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| issue date = 09/04/1985
| issue date = 09/04/1985
| title = Rev 8 to Procedure A-25.4, Reactor Post-Trip Review.
| title = Rev 8 to Procedure A-25.4, Reactor Post-Trip Review.
| author name = SPECTOR S N
| author name = Spector S
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| addressee name =  
| addressee name =  
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:GlNNASTAmpgUNlT¹SCOMPtEonOATE:-ROCHESTER GASANDELECTRICCORPORATIO T!IVIE;'GINNASTATIONCONTROLLED COPYNUMBERPROCEDURE NO.JA-25.4REV.NO.8REACTORPOSTTRIPREVIEWTECHNICAL REVIEWPORCREVIEWDATEQOREVIEWPLANTSERINTENDENT EFFECTIVE DATEQA~NON-QACATEGORY1.0REVIEWEDBY:THISPROCEDURE CONTAINS7PAGESS509>00077 S50903'-PDRADOCK,05000244'
{{#Wiki_filter:GlNNA STAmpg UNlT ¹S COMPt Eon OATE:-
."..P.:"",PDR 1i1 A-25':1A-25.4REACTORPOSTTRIPREVIEW1~0PURPOSE:1~2Todefinedutiesandresponsibilities fortheconductofareactorposttripreview.Thisreviewwillbeconducted todetermine thecausesofallunplanned reactortrips(i.e.openingoftripbreakerswithoutallcontrolrodsfullyinserted) atGinnaStation.Todefinethescopeofthereviewandtherecordsthatmustbereviewedtoperformthisassessment.
ROCHESTER GAS AND ELECTRIC CORPORATIO      T!IVIE;
2'
                                    'GINNA STATION CONTROLLED COPY NUMBER PROCEDURE NO. J  A-25.4                        REV. NO. 8 REACTOR POST  TRIP REVIEW TECHNICAL REVIEW PORC REVIEW DATE QO REVIEW                              PLANT S  ERINTENDENT EFFECTIVE DATE QA~     NON-QA            CATEGORY 1.0 REVIEWED BY:
THIS PROCEDURE CONTAINS      7  PAGES S509>00077 S50903'-
.".. P.:     ",PDR PDR "ADOCK,05000244'
 
i 1
1
 
A-25 ':1 A-25.4 REACTOR POST    TRIP REVIEW 1~0      PURPOSE:
To  define duties and responsibilities for the conduct of a reactor post trip review. This review will be conducted to determine the causes of all unplanned reactor trips (i.e. opening of trip breakers without all control rods fully inserted) at Ginna Station.
1~2      To define the scope of the review and the records that must be reviewed to perform this assessment.
2 '    


==REFERENCES:==
==REFERENCES:==


2.12.22'2'2.5FacilityTechnical Specifications A-25"Reporting ofUnusualPlantConditions" A-25.1"GinnaStationEventReport",0-9.3"NRCImmediate Notification" InternalNRCMemoFromR.W.Starostecki,
2.1      Facility Technical Specifications 2.2     A-25 "Reporting   of Unusual Plant Conditions" 2 '      A-25.1 "Ginna Station Event Report" 2 '    ,0-9.3 "NRC  Immediate  Notification" 2.5      Internal  NRC Memo  From R.W. Starostecki, Director, .DPRP
: Director,
 
