 15% within a one hour period,THEN notify Chemistry to obtain an RCS sample for Iodinebetween 2 and 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> following power change (TS 3.4.8).PowerreductionANYNotify NLO to perform the following:

• 11.15 Monitor Secondary chemistry and adjust chemical feed as neededusing Secondary System Chemical Addition (2106.028). Termination Criteria: When reactivity manipulations are satisfied or at the discretion of thelead examiner.

Appendix D Scenario 2Form ES-D-2Revision 1Page 13 of 26Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6Event

Description:

'A' Steam Generator MSIV 2CV-1010-1 fails closed.Then 2 minutes after trip anExcess Steam Demand outside containment commences. Control Element Assembly #38 remains fullywithdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactortrips.TimePositionApplicant's Actions or BehaviorCued byleadexaminerANYReport Reactor Tripped SROEnter and implement EOP 2202.001, Standard Post Trip Actions.

SRO 1.Notify Control Board Operators to monitor safety functions usingExhibit 7, CBO Reactor Trip Checklist.

2.Open Safety Function Tracking page.ReactivitycontrolsafetyfunctionATC 3.Check Reactivity Control established as follows:A. Reactor power lowering.B. ALL CEAs fully inserted.(Not met due to Event #6, performcontingency)

SRODirect ATC to perform emergency boration in progress using Exhibit 1,Emergency Boration._____B.Verify emergency boration in progress using Exhibit 1,Emergency Boration.Examiner note: Emergency boration can not be established.ATC1. Select ONE of the following Emergency Boration flowpaths:FLOWPATHACTIONS REQUIRED A.Gravity Feed A.Verify at least ONE BAMTank Gravity Feed valve open:2CV-4920-12CV-4921-1B. BAM pumps B.1) Start at least ONE BAM pump.2) Open Emergency Borate valve(2CV-4916-2).3) Verify Boric Acid Makeup Flow Control valve (2CV-4926) closed.

C.RWT to Charging pumpsC. Open Charging Pump Suction Source From RWT valve (2CV-4950-2).

Appendix D Scenario 2Form ES-D-2Revision 1Page 14 of 26Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6Event

Description:

'A' Steam Generator MSIV 2CV-1010-1 fails closed.Then 2 minutes after trip anExcess Steam Demand outside containment commences. Control Element Assembly #38 remains fullywithdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactortrips.TimePositionApplicant's Actions or BehaviorATC2. Close VCT Outlet valve (2CV-4873-1).Examiner Note: The VCT outlet valve will not close and shouldperform step 3.ATC 3. IF VCT Outlet valve does NOT close,THEN verify BAM Pumps Emergency Boration flowpath selected.Examiner Note: 2P-39B breaker will trip when the pump is startedand 2P-39A is not available due to the line up for acid reducingchemistry. Emergency boration can not be completed and should bereported to the SRO.Examiner note: SRO may discuss Shutdown margin Tech Spec 3.1.1.1 due to one CEAwithdrawn and inability to emergency borate. One CEA can be withdrawn withoutemergency boration and meet shutdown margin (SDM).Cue: If contacted as the AO to open 2CVC-40A (2P-39A discharge valve), then report that it isstuck closed and will not open.Cue: If contacted as the WCO to locally close 2CV-4873-1 VCT outlet valve, then delay locallyclosing the valve until after Functional recovery procedure has been entered.VitalAuxiliariessafetyfunction BOP 4.Check Maintenance of Vital Auxiliaries satisfied:A. Main Turbine tripped.B. Generator Output breakers open.C. Exciter Field breaker open.D. At least ONE 6900v AC bus energizedE. At least ONE 4160v Non-vital AC bus energized.F. BOTH 4160v Vital AC buses energized.G. BOTH DGs secured.H. At least ONE 125v Vital DC bus energized:2D01 - SPDS point E2D012D02 - SPDS point E2D02 Appendix D Scenario 2Form ES-D-2Revision 1Page 15 of 26

______Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6Event

Description:

'A' Steam Generator MSIV 2CV-1010-1 fails closed.Then 2 minutes after trip anExcess Steam Demand outside containment commences. Control Element Assembly #38 remains fullywithdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactortrips.TimePositionApplicant's Actions or Behavior RCSInventoryControlSafetyfunctionATC 5.Check RCS Inventory Control established as follows:A. PZR level:10 to 80%.Trending to setpoint.(May not be met due to ESD Event#5 perform contingency if not met)B. RCS MTS 30°F or greater.

SROExaminers Note: This may or may not be performed depending on thePZR level trend at the time this safety function isassessed.Direct the following as necessary:A. Perform as necessary:

1) IF SIAS actuated on PPS inserts, THEN GO TOStep 6.2) Verify PZR Level Control system restoring level to setpoint.ATC 6.Check RCS Pressure Control:1800 to 2250 psia.Trending to setpoint

. (May not be met due to ESD Event #5.Perform contingency if not met)

RCSPressureControlSafetyfunction SROExaminers Note: This may or may not be performed depending on thePZR level trend at the time this safety function isassessed.Direct the following actions as necessary:

6.Perform as necessary:A. IF RCS pressure lowers to less than 1400 psia,THEN trip ONE RCP in EACH loop.

B. IF NPSH requirements violated ORRCS MTS less than 30°F,THEN verify ALL RCPs tripped.D. IF RCP 2P32A or 2P32B stopped,THEN verify associated PZR Spray valve in MANUAL andclosed.E. IF RCS pressure lowers to 1650 psia or less,THEN perform the following:1) Verify SIAS actuated on PPS inserts.

2)GO TO Step 7.

Appendix D Scenario 2Form ES-D-2Revision 1Page 16 of 26Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6Event

Description:

'A' Steam Generator MSIV 2CV-1010-1 fails closed.Then 2 minutes after trip anExcess Steam Demand outside containment commences. Control Element Assembly #38 remains fullywithdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactortrips.TimePositionApplicant's Actions or BehaviorF. Verify PZR Pressure Control system restoring pressure tosetpoint.G. IF ALL RCPs stopped AND RCS pressure greater than 2250psia, THEN initiate Aux spray usingAttachment 27, PZR Spray Operation.ATC 7.Check Core Heat Removal by forced circulation:

A.At least ONE RCP running.B. CCW flow aligned to RCPs

.C. Loop delta T less than 10°F.D. RCS MTS 30°F or greater.E. Check SW aligned to CCW

.(May not be aligned and shouldperform contingency)F. IF SIAS or MSIS actuated,THEN maintain SW header pressure greater than 85 psig.

SROIf required, direct the contingency for step 7. ECore HeatRemovalsafetyfunction.BOPE. IF CCW available,THEN restore SW to CCW, refer to 2202.010 Exhibit 5,CCW/ACW/SW Alignment.

