Procedure History Sheet -'ReviewLevel · PGI|rE/NPG Form 69-10733 (09/03/97) Page 4 of 5 Procedure History Sheet-Review Level 'A'3-LICENSING BASIS IMPACT EVALUATIONSCREENUse the applicable

PGSE/NPG Form 69-10733 (09/03/97)Page 1 of 5

Procedure History Sheet -'Review Level 'A'- BASIC INFORMATION ls this procedure being rescinded? Yes No

If revising two or more procedures, enter VARIOUS in procedure no., complete form 69-20083, and attach to this PHS.

PROCEDURE NO. OP 8-8D REV UNIT P 1 P2 H 1<2

REFUELING PREREQUZSITES

2 - CHANGE DETAILS List change details and why they are needed. Identify ARs, LERs, NCRs, etc.INCORPORATED OTSC OF 8/6/97ADDED WORDS TO ATT 8.1, STEP 26, AND ATT 8.2, STEP 17, TO INSURE NEUTRONIC COUPLINGBETWEEN CORE AND DETECTORS. AR A0371129, A0425124, A0371130, AND DCL-97-035.

g Jd/ >]pe y< y trig( /Cr p 2 Zo ~pp7rt'(5 gyp)fZC(p~ f /6 o cP 4'+5

~ ra~I/~ Fu'g/7 nt+5/(-rr spr5p rw l>cAed)

3 - PREPARATION AND REVIEW

Sponsor

Ind. Tech. Reviewer

Surv. Test Coord. (1)

PS (2)

NQS (3)

Print Last NameFARRER

Signature Date

/p- f-P'7i~~zl~r r

H N/A

IN/A

8 N/A

(1) For new or revised STPs that involve a change of intent & other procedures that affect the(2) For administrative procedures.(3) For new Quality Related administrative procedures & revisions that require a change to a Q

surveillance test program.

commitment in PCD.

4 - PSRC REVIEW H N/A ~ Special tests or infrequently performed evolutions (refer to AD13.ID1).~ New heavy load handling procedures/changes to methods & routes used.~ Procedures identified in EDMS, NPG Manual, Volume 01.

Recommend for Approval at Meeting 0:

5 - PROCEDURE APPROVAL

Date:

Designate minimum approval level by checking ONE of the following blocks.

Q PSRC CHAIR (PSRC REVIEWED) P VP, DCPP (IDAPS) Q MANAGER (DLAPS) 8 DIRECTOR (WORK PROCEDURES)

~ "PASRO" PIMS code required to approve STPs, Emergency Plan Implementing and Operations section procedures.~ "PAOTH" PIMS code & TQ1.ID1 qual for position responsible for procedure required to approval all other

procedures.

~ i</~aFor IDAPs affecting the G.O., obtainapproval of the VP,NTS or delegate.

Approval Signatur

Approval Signature

PROCEDURE CONTROL USE ONLY

Date

Date

H N/A

Received Effective Distributed Uploaded CN Sent/By

01057510.DOC 1A 17

9802200i40 9802i3PDR ADQCK 05000275P 'PDR

Reference AD1.lD2 Attachment 7.1

"t

PG8(E/NPG Form 69-10733 (09/03/97)Page 2of 5

Procedure History Sheet - Review Level 'A'

NPG

DCPP

NTS

C&TSTESOTHER

SVP&GMBusiness PlanningBudg & Perf MgmtMgr. NQSNQS Ops & StrategicNQS MaintenanceNQS Engr & ProcureVP&PM, OCPP

Mgr, Site ServicesGeneral ServicesSecurity ServicesEmergency PlanningHealth & SafetyEnvironmental OpsMgr Mnt SvsProcedure ServicesTechnicalMaterial ServicesMechanicalMgr Outage SvsUnit 1 OutageUnit 2 OutageSch & Otg PingProj & Support SvcsMgr Operations SvsOperationsRadiation Prot.ChemistryVP, NTSNucl. Fuel PurchLearn SvsContract SvsSFNPG Support SvsMgr. Design Engr SvcsEngineering Proj.Tech Support SectMgr., NSALLic & Dsgn BasisRegulatory ServicesDCISC/NSOC/PNACMgr Eng SvsNSSS Sys EngScndry Sys EngBOP Sys EngElec/l&C Sys EngSupport Eng

6 - CROSS DISCIPLINE REVIEW(S)Organization

000CI0000CICICI0CI00000CI0CI0CI00ClCl0CICI000CI0ClCl00CI00CI0CICICICICICI

CICIClCICICI0CIClCI0CI0CI00CI0ClCl0CI00CIHCICICI0CICICICICICl00HCICICI00CICICICICICI

AND CHANGE NOTICEChange CDRNotice

Reviewer ResponseRec'd

000CI0CICICICICICICI0CICI0CI0CI0CI0000CI00CICI0000CI00CIH

CommentsResolved

CICICl00CI00CI0CICICICI0ClClCICI0CI0CICICIQ'I

CICI0CI0CIClCI000ElCICIClClCl0CICICI0CI

01057510.DOC 1A 18 Reference AD1.ID2 Attachment 7.1

PG&E/NPG Form 69-10733 (09/03/97)Page 3 of 5

Procedure History Sheet - Review Level 'A'

- PROCEDURE REVISION DURATIONIs this procedure revision permanent? H YES Q NO

If no, indicate expiration date or eventShould the previous revision be reinstated upon expiration of this revision?