.DPRP3.0INSTRUCTIONS:
==3.0 INSTRUCTIONS==
3.1ControlRoom0erator3~1~1SubmitanA-25.1,"UnusualEventReport"'.
3.1      Control  Room 0  erator 3~1~1    Submit an A-25.1, "Unusual Event Report"'.
3~1.2InformShiftSupervisor ofunusualconditions orobservations madeduringtheevent.3'ShiftTechnical Advisor3.2.1TheShiftTechnical Advisorshallperformapreliminary assessment oftheevent.Thisshallbedocumented bycompletion oftheattachedPost-Trip ReviewForm.
3 ~ 1.2  Inform Shift Supervisor of unusual conditions or observations  made  during the event.
A-25~423''Uponcompletion oftheform,forwardittotheShiftSupervisor forinclusion withtheA-25.4Review.3.2.3TheShiftTechnical Advisorwillalso,uponrequestoftheShiftSupervisor, assistwiththeShiftSupervisor's assessment.
3 '     Shift Technical Advisor 3.2.1    The Shift Technical Advisor shall perform a preliminary assessment of the event. This shall be documented by completion of the attached Post-Trip Review Form.
3.3OtherPlantPersonnel 3~3~1Anyotherplantpersonnel thatareinvolvedwiththeevent(Auxiliary Operators, I&CTechs,Electricians, etc.)shouldmakethemselves available totheShiftSupervisor toansweranyquestion(s) abouttheirinvolvement intheevent.3'3'.1ShiftSuervisorTheShiftSupervisor istoreviewtheA-25.1report,Operatornotes,theShiftTechnical Advisorsassessment andanyotherinformation available tomakeaprelim-inaryassessment ofthecauseoftheReactorTrip.TheShiftSupervisor maycallupontheShiftTechnical Advisorandanyotherplantpersonnel toassisthiminhisassessment.
 
TheShiftSuperviso'r Assessment andmaterialusedintheassessment willbepassedtotheDutyEngineeraftertheShiftSupervisor completes hisassessment.
A-25 ~ 4 2 3 ' '     Upon  completion of the form, forward  it  to the Shift Supervisor for inclusion with the A-25.4 Review.
3.4.23''.1TheShiftSupervisor shallreviewtheeventandassignoneofthefollowing classifications totheevent.(Markotherclassifications N/A).Condition One-thecauseofthetripispositively known.Allsafety-related andotherimportant equipment functioned properlyduringthetrip.3''.2Condition Two-thecauseofthetripispositively known.Somesafety-related and/orotherimportant equipment functioned inanabnormalordegradedmanner.3.4.2'Condition Three-thecauseofthetripisnotpositively known.
3.2.3    The  Shift Technical Advisor will also, upon request of the Shift Supervisor, assist with the Shift Supervisor's assessment.
A-25.4:33'DutEnineer3~5~1TheDutyEngineershallreviewtheShiftSupervisor's "assessment oftheeve'nt.Ifthecomputerposttripreview'rintout isavailable itshallalsobereview-ed.TheDutyEngineershallmakeanassessment ofthecauseoftheevent.TheDutyEngineershallforwardallmaterials, including hisassessment, tothePlantSuperintendent.
3.3      Other Plant Personnel 3 ~ 3 ~ 1 Any  other plant personnel that are involved with the event (Auxiliary Operators, I&C Techs, Electricians, etc.) should make themselves available to the Shift Supervisor to answer any question(s) about their involvement in the event.
3.5.2TheDutyEngineershallreviewtheeventclassificat-ion.IftheDutyEngineerdoesnotconcurwiththeShiftSupervisor's classification, thePORCwillreviewtheeventandclassifyit.3.6PlantSuerintendent 3.6~1ThePlantSuperintendent shallscheduleameetingofthePlantOperations ReviewCommittee (PORC)withthepurposeofreviewing theevent.3~6.2Alleventsregardless ofclassification shallbereviewedbythePORCandthePlantSuperintendent's permission grantedbeforetheReactormayberestarted.
3 '       Shift Su ervisor 3 '.1    The Shift Supervisor is to review the A-25.1 report, Operator notes, the Shift Technical Advisors assessment and any  other information available to make a prelim-inary assessment of the cause of the Reactor Trip. The Shift Supervisor may call upon the Shift Technical Advisor and any other plant personnel to assist him in his assessment. The Shift Superviso'r Assessment and material used in the assessment will be passed to the Duty Engineer after the Shift Supervisor completes his assessment.
3.6.3Intheeventthatthecauseofthetripispositively knownandallSafetyRelatedequipment functioned
3.4.2    The  Shift Supervisor shall review the event and assign one of the following classifications to the event. (Mark other classifications N/A) .
: properly, thePlantSuperintendent mayauthorize theReactorrestartpriortocompletion ofalltheattachments tothisprocedure.
3 '  '.1 Condition One the cause of the trip is positively known. All safety-related and other important equipment functioned properly during the trip.
3'PORC3.7.1Reportsshallbepresented bySubcommittee Chairmanasidentified onAttachment B.3.7'3''PORCshallreviewtheeventandeitherconcurwiththeassessment presented toitorinitiateitsowninvestigation intothecauseoftheevent.Attachment Cidentifies necessary criteriaforplantrestart.IPORCshalldetermine ifallsafetyorTechSpec.que-stionsareresolved.
3 '   '.2 Condition Two - the cause of the trip is positively known. Some sa fety-related and/or other important equipment functioned in an abnormal or degraded manner.
3.7.4PORCshallrecommend tothePlantSuperintendent whetherornottoallowaReactorrestart.
3.4.2 '   Condition Three - the cause of the          trip is    not positively known.
l A-25.4:43'0erationsManaer3.8~1Operations Managerorhisalternate shallreviewthismaterialandconcurwithPORC'sassessment priortotakingthereactorcritical.
 