Appendix D Scenario 2Form ES-D-2Revision 1Page 17 of 26Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6Event

Description:

'A' Steam Generator MSIV 2CV-1010-1 fails closed.Then 2 minutes after trip anExcess Steam Demand outside containment commences. Control Element Assembly #38 remains fullywithdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactortrips.TimePositionApplicant's Actions or BehaviorANY 8.Check RCS Heat Removal:A. Check SG available by BOTH of the following:At least ONE SG level 10 to 90%.FW maintaining SG level.(Should not be met due toMSIS, perform contingency if necessary)B. Check MFW in RTO.(Should not be met due to MSIS,perform contingency if necessary)C. Check Feedwater line intact by the following:SG level stable or rising.NO unexplained step changes or erratic FW flow.NO unexplained step changes or erratic Condensate flow.D. Check Condensate Pump discharge header pressure < 753 psig.E. Check SG pressure 950 to 1050 psia.(Not Met, performContingency)F. Check RCS TC 540 to 555°F.ANYPerform step 8 contingency actions that are applicable:A. Perform the following:

1)IF SG level lowering,THEN verify EFAS actuated.(To the 'B' S/G only)ANYB. Verify EITHER of the following:BOTH MFW pumps tripped.SG levels controlling at setpoint Appendix D Scenario 2Form ES-D-2Revision 1Page 18 of 26Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6Event

Description:

'A' Steam Generator MSIV 2CV-1010-1 fails closed.Then 2 minutes after trip anExcess Steam Demand outside containment commences. Control Element Assembly #38 remains fullywithdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactortrips.TimePositionApplicant's Actions or BehaviorANYE. Perform as necessary:

1) IF SG pressure 751 psia or less, THEN perform thefollowing:a) Verify MSIS actuated onPPS inserts.b) Maintain RCS post-cooldown conditions as follows:Maintain RCS pressure within P-T limits with PZRheaters and spray usingAttachment 27, PZR Spray Operation.Maintain RCS temperature by steaming intact SGusing Upstream ADV or Upstream ADV IsolationMOV.c)GO TO Step 9.

Appendix D Scenario 2Form ES-D-2Revision 1Page 19 of 26Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6Event

Description:

'A' Steam Generator MSIV 2CV-1010-1 fails closed.Then 2 minutes after trip anExcess Steam Demand outside containment commences. Control Element Assembly #38 remains fullywithdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactortrips.TimePositionApplicant's Actions or Behavior 9.Check CNTMT parameters:A. Temperature and Pressure:Temperature less than 140°F.Pressure less than 16 psia.B. Check CNTMT Spray pumps secured.C. NO CNTMT radiation alarms or unexplained rise in activity:1) CAMS alarms:"CNTMT PART/GAS RAD HI/LO" annunciator(2K10-B6) clear.2) RCS leakage alarms:"AREA RADIATION HI/LO" annunciator (2K11-B10)clear."PROC LIQUID RADIATION HI/LO" annunciator(2K11-C10) clear.3) Check the following radiation monitors trend stable:CNTMT AreaMSProcess LiquidD. NO secondary system radiation alarms or unexplained rise inactivity: 1) "SEC SYS RADIATION HI" annunciator (2K11-A10)clear.2) Secondary Systems Radiation monitors trend stable:Main Steam linesSG SampleCondenser Off Gas SRO10. Notify STA to report to control room.11. Verify NLOs informed of Reactor trip.12. Verify Reactor trip announced on Plant page.13. Notify SM to refer to Technical Specifications and 1903.010,Emergency Action Level Classification.

Appendix D Scenario 2Form ES-D-2Revision 1Page 20 of 26Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6Event

Description:

'A' Steam Generator MSIV 2CV-1010-1 fails closed.Then 2 minutes after trip anExcess Steam Demand outside containment commences. Control Element Assembly #38 remains fullywithdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactortrips.TimePositionApplicant's Actions or Behavior SRO14. Direct control board operators to acknowledge ALL annunciatorsand announce ALL significant alarms.

SRO15. Check ALL safety function acceptance criteria satisfied.(All safetyfunctions are not satisfied, perform contingency)15. IF ANY safety function acceptance criteria NOT satisfied,THEN perform the following:A. Notify control room staff ofsafety functions NOT satisfied.B. GO TO Exhibit 8,Diagnostic Actions.

SRODiagnose Functional Recovery EOP 2202.009.

SROEnter and implement Functional Recovery EOP 2202.009.

SRO2. Record present time:Time .

SRO* 3. Notify SM to refer toTechnical Specifications and 1903.010,Emergency Action Level Classification.ANY* 4. Check RCS pressure greater than 1400 psia.ANYIf not performed in SPTA's, Then perform contingency to secure 2 RCPs* 4. Perform the following:A. IF RCS pressure less than 1400 psia, THEN perform thefollowing:1) Verify maximum of ONE RCP running in EACH loop.

2) IF RCP 2P32A or 2P32B stopped, THEN verify associatedPZR Spray valve in MANUAL and closed.Examiner Note:The SRO may have directed the ATC and BOP actions for maintaining post-cooldownconditions from SPTAs and therefore may not implement the following floating step.

SROShould pull up the floating step for maintain post-cooldown conditions.HR-2 Step 33.

Appendix D Scenario 2Form ES-D-2Revision 1Page 21 of 26Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6Event

Description:

'A' Steam Generator MSIV 2CV-1010-1 fails closed.Then 2 minutes after trip anExcess Steam Demand outside containment commences. Control Element Assembly #38 remains fullywithdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactortrips.TimePositionApplicant's Actions or BehaviorMaintainpost-cooldownconditions CRITICAL STEP BOP33. Maintain RCS post-cooldown conditions as follows:A. Maintain RCS temperature by steaming intact SG usingEITHER of the following:Upstream ADV.Upstream ADV Isolation MOV.RCS temperature must be maintained within 30°F of 'A' SteamGenerator Tc when generator boiled dry.Maintainpost-cooldownconditions CRITICAL STEPATCB. Maintain RCS pressure within P-T limits using PZR heaters and2202.010 Attachment 27, PZR Spray Operation.Maintain Post steam generator blow down pressure using attachment27 within the Pressure-Temperature limits of 200°F and 30°F.ANY* 5. IF SIAS or MSIS actuated,THEN perform the following:A. Verify at least ONE SW pump running on EACH loop.ANYB. Check EITHER DG running.ANYC. Verify running DG SW Outlet valve open:-1503-1-1504-2ANYD. Verify SW pump suction aligned to Lake.ANYE. Check 4160v Non-vital bus 2A1 OR 2A2 energized from offsitepower.ANYF. Check 4160v Vital buses2A3 AND 2A4 energized from offsite power.ANYG. Start SW pumps as needed to maintain SW header pressure.ANYH. Check SW to CCW restored.ANYI. Check ACW restored.(ACW is not restored, performcontingency)

BOPI. Restore SW to ACW, refer to 2202.010 Exhibit 5,CCW/ACW/SW Alignment.ANYJ. Maintain SW header pressure greater than 85 psig.ANY6. Notify Chemistry to sample BOTH SGs for activity.ANY7. Verify SG Sample valves open.

Appendix D Scenario 2Form ES-D-2Revision 1Page 22 of 26Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6Event

Description:

'A' Steam Generator MSIV 2CV-1010-1 fails closed.Then 2 minutes after trip anExcess Steam Demand outside containment commences. Control Element Assembly #38 remains fullywithdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactortrips.TimePositionApplicant's Actions or BehaviorANY8. Check ALL available Hydrogen Analyzers in service, refer to2104.044, Containment Hydrogen Control Operations - Exhibit 1,Hydrogen Analyzer Auto Start.(perform contingency)ANY8. Verify all available Hydrogen Analyzers in service within 70minutes from start of event.Record time fromEntry Section step 2:Time ______________Examiner note: This step may not be performed due to70 minuteallowance for start.ANY9. Open Functional Recovery Success Path Tracking page.