Q YES Q NO HN/A

Tracking AR(s)/AE(s)

8 - OTHER AFFECTED PROCEDURES OR DOCUMENTS H N/AIdentify documents to be written, revised, or rescinded due to this procedure/change. List trackingAR(s)/AE(s) unless revisions/rescissions are in progress.

Affected Documents (Write, Revise, Rescind)

9 - PROCEDURE COMMITMENTDATABASE (PCD)

Does any information in the PCD need to be updated or corrected? Q YES HNOIf YES, submit the change in accordance with XI4.ID1 and XI4.ID2 as appropriate.

10 - BIENNIALREVIEWWas this procedure reviewed to determine if other changes were necessary ordesirable.

Q YES H NO

11 - DESIGN CRITERIA MEMORANDA(DCM)Does the procedure conflict with DCM Section 4, "Design Bases" or Section 5, "Surveillance/MaintenanceRequirements" ?

Q YES Q NO HN/AIf YES, contact the responsible Engineer (listed in the DCM folder in EDMS) and refer to CF3.ID2 for furtherguidance. The proposed revision cannot be made until the conflict is resolved.

12 - CHANGE NOTICE (TO BE E-MAILEDTO PROCEDURE USERS) H N/AIf a work procedure, check N/A.Briefly describe how present practices are changed and who is affected. Also, if this information is availableas an electronic file, send it to PSOPROCODCPP.

01057510.DOC 1A 19 Roforonco AD1.ID2 Attachment 7.1

I'4

*

PGI|rE/NPG Form 69-10733 (09/03/97)Page 4 of 5

Procedure History Sheet - Review Level'A'3

- LICENSING BASIS IMPACT EVALUATIONSCREENUse the applicable TS3.ID2 appendices to answer the following questions:

Screening for Determining the Need for Prior Regulatory Agency Approval1. Does the procedure or procedure change involve a change to the Facility Operating

License (OL), including OL Attachments (Technical Specifications, EnvironmentalProtection Plan and Antitrust Conditions?)If "Yes," submit an LAR to the NRC. Do not approve or release the procedure for useuntil the LA is received.

2. Does the PCD contain any commitment to a regulatory agency that must be changedand require notification to that agency?If "Yes," process the change in accordance with XI4.ID2.

3. Does the PCD contain any commitment to a regulatory agency that must be changedand require prior approval from that agency?lf "Yes," do not approve or release the procedure for use until approval is received.

QY HN

QY HN

QY HN

10 CFR 50.59, 10 CFR 50.54(a)(3) and OL Condition 2.C.(5)b/2.C.(4)b. ScreenDoes the procedure or procedure change:

1. Involve a change to the facility design, function or method of performing the function, QY HNas described in any SER, SSER, or the living FSAR Update.

2. Involve a change to system operation or administrative control over plant activities, as QY HNdescribed in any SER, SSER, or the living FSAR Update?

3. Result in a test, experiment, condition or configuration that might affect safeoperation of the plant but was not anticipated, described or evaluated in any SER,SSER, or the living FSAR Update?

QY EN

4. Rely on a vendor safety evaluation that has not been reviewed by the PSRC? QY HN

lf any questions are answered "Yes," complete LBIE Section 1 in accordance with TS3.ID2.

Environmental Protection Screen (TS3.ID2, Appendix 7.3)Does the procedure or procedure change:

1. Involve discharging new effluents or changes to effluents currently discharged to air,fresh water, sea water, or land?

2. Involve a change in: quantity', use, or storage of materials classified as hazardous(including oils) or the generation of hazardous wastes? ("See paragraph 5.4.2 ofTS3.ID2)

3. Result in disturbing land that was previously undisturbed?

4. Alter surface water runoff patterns or amounts?

5. Involve work within the SLO-2 archeotogical site boundary?

QY HN

QY EN

QY HN

QY gNQY E(N

If any questions are answered "Yes," complete LBIE Section 2 in accordance with TS3.ID2.

p4

01057510.DOC 1A 20 Reference AD1.ID2 Anachment 7.1

0

PGEcE/NPG Form 69-10733 (09/03/97)Page 5 of 5

Procedure History Sheet - Review Level'A'3

- (Continued)

Emergency Plan Screen (TS3.ID2, Appendix 7.1)1. Does the Emergency Plan require review on the basis of TS3.ID2, Appendix 7.1?

lf "No," skip the next question and signature.

2. If the answer to the above question was "Yes," does the procedure or procedurechange result in a change to the EP? (See TS3.ID2, paragraph 5.5.4.a)

If "Yes," complete LBIE Section 3 in accordance with TS3.ID2.

If "No," sign and date:

QY EN

QY QN

EMERGENCY PLAN REVIEWER SIGNATURE DATE PRINT LAST NAME

Security Plan Screen (TS3.ID2, Appendix 7.2)1. Do any of the security plans (PSP, SCP, STOP) require review on the basis of

TS3.ID2, Appendix 7.2? If "No," skip the next question and signature.2. If the answer to the above question was "Yes," does the procedure or procedure

change result in a change to a security plan?

If "Yes," complete LBIE Section 4 in accordance with TS3.ID2.

If "No," sign and date

QY E(N

QY QN

SECURITY PLAN REVIEWER SIGNATURE DATE PRINT LAST NAME

REMARKS: Briefly describe how any issues may interface with the licensing basis (documents). For eachScreen Section above having all "No answers, provide the logic for the "No" answers if clarification isrequired. Identify any screen references or attachments.A 10CFR50.59 Safety Evaluation has been performed in PGaE Letter DCL-97-035 aspart of the submittal of the Technical Specification Bases change. PriorRegulatory approval is not required prior to implememtation.

Based upon the above criteria, I have determined that an LBIE Is is not required.SPONSO SIGNA RE DATE/0-P-Pp'RINT LAST NAME

FARRER

Based upon my independent technical review, I concur with the above conclusionINDEPENDENT TECHNICAL REVIEWER SIGNATURE DATE PRINT LAST NAME

01057510.DOC Reference AD1.ID2 Attachment 7.1

c-w

***ISSUED FOR USE BY:PACIFlC GAS AND EI,ECTRIC COMPANYNUCLEARPOWER GENERATIONDIABLOCANYONPOWER PLANTOPERATING PROCEDURE

DATE: EXPIRES:NUMBER OP B-SD

REVISION 27

PAGE 1 OF 3

UNITS

TITLE: REFUELING PREREQUISITES

EFFECTIVE DATEPROCEDURE CLASSIFICATION: QUALITYRELATED

SCOPE

1.2

The purpose of this procedure is to ensure the following:

1.1.1 Readiness of equipment and associated systems to insure a safe andexpeditious refueling operation.

1.1.2 Verification of equipment status and plant conditions prior to and duringrefueling to insure planned conditions are being maintained.

1.1.3 Verification of valve lineup to insure that the boron concentration and volumein the RCS is maintained during refueling.

1.1 4 Identify those activities which must be current prior to and during corealterations (RCCA latching, RCCA unlatching, drag testing, core unloadingand loading).

Those activities which must be completed prior to entering Mode 6 are covered inOP L-6.

2. DISCUSSION

2.1 This procedure establishes or verifies the required system conditions and equipmentoperability as specified by Technical Specification as prerequisites for refueling.Additional administrative conditions set forth by governing plant procedures are alsoincluded to provide a single checklist for determining the readiness of the plant and stafffor refueling operations.

RESPONSIBILITIES

3.1 The responsibility for refueling prerequisites rests with each department within the plantstaff.

3.2 The Shift Foreman (SFM) willhave the overall responsibility for the performance ofthis procedure, including but not limited to the following:

3.2.1 Verification of all refueling prerequisites.

3.2.2 Periodic check off lists.

3.2.3 Valve lineups and plant operation in MODE 6 status.

3.2.4 Coordination, communication, and direction of all refueling activitiesbetween the Control Room and other plant locations.

00307227.DOA 02 i t 0 l02.0122

PACIFIC GAS AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT


NUMBER OP B-SDREVISION 27PAGE 2 OF 3

UNITS 1 AND 2

3.2.5

3.2.6

Continuous updating of the Control Room fuel accountability board and theaccuracy of the other accountability boards.

Continuous monitoring of count rate data during refueling by a licensedoperator.

3.3 Senior Reactor Operator (SRO) in charge of fuel handling shall be responsible for:

3.3.1 Observation and direct supervision of CORE ALTERATIONS. This SROshall have no other concurrent responsibilities during this operation.

3.4 Power Production Engineers (Nuclear) willhave the following responsibilities:

3.4.1 Composition and implementation of the refueling sequence.

3.4.2 Assist the SFM and SRO with coordination, communication and direction ofrefueling activities between the Containment and Fuel Handling Building.

3.4.3 Periodically monitoring the status of all fuel accountability boards.

3.4.4 Interpretation of count rate data and preparation/interpretation of 1/M plots.

3.4.5 Maintenance of current core map.

3.5 The Chemistry and Environmental Operations (CEO) Director shall be responsible forboron concentration sampling of the RCS, Fuel Transfer Canal and Spent Fuel Pool.