SRO 10.Notify Control Board Operators to perform the following:A. Monitor floating steps.B. Verify actuated ESFAS componentsusing 2202.010 Exhibit 9,ESFAS Actuation.ANY 11.Determine safety function status as follows:A. Check Reactivity Control satisfied by EITHER of the following:Maximum of ONE CEA NOT fully inserted and Reactor powerlowering.Reactor power less than 10-1% and stable or lowering.Examiners note: Reactivity will be satisfied.ANYB. Check Vital DC Auxiliaries satisfied:1) At least ONE 125v Vital DC bus energized:2D01-SPDS point E2D012D02-SPDS point E2D022) At least ONE 120v Vital AC bus energized:2RS1 - SPDS point E2RS1 or E2RS1RS32RS2 - SPDS point E2RS2 or E2RS2RS42RS3 - SPDS point E2RS3 or E2RS1RS3 Appendix D Scenario 2Form ES-D-2Revision 1Page 23 of 26Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6Event

Description:

'A' Steam Generator MSIV 2CV-1010-1 fails closed.Then 2 minutes after trip anExcess Steam Demand outside containment commences. Control Element Assembly #38 remains fullywithdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactortrips.TimePositionApplicant's Actions or Behavior2RS4 - SPDS point E2RS4 or E2RS2RS4ANYC. Check Vital AC Auxiliaries satisfied:1) At least ONE 4160v Vital AC bus (2A3/2A4) energized.ANYD. Check RCS Inventory Control satisfied:1) CVCS maintaining PZR level10 to 80% [40 to 70%] andlevel stable or trending to setpoint.2) RCS MTS 30°F or greater.3) RVLMS LVL 03 or higher elevation indicates WET.ANYE. Check RCS Pressure Control satisfied:1) RCS pressure maintained withinP-T limits, refer toAttachment 1, P-T Limits.ANYF. Check RCS and Core Heat Removal satisfied:1) At least ONE intact SG available for Heat Removal byEITHER of the following:Level 10 to 90% [20 to 90%] with FW available.Level being restored with total FW flow of 485 gpm orgreater.2) IF ANY RCP operating, THEN RCST less than 10°F and NOT rising.3) IF ALL RCPs secured, THEN RCST less than 50°F and NOT rising.4) RCS T C less than 555°F and NOT rising.5) RCS MTS 30°F or greater.6) RVLMS LVL 01 indicates WET.

Appendix D Scenario 2Form ES-D-2Revision 1Page 24 of 26Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6Event

Description:

'A' Steam Generator MSIV 2CV-1010-1 fails closed.Then 2 minutes after trip anExcess Steam Demand outside containment commences. Control Element Assembly #38 remains fullywithdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactortrips.TimePositionApplicant's Actions or BehaviorANYG. Check CNTMT Isolation satisfied:1) CNTMT parameters normal:a) "CNTMT RADIATION HI" annunciator (2K10-A6)clear.b) NO unexplained rise in CNTMT radiation.c) CNTMT pressure less than18.3 psia.2) "SEC SYS RADIATION HI" annunciator (2K11-A10)clear.3) NO unexplained rise in Secondary Systems Radiationmonitor trends:Main Steam linesSG SampleCondenser Off GasANYH. Check CNTMT Temperature and Pressure Control satisfied:1) CNTMT pressure less than 16 psia.2) CNTMT temperature less than 140°F.ANY12. Locally remove danger tags and close the following breakers.2B51-E4 "LTOP RELIEF ISOL2CV-4730-1"2B51-K2 "LTOP RELIEF ISOL2CV-4741-1"ANY*13. Check ALL Safety Function acceptance criteria satisfied.

Appendix D Scenario 2Form ES-D-2Revision 1Page 25 of 26Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6Event

Description:

'A' Steam Generator MSIV 2CV-1010-1 fails closed.Then 2 minutes after trip anExcess Steam Demand outside containment commences. Control Element Assembly #38 remains fullywithdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactortrips.TimePositionApplicant's Actions or Behavior SRO*13. Perform the following:A. Determine appropriate success paths using Success PathDecision Trees.B. Initiate success paths for ALL Safety Functions in the followingorder:1) Jeopardized.2) Challenged.3) Satisfied.

C. IF higher priority Safety Function jeopardized AND lowerpriority safety function success path in progress, THEN GO TOappropriate success path for highest priority safety function injeopardy.D. WHEN success path implemented for EACH Safety Function,THEN RETURN TO Step 14 ofEntry procedure.Examiner Note: The SRO should complete the safety functions in order of hierarchy that arechallenged first, and then the satisfied safety functions.Examiner Note: The SRO may discuss Tech Spec 3.4.1.2 RCS loops and 3.4.9.1 RCS cooldownlimits to due the excess steam demand event.Termination criteria: When post-cooldown conditions have been stabilized and safety functionsprioritized or at examiner's discretion.

Appendix D Scenario 2Form ES-D-2Revision 1Page 26 of 26Op-Test No.: 1 Scenario No.: 2 Event No.: 7Event

Description:

Green train Containment coolers fail to automatically or manually actuate.TimePositionApplicant's Actions or BehaviorANYRecognize the Green train Containment coolers failed to automaticallyactuate.SRODirect the CBOT to manually align the Green train Containment Coolersto the emergency mode using OP-2202.010 Standard Attachment, Exhibit 9 BOPPerform the following to align the Green train Containment Coolers to theemergency mode:

3.0 IF CCAS, THEN verify the following:Red Train CNTMT Coolers in service.Service Water aligned to Red Train CNTMT Coolers.Red Train Bypass Dampers open.Green Train CNTMT Coolers in service.Service Water aligned to Green Train CNTMT Coolers.Green Train Bypass Dampers open.Examiner note: The SRO may discuss Tech Spec 3.3.2.1 ESFAS and 3.6.2.3 ContainmentCooling due to the failure to automatically actuate.Termination criteria: Green train Containment Coolers aligned IAW 2202.010 Exhibit 9 or atexaminer's discretion.

Appendix D Scenario 3Form ES-D-1Revision 1Page 1 of 27Facility: ANO-2Scenario No.: 3 (Modified)Op-Test No.: 2009-1Examiners:Operators:Initial Conditions:~60% MOL, Condenser outer waterboxes placed in service after tube plugging. All Engineered SafetyFeatures systems are in standby. 2PCV-0231 jacked closed. RED Train Maintenance Week.Turnover:~60% power Condenser outer waterboxes placed in service after tube plugging. 260 EFPD. EOOSindicates 'Minimal Risk'. 2PCV-0231 jacked closed, manually control seal steam pressure. RED TrainMaintenance Week. The previous shift has completed steps 10.1.1 through 10.1.6 and section 10.2 ofstarting the second heater drain pump and 'B' Heater drain pump needs to be placed in service. 2Condensate pumps are running with Condensate recirculation valves in manual.Commence power escalation using applicable 2104.002 step 9.1 through 9.11 are complete and steps9.13 to 9.18 and 9.20 to 9.28 are not applicable or complete. Reactor engineering recommends a 12%per hour rate.EventNo.Malf. No.EventType*EventDescription 1(New)N (SRO)R (ATC)Power escalation following a forced outage.