3.6 The Radiation Protection Director shall be responsible for all radiation monitoring andhealth physics activities.

3.7 Site Quality Assurance shall be responsible for periodic surveillance to ensurecompliance with this procedure.

None

PRECAUTIONS AND LIMITATIONS

None

00307-27.DOA 02 2 I 0102.0122

PACIFIC GAS AND ELECTRIC COMPANYDIABLOCANYONPOWER PLANT


NUMBER OP BADREVISION 27PAGE 3 OF 3

UNITS 1 AND 2

6. INSTRUCTIONS

6.1 The Refueling Prerequisites Procedure is divided into the following attachments tofacilitate their accomplishment. They consist of checklists and subprocedures some ofwhich are to be considered prerequisites to the actual commencement of refueling.

Attachment 8.1, "Core Unloading Prerequisites Checklist"

6.2

6.3

Attachment 8.2, "Core Loading Prerequisites Checklist"

Responsible Department Director or designee willsign off the prerequisites items inAttachment 8.1 or 8.2.

The SFM willverify each department's sign offon Attachment 8.1 or 8.2.

6.4 Prior to fuel movement, the SFM willverify whether all prerequisites have beencompleted within the required period of time.

6.5 Periodic verification of items required for refueling is accomplished using STP I-1A, B,C, and D (periodic check list) procedures, Attachments 8.1, 8.2, and the plantSTP scheduling program. The SFM shall verify where applicable that prerequisites areretested at the required frequency.

The actual fuel movement sequence is supplied in References 7.1 and 7.2 which willbeissued by Reactor Engineering.

REFERENCES

6.6

7.1

7.2

7.3

8. ATT

Supplement 1 - Unloading Sequence.

Supplement 2 - Loading Sequence.

Supplement 3 - Insert Shuffle Sequence (Spent Fuel Pool).

ACHMENTS

8.1 "Core Unloading Prerequisites Checklist," 11/07/97

8.2 "Core Loading Prerequisites Checklist," 11/07/97

9. RECORDS

D. Farrer

9.1 After Refueling Operations are completed, forward all checklists to SPPE (ReactorEngineering) for entry into RMS.

10. SPONSOR

00307227.DOA 02 3 I OI02.0122

11 7

DIABLOCANYON POWER PLANTOP B-8D

ATTACHMENT8.1 AND

Page I of 7

TITLE: CORE UNLOADINGPREREQUISITES CHECKLIST

ITEMNO. DESCRIPTION

CEO = Chemistry and Environmental TM = Technical Maintenance DirectorOperations DirectorRP = Radiation Protection Director MM = Mechanical Maintenance DirectorNSSS = Engineering Director OP = Operations Director

Prior to RCCA unlatching, verify Items I through 22 are current.

Verify all routine surveillance tests required for MODE 6 operationshown on the Master Surveillance Test Schedule are current.

RESPONSIBLE DEPT REVIEWEDINITIALS/DATE INITIALS/DATE

OP /

5.

Temporary nozzle dams removed, or design and use approved by PSRC. N/A [ ]Applicable portions of the FIIB and Con(ainmcnt have been classifiedas an FME area per AD4.ID6. All cleanliness requirements are ineffect and being monitored by Maintenance Department.

Verify STP M-42 was performed within l00 liours of Rx head removal.

Reactor cavity level indicating system is installed and operable.

After the Refueling Cavity has been filled, initiate an SFMClearance and tag the following valves closed.

a. LWS-91 Refueling Cavity Drain Lineb. LWS-92 Refueling Canal Drain to RCDTc. LWS-IICV-II I Refueling Canal Flushing Valved. The flange downstream of HCV-I I I is installed, or

the filter assembly flange isol valve is CAU fION tagged closed.e. RCS-8032 Leak Detection Return to RCDT.

Verify boron samples from the RCS, Fuel Transfer Canal and SpentFuel Pool when filled are being taken in accordance with frequenciesstated in CAP A-I procedure.

Portable radiation monitor(s) are available for use on the manipulatorcrane and spent fuel pool bridge crane, and a "SPING" continuous airmonitor is located in Containment and the Fuel Handling Building.

OP /

(CONT) MM /

OP /OP /TM /OP /

CEO /

RP

00307227. DOA 02 4 t 0(02.0(22

I I/ 7

OP B-8D (UNITS I AND 2)ATTACHMENT8.1

TITI.E: CORE UNI.OADINGPl<EREQUISITES CI IECKLIST

Page 2 of 7

ITEM DESCRIPTIONNO.

PRIOR TO RESPONSIBLE NEXTCORE ALT. DEPARTMENT VERIFIED (SFM) RETEST DUECOMPLETE INIT./DATE INIT. HOUR/DATE FREQUENCY DATEWITIIIN

(SFM) RETESTCOMPLETED

INIT.HOUR/DATE

10.

TS 3.1.2.3, charging pump,at least one charging pump in theboron injection path of item 12shall be detnonstrated OPERABLE.This can be accomplished byperforming STP P-CCP-11/12 (21/22)or P-PDP-13 (23).

At least one BA transfer pumpshall be demonstrated OPERABLEifonly the flow path throughthe BA transfer pump of item 12is OPERABLE (TS 3.1.2.5.a).This can be accomplished byperforming STP P-BAT-1 I/12 (21/22).

S fP 1-1D, Routine monthlychecks including corealteration items.

92 days

92 days

31 days

OP / 92 days

OP / 92 days

OP / / 31 days See STP I-1D

00307227. DOA 02 5 I 0t02.0t22

11 37

OP 8-8D (UNITS I AND 2)ATTACHMENT8.1

Page 3 of 7

TITLI.': CORE UNLOADINGPREREQUISITES C) IECKLIST

ITEM DESCRIPTIONNO.

PRIOR TOCORE ALT.COMPLETEWITHIN

RESPONSIBLE NEXTDEPARTMENT VERIFIED (SFM) RETEST DUEINIT./DATE INIT. HOUR/DATE FREQUENCY DATE


INIT.HOUR/DATE

12. One of the followingbora(ed water sourcesshall be OPERABLE:

7 days OP / 7 days

13.

14.

a. The BA storage system with:

I) A minimum containedborated water volumeof 2,499 gallons

2) Between 7,000 and7,700 ppmB, and

3) A minimum solutiontemperature of 65'F.(STr I-IC)

b. The refueling water storagetank with: (STP R-20)I) A nllnlnlunl contained

borated water volumeof 50,000 gallons.

2) A minimum boronconcentration of2300 ppm, and

3) A minimum solutiontemperature of 35'F.

STP I-IC, Routine weekly checksincluding core alteration items

Valves verified OPERABLE(STP V-9), or close allcontainment ventilationisolation valves andimplement a Shift Foreman'sclearance on those valves.

7 days

100 hours

OP /

OP /

7 days

7 days

See STP I-1C

See STP I-IC

00307227.DOA 02 6 t 0102.0t22

ll 7

OP B-SD (UNITS I AND 2)ATTACHMENT8.1

TITLE: CORE UNLOADINGPREREQUISITES CI.IECKLIST

Page 4 of 7

ITEM DESCRIPTIONNO.

PRIOR TO RESPONSIBLE NEXTCORE ALT. DEPARTMENT VERIFIED (SFM) RETEST DUECOMPLETE INIT./DATE INIT. HOUR/DATE FREQUENCY DATEWITIIIN


INIT.HOUR/DATE

15. TS 3.9.4 Contaimnentpenetrations:

a. Equipment door closedW/4 bolts minimum.Verified per MP M-45.1.

b. Minimum of one air lockdoor always closedVerified per STP's M-8EIand M-8E2.

Each penetration fromcontainment to outsideatmosphere shall:

I) be closed by valveor flange, or I ]

2) be capable of closingby "auto" CVI valve(This requirement maybe satisfied bycompletion STP V-9.) [ ]

Verify there are no openpathways providing directaccess from the containmentatmosphere to the outsideatmosphere by contactingthe outage manager andobtaining verbalconfirmation of containmentintegrity clearance/Administrative Tag Out andwork restriction programsin effect.

100 hours

100 hours

100 hours

100 hours

MM / / 7 days

OP / 7 days

OP / 7 days

OP / / 7 davs

See STP I-IC

See STP I-IC

See STP I-IC

See STP I-IC

00307227.DOA 02 7 t 0t02.0I22

J7

OP B-8D (UNITS I AND 2)AT'I'ACHMENT8.1

TITI.E: COI<E UNI.OADING I'I<EIREQUISITES CIIECKLIST

Page 5 of 7

ITEMNO.

DESCRIPTIONPRIOR TO RESPONSIBLE NEXTCORE ALT. DEPARTMENT VERIFIED (SFM) RETEST DUECOMPLETE INIT./DATE INIT. HOUR/DATE FREQUENCY DATEWITIIIN


INIT.HOUR/DATE

16.

17.

Verify boron concentrationsin samples taken from theRCS and Fuel Transfer Canalwlien filled are acceptableper STP I-IB.

STP I-1B Routine dailychecklist including corealteration items.

24 hours OP /

72 hours (RCS) OP /

(FTC)OP /

72 hours

24 hours

See STP I-IB

See STP I-IB

18.

19.

20.

21.

STP I-lARoutine shiftchecklist including corealteration items

STI'AA Source Range AnalogChannel Operational test, forchannels to be used (N-31 & N-32)

TS 3.9. 10.2, Verify

level )23 feet aboveirradiated fuel assemblieswitltin Ihe reactor(clev. 126 ft, 6 in).

a. TS 3.9.5 Establishdirect communicationsbetween the control room andthe refueling stations.

b. Test Evacuation Alarm.

12 hours

8 hours

2 hours

1 hour

OP /

TM /or

OP /OP /

OP /

/ 12 hours

7 days

/ ALLTIME

/ 12 hours

See STP I-IA

/See STP I-IB

See STP I-IA

C.O. Logs22. SRO for fuel handling

operations only and licensedRO required for continuousmonitoring of count rate dataduring CORE ALTERATIONS.