2(New)N (BOP)N (SRO)Place the 'B' Heater Drain pump in service.

3NIBLINEPWR(Modified)

I (BOP)I (SRO)'B' channel nuclear instrument fails high. Tech Spec forSRO.4XRCCHBPCNT(New)I (ATC)I (SRO)'B' Pressurizer control channel pressure fails high.

5SGBTUBE(Modified)M (ALL)'B' Steam Generator tube leakage ramps up to 275 gpmover 25 minutes. Manual reactor trip criteria whengreater than 44 gpm. Tech Spec for SRO 6RPSRXMANRPSRXAUTO(New)C (ATC)C (SRO)Failure of the reactor protection system to automaticallyor manually trip the reactor.

7 OP5130OP5134 (New)C (BOP)C (SRO)Generator output breakers fail to open automatically 8CNDVACPPA CND2C5BC (BOP)C (SRO)2C-5A Vacuum pump trip2C-5B Vacuum pump fails to auto start.* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajorTotal malfunctions. = 6, Malfunctions. after EOP entry = 2, Abnormal events = 2, Major transient = 1,EOPs with substantive actions =1, EOP Contingencies = 0, Critical tasks = 3.

Appendix D Scenario 3Form ES-D-1Revision 1Page 2 of 27Scenario #3 Objectives 1)Evaluate individual ability to perform a power escalation.

2)Evaluate individual ability to place the second heater drain pump in service.

3)Evaluate individual response to a failure of a Nuclear Instrumentation channel.

4)Evaluate individual response to a failure of a Pressurizer pressure control channel.

5)Evaluate individual response to a steam generator tube rupture.

6)Evaluate individual response to a failure of a RPS to manually or automatically trip the reactor.

7)Evaluate individual response to the generator output breakers failure to automatically open.

8)Evaluate individual ability to mitigate a steam generator tube rupture.

9)Evaluate individual response to a vacuum pump trip.

10)Evaluate individual response to a failure to the backup vacuum pump to auto start.

SCENARIO #3 NARRATIVESimulator session begins with the plant at approximately60% power and the Condenser outerwaterboxes have been placed back in service after tube plugging. Gland seal regulator, 2PCV0231 isjacked closed. The previous shift has completed steps 10.1.1 through 10.1.6 of OP-2106.016(Condensate and Feedwater operations) for placing the 'B' Heater Drain pump in service.When the crew has completed their control room walk down and brief, the ATC will commence apower escalation and the BOP will place the 'B' Heater drain pump in service.After the 'B' Heater Drain pump is placed in service, the ATC has completed all required reactivitymanipulations or cued by lead examiner, 'B' nuclear instrumentation channel will fail high. Thiswill result in a PPS channel trip and pre-trip, CPC sensor failure alarms and the NI linear and logpower instruments on 'B' channel failing to High. The SRO will enter the Nuclear InstrumentMalfunction AOP, AOP 2203.026. The SRO will direct the BOP to bypass points 1, 2, 3, and 4 on'B' PPS. TS 3.3.1.1 and 3.3.3.5 will be entered due to the excore failure.After the BOP has bypassed points 1, 2, 3, and 4 on 'B' PPS or cued by lead examiner, the 'B'channel Pressurizer (PZR) control channel will fail high. This will result in both main spray valvesto automatically open and both proportional heater banks to go to minimum fire. Actual PZRpressure will drop and will result in an automatic reactor trip, if actions are not taken to mitigate theevent. The SRO will enter Abnormal operating procedure OP 2203.028, PZR systems malfunctions.The SRO will direct selecting the opposite control channel.After the Crew has taken all actions of OP 2203.028 PZR systems malfunctions or cued by leadexaminer, a primary to secondary leak will start. The SRO will enter the primary to secondaryleakage AOP, OP 2203.038. ATC and BOP will perform RCS Leak rate determinations. The SROwill enter Tech Spec 3.4.6.2. The SRO will direct the NLO's to control secondary contaminationusing standard attachment 19 and direct the chemists to sample the SG's for activity. When thecrew has determined that the primary to secondary leak is greater than 44 gpm, the ATC will tripthe reactor.

Appendix D Scenario 3Form ES-D-1Revision 1Page 3 of 27SCENARIO #3 NARRATIVE (continued)When the ATC attempts to manually trip the reactor RPS will not work and the SRO will direct theATC to trip the reactor using the DSS system. The Crew will implement Standard Post Trip Actions(SPTA), OP 2202.001. During SPTAs the generator output breakers will fail to automatically openand require the BOP to manually open the breakers. The Crew should actuate safety injection(SIAS) and containment cooling actuation signal (CCAS) or verified that SIAS and CCASautomatically actuates. The Crew will lower Steam Dump master controller set point duringSPTAs to aid in maintaining margin to saturation. The ATC will secure two Reactor coolantPumps when RCS pressure goes below 1400 psia.The SRO will diagnose a Steam Generator Tube Rupture event and enter OP 2202.004, SteamGenerator Tube Rupture. The ATC will cool down the RCS to less than 535°F using the bypassvalves to the condenser. The BOP will override SW to CCW and ACW. The BOP will isolate the'B' SG using standard attachment 10 when RCS Thot is less than 535°F.After the EOP is entered, the RCS cooldown is started and at the lead examiner's discretion, 'A'vacuum pump will trip and 'B' vacuum pump will NOT automatically start. The BOP willmanually start 'B' vacuum pump. If this vacuum pump is not started, the SDBCS bypass valveswill close and the crew will have to steam the ruptured SG to atmosphere resulting in an off siteradiological release.

Appendix D Scenario 3Form ES-D-1Revision 1Page 4 of 27Simulator Instructions for Scenario 3Reset simulator to MOL ~60% power IC stead state.Ensure that AACG is secured and annunciators clear.Place MINIMAL RISK and RED Train Maintenance Week signs on 2C11.Swing ESF equipment aligned to the RED train.2PCV0231, Gland sealing steam pressure control valve failed closed.T1, T2, T3, T4, set to false.EventNo.Malf. No.Value/RampTimeEventDescription 1No malfunctions inserted in event #1.

2No malfunctions inserted in event #2.

3NIBLINEPWRTrigger = T1, 200B' channel nuclear instrument fails high. Tech Spec forSRO.4XRCCHBPCNTTrigger = T2, 2500 /Ramp =30 sec'B' Pressurizer control channel pressure fails high.

5SGBTUBETrigger = T3Value =275gpmRamp =25 min.'B' Steam Generator tube leakage ramps up to 275 gpmover 25 minutes. Manual reactor trip criteria when greaterthan 44 gpm. Tech Spec for SRO 6RPSRXMANRPSRXAUTOTRUE Failure of the reactor protection system to automaticallyor manually trip the reactor.

7 OP5130 OP5134 NO_AUTO_OPENGenerator output breakers fail to open automatically 8CNDVACPPA CND2C5BTrigger = T4 True2C-5A Vacuum pump trip2C-5B Vacuum pump fails to auto start.

Appendix D Scenario 3Form ES-D-1Revision 1Page 5 of 27Simulator Operator CUEsAt T=0Power escalation following a forced outage.At T=0Place the 'B' Heater Drain pump in service.Cue: If contacted as the AO then report section 10.2 2P-8A/B Seal Water Pressure ControllerOperation is complete.Cue: If contacted as the AO then report pre-start check are satisfactory for the 'B' Heater DrainPump.Cued byleadexaminerTrigger T1'B' channel nuclear instrument fails high. Tech Spec for SRO.Cue: When contacted as the WWM, then report that I & C planner will begin planning work onnuclear instrument.Cued byleadexaminerTrigger T2B' Pressurizer control channel pressure fails high.Cue: When contacted as the WWM, then report that I & C planner will begin planning work onfailed pressure instrument.Cued byleadexaminerTrigger T3'B' Steam Generator tube leakage ramps up to 275 gpm over 25minutes. Manual reactor trip criteria when greater than 44 gpm. TechSpec for SROCue: If contacted as the AO then report after 5 min that the local portions of Attachment 10 for'B' S/G are complete.Cue: If contacted as the AO then report you are commencing Attachment 19 control of secondarycontamination.Failure of the reactor protection system to automatically or manuallytrip the reactor.Generator output breakers fail to open automatically.TriggeredduringSGTR brief.If the brief isdelayed thentriggered 10min afterentering SGTRprocedure.Trigger T42C-5A Vacuum pump trip2C-5B Vacuum pump fails to auto start.Cue: If contacted as the AO then report that 'B' vacuum pump is running satisfactory and 'A'vacuum pump is secured.

Appendix D Scenario 3Form ES-D-2Revision 1Page 6 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 1Event

Description:

Plant power escalation from 60%.TimePositionApplicant's Actions or BehaviorT=0ALLCrew will conduct brief for power increase.

SRODirect applicable actions of OP, 2102.004 Power Operations.ATC9.12 IF NOT specified otherwise by Reactor Engineering,THEN commence raising power using Attachment A of thisprocedure forASI Control and power escalation limits:Commence RCS dilution. [Refer to Chemical Addition (2104.003)]Raise turbine load as necessary to maintain Tref within +/-2°F of program Tave using Exhibit 1, TAVE VS TREF.ANYDirect a NLO to perform the following:* 9.19 Perform the following:Monitor secondary chemistry during power escalationAdjust chemical feed as necessary using Secondary SystemChemical Addition (2106.028).

BOP9.29 WHEN ~ 50-55% power,THEN start second Heater Drain pump (2P-8A/B) usingCondensate and Feedwater Operations (2106.016).Termination criteria: When reactivity manipulations are satisfied or at the discretion of the leadexaminer.

Appendix D Scenario 3Form ES-D-2Revision 1Page 7 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 2Event

Description:

Place the 'B' Heater Drain pump in service starting at step 10.1.7.TimePositionApplicant's Actions or Behavior BOP10.1.7 Verify associated Alarms clear for pump to be started:2T-40A Low Pressure alarm (2K03-F1)2T-40A Low Level alarm (2K03-E1)2T-40B Low Pressure alarm (2K03-F2)2T-40B Low Level alarm (2K03-E2)

BOPNote:For cross-tied 2T-40 Tank operation, Recirc controllers areset up in lead/lag style of operation with Lead Recirccontroller ~ 15% greater than lag. The Dump controllerscan be set up this way if desired.Normal Heater Drain Pump Recirc Controller set points are85% on the Lead controller and 70% on the Lag controller.10.1.8 Place the following valve controllers in desired position (auto ormanual - refer to Attachment J) for Heater Drain Tank Levelcontrol:2T-40A Recirc 2CV-0725 Level controller (2LIC-0812)2T-40B Recirc 2CV-0719 Level controller (2LIC-0826)2T-40A Hi Level Dump to 2E-11B controller(2LIC-0813)2T-40B Hi Level Dump to 2E-11B controller(2LIC-0825)ANY10.1.9 Verify 2P-8A/B Seal Water pressure control established per Step 10.2.Cue: If contacted as the AO then report section 10.2 2P-8A/B Seal Water PressureController Operation is complete.

BOP10.1.10 Verify Heater Drain Tank level 4 ft (~ 94% on RecircIndicator) for selected pump to start.ANY10.1.11 IF pump casing warming performed,THEN verify Step10.1.4 complete.Cue: If contacted as the AO then report pre-start check are satisfactory for the 'B' HeaterDrain Pump.

BOP10.1.12 Start selected Heater Drain pump (2P-8A/B).

BOP10.1.13 Monitor 2T-40 levels on Recirc and HLD controllers.

Appendix D Scenario 3Form ES-D-2Revision 1Page 8 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 2Event

Description:

Place the 'B' Heater Drain pump in service starting at step 10.1.7.TimePositionApplicant's Actions or Behavior BOP10.1.14 Verify the following valves adjust as required to maintain HeaterDrain Tank level:2T-40A Hi Level Dump to 2E-11B (2CV-0813)2T-40B Hi Level Dump to 2E-11B (2CV-0825)2T-40A Recirc (2CV-0725)2T-40B Recirc (2CV-0719) Termination Criteria: When 'B' Heater Drain pump is in service or at lead examiner'sdiscretion.

Appendix D Scenario 3Form ES-D-2Revision 1Page 9 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 3Event

Description:

'B' channel nuclear instrument fails High. Tech Spec for SRO.TimePositionApplicant's Actions or BehaviorCued byleadexaminerANYAnnounce annunciators:2K04-A5 CH B RPS/ESF/PRETRIP/TRIP2K04-B3 PPS Channel TRIP2K04 H4 CPC channel sensor failureANYCrew will recognize that 'B' excore has failed High.

SROEnter and Implement AOP 2203.026, NI malfunction .ANY 1.Check at least TWO Linear Safety channels operable.ANY 2.Check ALL Linear Safety channels operable.(Channel 'B' willnot be operable)

SRO 2.IF ALL Linear Safety channels NOT operable,THEN perform the following:

A.Refer to TS 3.3.1.1,Reactor Protective Instrumentation.Examiner note: SRO must enter Tech Spec 3.3.1.1 action 2 BOP C.IF ONLY ONE channel failed,THEN verify the following trip functions bypassed:Hi Linear Power {1}High LPD {3}Low DNBR {4}

SRO D.GO TO Step 4.ANY 4.Check ALL Log Power channels operable.(Channel 'B' will notbe operable)

SRO 4.IF ALL Log Power channels NOT operable, THEN perform thefollowing:

A.IF Log Power channel #2 failed,THEN refer to TS 3.3.3.5,Remote Shutdown Instrumentation.

B.Refer to TS 3.3.1.1,Reactor Protective Instrumentation.Examiner note: SRO must enter Tech Spec 3.3.3.5 Appendix D Scenario 3Form ES-D-2Revision 1Page 10 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 3Event

Description:

'B' channel nuclear instrument fails High. Tech Spec for SRO.TimePositionApplicant's Actions or Behavior BOP D.IF ONLY ONE Log Power channel failed,AND associated Linear Safety channel failed,THEN verify the following trip functions bypassed:Hi Linear Power {1}Hi Log Power {2}High LPD {3}Low DNBR {4}

SRO 8.Notify I&C of Nuclear Instrument malfunctions.Cue: When contacted as the WWM, then report that I & C planner will begin planningwork on nuclear instrument.Termination criteria: When points 1, 2, 3 and 4 are bypassed on 'B' PPS or at the discretion ofthe lead examiner.