RCCA Unlatching Commenced

MODE 6

TIME DATE SFM

OP / / ALLTIME

RCCA Unlatching Completed /TIME DATE SFM

00307227. DOA 02 8 t 0t02.0t22

I I/ 7

OP 8-SD (UNITS I AND 2)ATTACI.IMENT8.1

Page 6 of 7

TITI.E: CORE UNLOADINGPREREQUISITES CI IECKI.IST

ITEMNO.

23.

24.

25.

26.

27.

2S.

30.

Complete OP 11-7:I Attachment 9.2 checklist.

Verify the following is satisfied:

a. Active SFM Admin Clearance exists on the 140'artitionwall locks and 115'oll-up door chains.

b. The Refueling SRO or designee has possession of the keysto the roll-up doors to prevent them from being opened.

Allcritical personnel participating in the core unloading have beenadequately trained for their part in the fuel handling operations.~

Core unloading sequence completed by Reactor Engineering to determineacceptable spent fuel storage locations (TS 3.9. 14.1 and 3.9. 14.3).The fuel movement sequence insures that the core is ncutronically coupledto the two source range detectors to be used.Fuel rack absorber specimen tree located in proper storage rack cell.

Verify that 100 hours have elapsed since the Rx has been shutdown.

Verify with radiation Protection that RCP D-220 Controls are in place(High Rad Areas locked for fuel transfer). Setting the controls too earlymay hinder maintenance activities.

Perform a spot check of the Manipulator Crane indexing after upperinternals removal. Check a minimum of two widely separated corelocations.

24.1

24.2

NOTF.: The breaker for the new fuel elevator has a ShiftForeman adntinistrative clearance to preclude inadvertent use.

A "dry run" of the fuel transfer system and manipulator crane shouldbe made with the dummy assembly ifpossible.

DESCRIPTION

Prior to core unloading, verify Items I through 19 and 23 through 37 are current.

Fuel accountability boards for control of fuel assembly and insertlocations during refueling operations are available for use in theappropriate areas (Sce TS6. ID2).

FIIB Ventilation is OPERABLE as defined in Tech Spec 3.9.12:

RESPONSIBLE DEPT REVIEWED'NITIALS/DATE INITIALS/DATE

NSSS /

OP INSSS I

NSSS /

NSSS I

OP /

OP /

OP /

OP

'S Shift Nuclear Engineering/Operations/Fuel Ilandlcrs00307227.DOA 02 0 I ot02.0122

IIOP 8-8D (UNITS I AND 2)

ATTACHMENT8.1

TITLE: CORE UNLOADINGPREREQUISITES CI I ECKLIST

ITEMNO.

DESCRIPTIONPRIOR TO RESPONSIBLE NEXTUNLOADING. DEPARTMENT VERIFIED (SFM) RETEST DUECOMPLETE INIT./DATE INIT. HOUR/DATE FREQUENCY DATEWITIIIN


INIT.HOUR/DATE

31.

32.

33.

34.

35.

36.

37.

38.

TM MP 4.4-2A, Spent Fuel Poolcrane load cell calibration.

LT 13-2, Spent Fuel PoolTemperature Channel TIC-651Calibration.

STP M-27, Fuel handlinginterlocks.

Verify acceptability of the SFPcooling system status perAttachment 9.5 of OP B-8DSI.

TS 3.9.11, Varffy ~secs fuel realwater level > 24 ft 6 in abovethe top of fuel assemblies in theracks for fuel movement(clev. 137 ft, 8 in).

TS 3.9.10.1, Vcrffy~rcfcclirr~cavit water level >23 feet aboveRx vessel flange and sufttcient forfuel movetnent (elev. 137 ft, 8 in).

a. TS 3.9.5, Establishdirect communicationsbetween the control room andthe refueling stations.


SRO for fuel handling operationsonly and licensed operatorrequired for continuous monitoringof count rate data during COREALTERATIONS.

6 months

31 days

7 days

12 hours

2 hours

2 hours

I hour

MODE 6

TM /

TM /

OP /NSSS /

OP /

OP /

OP /

OP /

6 mo.

92 days

/ N/A

12 hours

ALLTIME

/ ALLTIME

/ ALLTIME

See OP B-8DS I

See STP I-IB

See STP I-IA

C. O. Logs

Core Unloading CommencedTIME DATE SFM

Core Unloading Completed /TIME DATE SFM

00307227. DOA 02 to I 0102.0122

I 7/97

DIABLOCANYON POWER PLANTOP B-8D

ATTACHMENT8.2 AND

Page I of 8

TI'I'I.E: CORE LOADING PREI<EQUISITES CI IECKLIST

ITEMNO. DESCRIPTION

TM = Technical Maintenance DirectorCEO = Chemistry and EnvironmentalOperations DirectorRP = Radiation Protection Director MM = Maintenance DirectorNSSS = Engineering Director OP = Operations Director

Verify all routine surveillance tests required for MODE 6 operationshown on the Master Surveillance Test Schedule are current.