Appendix D Scenario 3Form ES-D-2Revision 1Page 11 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 4Event

Description:

Pressurizer control channel pressure fails high.TimePositionApplicant's Actions or BehaviorCued byleadexaminerANYAnnounce annunciator 2K10-E7 Pressurizer Pressure Control Channel 2Pressure HI / LO alarm is due to High pressure.ANYDetermine that 'B' control channel pressure has failed high and RCSpressure is actually lowering.

SRODirect the ATC to place 'A' Pressurizer pressure control channel inservice.SROEnter and implement PZR Systems Malfunctions AOP 2203.028.

SRO5. Check "CNTRL CH 1/2 PRESSURE HI/LO" annunciators (2K10-E6/E7) clear

.(Annunciator is not clear, implement contingency)ANY5. Perform the following:A. Compare PZR pressure instruments to determine affectedchannel.ATC C. IF only the selected control channel affected, THEN perform thefollowing:1) Place PZR Pressure Channel Select switch (2HS-4626) tothe unaffected channel.2) Restore PZR Spray valves and Heater control to automatic.ANYE. IF PZR Pressure Control Channel 2 failed, THEN perform thefollowing:1) Verify a maximum of ONE SDBCS 111/2% Bypass ORDownstream ADV Permissive switch in MANUAL:2CV-0302-0306-0301-03052) Verify ALL other SDBCS Bypass and ADV Permissiveswitches in OFF.

SROExit PZR Systems Malfunctions AOP 2203.028. Termination Criteria: PZR pressure control selected to channel A or at lead examiner'sdiscretion.

Appendix D Scenario 3Form ES-D-2Revision 1Page 12 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7Event

Description:

'B' Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manualreactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactorprotection system to automatically or manually trip the reactor and Generator output breakers failure toopen automatically.TimePositionApplicant's Actions or BehaviorCued byleadexaminerANYAnnounce alarmSEC SYS RADIATION HI

.SROEnter and Implement AOP 2203.038, Primary to Secondary leakage.ANY*2.Check PZR level stable or rising.(Not met, performcontingency)ANY*2.Perform the following:

A.Start and stop Charging pumps as necessary to maintainlevel.ANY*3.Check PZR level maintained within 10% of set point.ANY 4.Notify Chemistry to sample Secondary system for activity using1604.013, Measurement of Primary to Secondary Leak Rate.ANYDirect NLO to perform the following:

5.Minimize secondary contamination using 2202.010 Attachment 19,Control of Secondary Contamination.ANY 7.Determine Primary to Secondary leakrate by ANY of thefollowing:Computer RCS LKRT programs. Check PZR level stable and use Charging and Letdownmismatch minus Controlled Bleed Off. Check Letdown isolated and estimate RCS leak rate by totalCharging flow minus Controlled Bleed Off. Chemistry leakrate calculation using 1604.013, Measurement ofPrimary to Secondary Leakage. SG Tube Leak N-16 monitors.Manual leakrate calculation.

Appendix D Scenario 3Form ES-D-2Revision 1Page 13 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7Event

Description:

'B' Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manualreactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactorprotection system to automatically or manually trip the reactor and Generator output breakers failure toopen automatically.TimePositionApplicant's Actions or Behavior SRO*8. Refer to TS 3.4.6.2, Reactor Coolant System Leakage.Examiner note: SRO must enter Tech Spec 3.4.6.2 due to primary tosecondary leakage.ANY 10.Determine leaking SG by ANY of the following:

A.Secondary Systems Radiation Trend recorder: 2RR-1057 B.SG Sample Radiation monitors: 2RITS-5854 2RITS-5864 C.Main Steam Line Radiation monitors: 2RI-1007 2RI-1057 D.SG water sample results.

E.SG Tube Leak N-16 monitors.ANY 11.Check SG Blowdown aligned to SU/BD DI.

SROWhen the Leakrate is determined to be greater than 44 gpm the SRO willdirect the Reactor trip.12. IF RCS leakage greater than 44 gpmAND in Mode 1 OR 2,THEN perform the following:

A.Trip Reactor.

B.GO TO 2202.001, Standard Post Trip Actions.ATCRecognize a failure of manual RPS trip.

CRITICAL STEPATCTrip the Reactor using the DSS pushbutton.Examiner note: DSS trip must be completed within 1 minutes ofrecognition of RPS failure.

SROEnter and implement EOP 2202.001, Standard Post Trip Actions.

Appendix D Scenario 3Form ES-D-2Revision 1Page 14 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7Event

Description:

'B' Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manualreactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactorprotection system to automatically or manually trip the reactor and Generator output breakers failure toopen automatically.TimePositionApplicant's Actions or Behavior SRO 1.Notify Control Board Operators to monitor safety functions usingExhibit 7, CBO Reactor Trip Checklist.

2.Open Safety Function Tracking page.ATC 3.Check Reactivity Control established as follows:A. Reactor power lowering.B. ALL CEAs fully inserted.

BOPManually align Gland Seal Steam using 2CV-0233.

BOP 4.Check Maintenance of Vital Auxiliaries satisfied:A. Main Turbine tripped.B. Generator Output breakers open. (Not met due to event #7,Perform contingency)C. Exciter Field breaker open.D. At least ONE 6900v AC bus energized.E. At least ONE 4160v Non-vital AC bus energized.F. BOTH 4160v Vital AC buses energized.G. BOTH DGs secured.(May be running if SIAS is actuated,contingency is to verify service water outlet valve is open and thewill both be open)H. At least ONE 125v Vital DC bus energized:2D01 - SPDS point E2D012D02 - SPDS point E2D02 BOPB. Open Generator Output breakers: 5130 5134 BOPComplete Post Trip contingencies to align gland seal steam.

Appendix D Scenario 3Form ES-D-2Revision 1Page 15 of 27

______Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7Event

Description:

'B' Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manualreactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactorprotection system to automatically or manually trip the reactor and Generator output breakers failure toopen automatically.TimePositionApplicant's Actions or BehaviorATC 5.Check RCS Inventory Control established as follows:A. PZR level:10 to 80%.Trending to set point.(Not met due to SGTR Event #5,perform contingency)B. RCS MTS 30°F or greater.

SRODirect the following as necessary:A. Perform as necessary:

1) IF SIAS actuated on PPS inserts, THEN GO TOStep 6.2) Verify PZR Level Control system restoring level to setpoint.ATC 6.Check RCS Pressure Control:1800 to 2250 psia.Trending to set point

. (Not met due to SGTR Event #5,perform contingency)

Appendix D Scenario 3Form ES-D-2Revision 1Page 16 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7Event

Description:

'B' Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manualreactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactorprotection system to automatically or manually trip the reactor and Generator output breakers failure toopen automatically.TimePositionApplicant's Actions or Behavior SROExaminers Note: This may or may not be performed depending on thePZR level trend at the time this safety function isassessed.Direct the following actions as necessary:

6.Perform as necessary:A. IF RCS pressure lowers to less than 1400 psia,THEN trip ONE RCP in EACH loop.