RESPONSIBLE DEPT REVIEWED (SFM)INITIALS/DATE INITIALS/DATE

OP /

7.

8.

Temporary nozzle dan>s removed or design and use approved by PSRC. N/A [ ]

Applicable portions of the FHB and Containment have been classifiedas an FME area per AD4.ID6. Allcleanliness requirements are ineffect and being tnonitored by Maintenance Department.

The lower core internals anti RV Surveillance Capsule Plugs areinstalled in the reactor vcsscl and are ready for fuel placement.

Reactor cavity level indicating system installed and operable.

Nuclear Fuel Inspections OP B-8C and OP B-8F have been completedand all assembly numbers and orientations verified.

Thc movable incorc detector thimbles are witltdrawn.

Verify that the NIS Excore detectors arc fully inserted in towardthe vessel and that the uppermost and lowermost positioning devicelocking pins are engaged.

OP /MM /

(CONT)MM /

(INT) MM /

OP /TM /

NSSS

MM

TM

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/97


Page 2 of 8

TITLE: CORE LOADING PREREQUISITES CI IECKLIST

ITEMNO. DL'SCRIPTION

Aflcr tlic Refueling Cavity has been filled, initiate an SFMClearance and tag the following valves closed.

a. LWS-91 Rcfucling Cavity Drain Lineb. I.WS-92 Refueling Canal Drain to RCDTc. LWS-HCV-II I Refueling Canal I'lushing Valved. The flange downstream of HCV-I I I is installed, or

the filter assembly flange isolation valve is CAUTION tagged closed.e. RCS-8032 Leak Detection Return to RCDT


OP /

IO. Verify boron sarnplcs front the RCS, Fuel Transfer Canal and SpentFuel I'ool are being taken in accordance with frequencies statedin CAP A-I proccdurc.

CEO

00307227. DOA 02 12 I 0t02.0t22

I /97OP B-8D (UNITS I AND 2)

ATTACHMENT8.2

Page 3 of 8

TITLE: CORE LOADING PREREQUISITES CIIECKLIST

ITEM DESCRIPTIONNO.

PRIOR TO RESPONSIBLE NEXTLOADING. DEPARTMENT VERIFIED (SFM) RETEST DUECOMPLETE INIT./DATE INIT. HOUR/DATE FREQUENCY DATEWITIIIN


INIT.HOUR/DATE

12.

13.

TS 3.1.2.3, charging pump, atleast one charging pump in theboron injection path of Item 14shall be demonstrated OPERABLE.Tlds can be accomplished byperforming STP P-CCP-I I/12 (21/22)or P-PDP-13 (23).

At least one BA transfer pumpslral1 be demonstrated OPERABLEifonly the flow path throughthe BA transfer pump of item 14is OPERABLE (TS 3.1.2.5.a). Thiscan be accomplished by performingSTP P-BAT-11/12 (21/22).

STP l-lD, Routine monthly checksincluding core alteration items

92 days

92 days

31 days

OP / / 92 days

OP / /I'1 days

OP / / 92 days

See STP I-ID

00307227. DOA 02 l3 I 0102.0122

I /97

OP 8-8D (UNITS I AND 2)A'ITACI.I MENT 8.2

Page 4 of 8

TITLE: CORE LOADING PREREQUISITES CI IECKI.IST

ITEM DESCRIPTIONNO.

PRIOR TO RESPONSIBLE NEXTLOADING. DEPARTMENT VERIFIED (SFM) RETEST DUECOMPLETE INIT./DATE INIT. HOUR/DATE FREQUENCY DATEWITHIN


INIT.HOUR/DATE

14. One of the following boratedwater sources shall be OPERABLE:

7 days OP / 7 days

a. The BA storage system with:

I) A minimum contained boratedwater volmne of 2,499 gallons

2) Behveen 7,000 and 7,700 ppmB,and

3) A minimum solution temperatureof 65'F. (STP I-IC)

b. The refueling water storage tankwith: (STP R-20)

I) A minimum contained boratedwater volume of 50,000 gallons.

2) A minimum boron concentrationof 2300 ppm, and

3) A tlllllhnulllsolution tcnlpcfatufcof 35'F.

15. STP I-IC, Routine weekly checks 7 daysincluding core alteration items

OP / 7 days See STP I-IC

16. STP R-28, High Flux at Shutdown N/AAlarm setpoint current forMODE 6 and High Flux atShutdown switch on NIS Panelin NORMAL.

OP /

NSSS /

7 days

00307227.t3OA 02 0102.0122

I 7/97


Page 5 of 8

Tl'I'LE: CORE LOADING I'REREQUISITES CI IECKLIST

ITEMNO.

18.

19.

20

21.

DESCRIPTION

Fuel accountability boards for control of fuel assembly and insertlocations during loading operations are available for use in theappropriate areas (See TS6.ID2). The fuel movement sequenceinsures that the core is neutronically coupled to the two sourcerange detectors to be used.