B. IF NPSH requirements violated ORRCS MTS less than 30°F,THEN verify ALL RCPs tripped.D. IF RCP 2P32A or 2P32B stopped,THEN verify associated PZR Spray valve in MANUAL andclosed.E. IF RCS pressure lowers to 1650 psia or less,THEN perform the following:1) Verify SIAS actuated on PPS inserts.

2)GO TO Step 7.F. Verify PZR Pressure Control system restoring pressure to setpoint.G. IF ALL RCPs stopped AND RCS pressure greater than 2250psia, THEN initiate Aux spray usingAttachment 27, PZR Spray Operation.ATC 7.Check Core Heat Removal by forced circulation:

B.At least ONE RCP running.B. CCW flow aligned to RCPs

.C. Loop delta T less than 10°F.D. RCS MTS 30°F or greater.E. Check SW aligned to CCW

.(IF SIAS actuated will not bealigned and should perform contingency)F. IF SIAS or MSIS actuated,THEN maintain SW header pressure greater than 85 psig.

Appendix D Scenario 3Form ES-D-2Revision 1Page 17 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7Event

Description:

'B' Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manualreactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactorprotection system to automatically or manually trip the reactor and Generator output breakers failure toopen automatically.TimePositionApplicant's Actions or Behavior SROIf required Direct the contingency for step 7. E BOPE. IF CCW available,THEN restore SW to CCW, refer to 2202.010 Exhibit 5,CCW/ACW/SW Alignment.ANY 8.Check RCS Heat Removal:A. Check SG available by BOTH of the following:At least ONE SG level 10 to 90%.FW maintaining SG levelB. Check MFW in RTO.C. Check Feedwater line intact by the following:SG level stable or rising.NO unexplained step changes or erratic FW flow.NO unexplained step changes or erratic Condensate flow.D. Check Condensate Pump discharge header pressure < 753 psig.(May not be met if manual actions have not already beentaken)E. Check SG pressure 950 to 1050 psia.F. Check RCS TC 540 to 555°F.

Appendix D Scenario 3Form ES-D-2Revision 1Page 18 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7Event

Description:

'B' Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manualreactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactorprotection system to automatically or manually trip the reactor and Generator output breakers failure toopen automatically.TimePositionApplicant's Actions or BehaviorANYPerform step 8 contingency actions that are applicable:

D.Perform EITHER of the following:

1)Throttle Condensate Pump Recirc Valves to maintainpressure:2FIC-0662 for 2CV-06622FIC-0663 for 2CV-0663 2)Depress "R/L" button on tripped MFP Recirc ValveController:2FIC-0735 for 2P-1A2FIC-0742 for 2P-1B Appendix D Scenario 3Form ES-D-2Revision 1Page 19 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7Event

Description:

'B' Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manualreactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactorprotection system to automatically or manually trip the reactor and Generator output breakers failure toopen automatically.TimePositionApplicant's Actions or BehaviorANY 9.Check CNTMT parameters:A. Temperature and Pressure:Temperature less than 140°F.Pressure less than 16 psia.B. Check CNTMT Spray pumps secured.C. NO CNTMT radiation alarms or unexplained rise in activity:1) CAMS alarms:"CNTMT PART/GAS RAD HI/LO" annunciator(2K10-B6) clear.2) RCS leakage alarms:"AREA RADIATION HI/LO" annunciator (2K11-B10)clear."PROC LIQUID RADIATION HI/LO" annunciator(2K11-C10) clear.3) Check the following radiation monitors trend stable:CNTMT AreaMSProcess LiquidD. NO secondary system radiation alarms or unexplained rise inactivity:(Not met due to SGTR Event #5)

1) "SEC SYS RADIATION HI" annunciator (2K11-A10)clear.2) Secondary Systems Radiation monitors trend stable:Main Steam linesSG SampleCondenser Off Gas Appendix D Scenario 3Form ES-D-2Revision 1Page 20 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7Event

Description:

'B' Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manualreactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactorprotection system to automatically or manually trip the reactor and Generator output breakers failure toopen automatically.TimePositionApplicant's Actions or Behavior SRO10. Notify STA to report to control room.11. Verify NLOs informed of Reactor trip.12. Verify Reactor trip announced on Plant page.13. Notify SM to refer to Technical Specifications and 1903.010,Emergency Action Level Classification.

SRO14. Direct control board operators to acknowledge ALL annunciatorsand announce ALL significant alarms.

SRO15. Check ALL safety function acceptance criteria satisfied.(All safetyfunctions are not satisfied, perform contingency)15. IF ANY safety function acceptance criteria NOT satisfied,THEN perform the following:A. Notify control room staff of safety functions NOT satisfied.

B.GO TO Exhibit 8, Diagnostic Actions.

SRODiagnose Steam Generator Tube Rupture EOP 2202.004.

SROEnter and implement Steam Generator Tube Rupture EOP 2202.004.

SRO* 1. Confirm diagnosis of SGTR:A. Check SFSC acceptance criteria satisfied every 15 minutes.B. Refer to 2202.010 Attachment 20,Break Identification Chart.C. Verify SG Sample valves open.D. Notify Chemistry to perform BOTH of the following:SampleBOTH SGs for activity

.Monitor RDACS for off site dose releases

.SRO* 2. Notify SM to refer to Technical Specifications and 1903.010,Emergency Action Level Classification.ANY 4.Verify SIAS and CCAS actuated on PPS inserts.

Appendix D Scenario 3Form ES-D-2Revision 1Page 21 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7Event

Description:

'B' Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manualreactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactorprotection system to automatically or manually trip the reactor and Generator output breakers failure toopen automatically.TimePositionApplicant's Actions or Behavior SRO 5.Notify Control Board Operators to perform the following:A. Monitor floating steps.B. Verify actuated ESFAS components using 2202.010, Exhibit 9,ESFAS Actuation.ANY*6. Check CCW aligned to RCPs.

SROMay elect to pull up the floating step for commencing a cooldown. Step11. It is possible that the SRO will implement step 11 at the same time heimplements step 7.ATC11. Commence RCS cooldown to less than 535°F TH as follows:A. Reset Low SG Pressure set points during cooldown anddepressurization.B. Commence RCS depressurization to maintain RCS MTS 30 to 45°F.C. Monitor cooldown rate as follows:Record RCS T C and PZR temperature using Attachment 8,RCS Cooldown Table.Plot RCS pressure versus RCS T C using 2202.010Attachment 1, P-T Limits every 15 minutes.D. IF ANY RCPs running,THEN initiate RCS cooldown using EITHER of the following:1) SDBCS Bypass valves (condenser available) - mostpreferred.2) SDBCS ADV from intact SG to atmosphere - leastpreferred. IF necessary, THEN supplement with SDBCS ADV fromruptured SG to atmosphere as needed.ANYF. IF SDBCS Bypass valves available for RCS cooldown, THENplace ALL ADV Permissive switches in OFF.