Allcritical personnel participating in the core loading have beenadequately trained for their part in the fuel handling operations.*

Portable radiation monitor(s) are available for use on the manipulatorcrane and spent fuel pool bridge crane and a "SPING" continuousair monitor is located in Containment and the Fuel Handling Building.

An underwater TV camera with video taping capability and adequateunderwater lighting is available for post-loading verification.

FHB Ventilation is OPERABLE as defined in Tech Spec 3.9.12:


NSSS /

NSSS /

RP /

NSSS /

OP / /NSSS / /

21.1

21.2

Complete OP H-7:I Attachment 9.2 checklist.

Verify the following is satisfied:

a. Active SFM Admin Clearance exists on the 140'artitionwall locks and 115'oll-up door chains.

b. The Refueling SRO or designee has possession of the keysto the roll-up doors to prevent them from being opened.

* Shift Nuclear Engineering/Operations/Fuel Handling

00307227.DOA 02 OI02.0I22

I /97


Page 6 of 8

TI'I'l.l.': CORE LOADING PREREQUISITES CI IECKLIST

I' EMNO.

22.

DESCRIPTION

'I'S 3.9 4 Containment

pet tel rations:

a. Equipment door closedhV/4 bolts minimum.Veritted p«r MP M-45.1

b. Minimum of one air lockdoor always closedVerified per STP M-8E

c. Each penetration fromcontainment ttt outsideatmosphere shall:

I) Ie closed by valveor flange, or

2) be capable of closingby "auto" CVI valveMay be satisfied bycompletion of STP V-9).

d. Verify there arc no openpathways providing directaccess from the containmentatmosphere to the outsideatmosphere by contactingthe outage manager andobtaining verbal confirmationof containment integrityclearance/Administrative TagOut, and work restrictionprograms in effect.

100 hours MM / / 7 days

100 hours OP / 7 days

100 hours OP / / 7 days

100 hours OP / 7 days



INIT.HOUR/DATE

See STP I-IC

See STP I-IC

See STP I-IC

See STP I-1C

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/97


Page 7 of 8

TITLE: CORE LOADING PREREQUISITES CI IECKLIST

ITEM DESCRIPTIONNO.

PRIOR TO RESPONSIBLE NEXTLOADING. DEPARTMENT VERIFIED (SFM) RETEST DUECOMPLETE INIT./DATE INIT. HOUR/DATE FREQUENCY DATEWITHIN


INIT.HOUR/DATE

23.

24.

25

26.

27.

Valves verified OPERABLE per(STP V-9), or close allcontainment ventilationisolation valves and implementa Shift Foreman's clearance onthose valves.

Verify boron concentrationsin samples taken from theRCS and Fuel Transfer Canalare acceptable per STP I-lB.

STP I-IB Routine dailychecklist including corealteration items.

STP I-IARoutine shiftchecklist including corealteration items

STP I-4A Nuclear Source RangeAnalog Channel Operationaltest, both channels N-31 & N-32

S I'P 1-4C, Calibration of AudioCount Rate/Sealer 'I'imcr Channel,current (should be performed inconjunction with STP 1-4A).

100 lloufS

24 hours

12 lioui'S

8 hours

N/A

OP / /

(FTC)OP /

OP / /

OP /

TM /ofOP /TM /

7 days

72 hours

24 hours

12 hours

7 days

18 months

See STP I-IC

See STP I-IB

See STP I-IB

See STP I-IA

00307227.t)OA 02 17 I 0102.0122

'I

I /97


Page 8 of 8

Tl I'LE: CORE I OADING PREREQUISITES CI I ECKLIST

ITEM DESCRIPTIONNO.



INIT.HOUR/DATE

29

30.

31.

2 hours

TS 3.9.10.1, Level, verify

>23 feet above Rx vessel flangeand sufficient for fuel movement(elev. 137 ft, & in).

2 hours

TS 3.tt.t I. Verify ~sent fuel nnlwater level > 24 ft 6 in abovethe top of fuel assemblies inthe racks for fuel movement(elcv. 137 ft, & in).

Verily with radiation Protection thatRCP D-220 Controls are in place(1ligh Rad Areas locked for fuel transfer).Setting the controls too early mayhinder maintenance activities.

OP /

OP /OP /

ALLTIME

/ ALLTIME

/ ALLTIME See STP I-IB

32.

33.

a. TS 3.9.5, Communications,establish direct communicationsbetween the control room and therefueling stations.


SRO for refueling operationsonly and licensed operatorrequired for continuousmonitoring of count rate dataduring CORE ALTERATIONS.

I hour

MODE 6

OP /

OP /

/ 12 hours

/ ALLTIME

See STP I-IA

C. O. Logs

Core Loading CommencedTIME DATE SFM

Core Loading CompletedTIME DATE SFM

00307227. DOA 02 ts t Ot02.0122