Appendix D Scenario 3Form ES-D-2Revision 1Page 22 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7Event

Description:

'B' Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manualreactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactorprotection system to automatically or manually trip the reactor and Generator output breakers failure toopen automatically.TimePositionApplicant's Actions or Behavior BOPG. Verify EFW or AFW capable of feeding SGs.ANYH. Secure running MFW pump.

BOPI. Close ALL MFW Block valves.ANY7. Restore ESF/Non-ESF systems post-SIAS as follows:A. Verify at least ONE SW pump running on EACH loop.ANYB. Verify DG SW Outlet valves open.ANYC. Verify SW pump suction aligned to Lake.ANYD. Check 4160v Non-vital bus 2A1 or 2A2 energized fromoffsite power.ANYE. Check 4160v Vital buses 2A3 AND 2A4 energized from offsitepower.BOPF. Start SW pumps as needed to maintain SW header pressure.ANYG. Check SW to CCW restored.ANYH. Check ACW restored.(Not met, perform contingency)

BOPH. Restore SW to ACW, refer to 2202.010 Exhibit 5,CCW/ACW/SW Alignment.

BOPI. Maintain SW header pressure greater than 85 psig.ANY*8. Verify Safety Injection flow to RCS as follows:A. Check total HPSI flow acceptable using 2202.010 Exhibit 2,HPSI Flow Curve.B. Check total LPSI flow acceptable using 2202.010 Exhibit 3,LPSI Flow Curve.ANY9. Check RCS pressure greater than 1400 psia.(Not met, performcontingency)

Appendix D Scenario 3Form ES-D-2Revision 1Page 23 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7Event

Description:

'B' Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manualreactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactorprotection system to automatically or manually trip the reactor and Generator output breakers failure toopen automatically.TimePositionApplicant's Actions or BehaviorANY9. Perform the following:A. IF RCS pressure less than 1400 psia, THEN perform thefollowing:1) Verify maximum of ONE RCP running in EACH loop.

2) IF RCP 2P32A or 2P32B stopped, THEN verify associatedPZR Spray valve in MANUAL and closed.

B.IF NPSH requirements violated ORRCS MTS less than 30°F,THEN perform the following:1) Stop ALL RCPs.

3)Verify BOTH PZR Spray valves in MANUAL and closed.ANY10. Check IA pressure greater than 65 psig.ANY*12. Minimize primary to secondary break flow as follows:A. Check ANY RCP running.B. Maintain RCS pressure within the following criteria:Within 100 psia above minimum RCP NPSH requirement,refer to 2202.010 Attachment 1, P-T Limits.Less than 1000 psia as conditions allow.Within 50 psi of ruptured SG pressure as RCP NPSHrequirements allow.Examiners note: The criteria to minimize break flow can not beestablished until HPSI is overridden. Then the crew should establishthese limits.

Appendix D Scenario 3Form ES-D-2Revision 1Page 24 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7Event

Description:

'B' Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manualreactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactorprotection system to automatically or manually trip the reactor and Generator output breakers failure toopen automatically.TimePositionApplicant's Actions or BehaviorANYC. Use EITHER of the following to depressurize RCS:

1)2202.010 Attachment 27, PZR Spray Operation.

2)IF HPSI termination criteria met, THEN cycle Chargingpumps or throttle HPSI flow to lower PZR pressure.ANYD. IF RCS pressure less than ruptured SG pressure,THEN sample RCS Boron concentration every 30 minutes.ANY 13.Determine ruptured SG by comparing ANY of the following:A. Secondary Systems Radiation Trend recorder (2RR-1057).B. Main Steam Line Radiation Monitors:C. SG Sample Radiation Monitors:D. SG Tube Leak N-16 monitor history trends.E. SG levels.1) Level rising faster in ONE SG with similar FW flow ratesand steaming rates in BOTH SGs.2) Rising SG level with ALL FW isolated.F. Steam flow and FW flow prior to Reactor trip.

G.SG water sample results.

H.

Appendix D Scenario 3Form ES-D-2Revision 1Page 25 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7Event

Description:

'B' Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manualreactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactorprotection system to automatically or manually trip the reactor and Generator output breakers failure toopen automatically.TimePositionApplicant's Actions or BehaviorANYDirect the NLO's to perform the following:

14.Minimize secondary contamination by performing BOTH of thefollowing:A. Commence isolation of ruptured SG by performing local actionsONLY of 2202.010 Attachment 10, SG Isolation.B. 2202.010 Attachment 19, Control of Secondary Contamination.Cue: If contacted as the AO then report after 5 min that the local portions of Attachment10 for 'B' S/G are complete.Cue: If contacted as the AO then report you are commencing Attachment 19 control ofsecondary contamination.ANY15. Isolate ruptured SG Steam Supply to EFW pump 2P7A as follows:ANYA. Verify EFW pump 2P7B running.

B.IF 2P7B NOT running, THEN verify AFW pump 2P75 running.C. Stop EFW pump 2P7A:1) Override and close Steam Supply to 2P7A valve(2CV-0340-2).

2)Close Main Steam Supply valve from ruptured SG toEFW pump 2P7A:"SG A TO EMER FW PMP TURB" 2CV-1000-1"SG B TO EMER FW PMP TURB" 2CV-1050-2Examiners note: SRO must enter Tech Spec 3.7.1.2 for EmergencyFeedwater.

Appendix D Scenario 3Form ES-D-2Revision 1Page 26 of 27Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7Event

Description:

'B' Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manualreactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactorprotection system to automatically or manually trip the reactor and Generator output breakers failure toopen automatically.TimePositionApplicant's Actions or Behavior CRITICAL STEPALL 18.Isolate ruptured SG as follows:A. Monitor RCS TH during cooldown with ANY of the following:PMS point T4614PMS point T4714SPDS displayB. WHEN RCS TH less than 535°F,THEN isolate ruptured SG using2202.010 Attachment 10, SG Isolation.C. Maintain ruptured SG less than1050 psia with ONE of the following

MSIV Bypass valveUpstreamADVExaminer note: 2202.010 Attachment 10 must be complete within 30minutes of entering the EOP.Examiners note: SRO may enter Tech Spec 3.4.5 for Steam generator integrity.Termination criteria: RCS Cool down to less than 535°F Th and 'A' SG isolated or at thediscretion of the lead examiner.

Appendix D Scenario 3Form ES-D-2Revision 1Page 27 of 27Op-Test No.: 1 Scenario No.: 3 Event No.: 8Event

Description:

2C-5A Vacuum pump trip and 2C-5B Vacuum pump fails to auto start..TimePositionApplicant's Actions or BehaviorTriggeredduring SGTRbrief.If the briefis delayedthentriggered10 minafterentering SGTRprocedure.ANYAnnounce alarm VACUUM PUMP 2C5A TRIP SROEnter and implement ACA 2203.012C, Annunciator 2K03 correctiveaction.BOP2.1 Verify Vacuum Pump (2C-5B) running properly per CondenserVacuum System (2106.010)

CRITICAL STEP BOPStart the 'B' vacuum pump and dispatch a NLO to verify it is runningproperly.Start the 'B' Vacuum pump prior to a condenser interlock whichwould require steaming to atmosphere.Cue: If contacted as the AO then report that 'B' vacuum pump is running satisfactory and'A' vacuum pump is secured.Termination criteria: When 'B' Vacuum pump has been started or at examiners discretion.