3.9Corrective Actions3.9.1Anymemberoftheplantstaffmayinitiatecorrective actionbybringingthemattertotheattention ofplantmanagement ortheShiftSupervisor.
A-25.4:3 3 '       Dut  En  ineer 5~1  The Duty Engineer shall review the Shift Supervisor's 3 ~
3.9'Theplantshallnotbemadecriticalafteratripuntiltheeventhasbeenreviewedandthecauseisknown.4.0RECORDS:4.14.2RecordsofthereviewshallbenotedintheminutesofthePORCmeeting.ThePORCminutesshallbethepermanent recordofthereview.4.3AllmaterialusedinthePostTripReviewshallbeattachedtothisprocedure andforwarded toCentralRecords.COMPLETION DATECOMPLETED BY:OPERATIONS MANAGER:
        "assessment of the eve'nt.
A-25.4:5A-25.4REACTORPOST-TRIPREVIEW(RefertoA-25.4forInstructions)
review'rintout is available Ifit shall the computer post trip also be review-ed. The Duty Engineer    shall make an assessment of the cause of the event. The Duty Engineer shall forward all materials, including his assessment, to the Plant Superintendent.
TIMEOFTRIP:DATE:II.DESCRIPTION OFEVENT:III.ACTIONSPERFORMED BYSTA:a)Procedures referredto:b)Parameters observed:
3.5.2    The Duty Engineer  shall review the event    classificat-ion. If  the Duty Engineer does not concur with the Shift Supervisor's classification, the PORC will review the event and classify it.
c)Recognition/Diagnosis reached:d)AdvicegiventoShiftSupervisor:
3.6      Plant Su erintendent 3.6 ~ 1  The Plant Superintendent shall schedule a meeting of the Plant Operations Review Committee (PORC) with the purpose of reviewing the event.
IV.CAUSEOFEVENT:V.ADDITIONAL COMMENTS:
3 ~ 6.2  All  events regardless of classification shall be reviewed by the PORC and the Plant Superintendent's permission granted before the Reactor may be restarted.
SHIFTTECHNICAL ADVISOR:
: 3. 6.3    In the event that the cause of the trip is positively known and    all Safety Related equipment functioned properly, the Plant Superintendent may authorize the Reactor restart prior to completion of all the attachments to this procedure.
A-25.4:6ATTACHMENT BPORCSUBCOMMITTEE CHAIRMANASSIGNMENTS Evaluation ofSafetTechnical andTech.Sec.uestionsandReviewAainstAlicableInformation fromtheUFSARandPriorTransients Technical Manageralternates:
3 '       PORC 3.7.1    Reports shall be presented by Subcommittee Chairman as  identified on Attachment B.
NuclearEngineerDutyEngineerEvaluation ofEimentMalfunctions andReairPlansMaintenance Manageralternates:
3.7 '     PORC shall review the event and either concur with the assessment presented to it or initiate its own investigation into the cause of the event. Attachment C identifies necessary   criteria for plant restart.
I&CSupervisor Maintenance Supervisor PostTriReviewCauseIdentification A-25.4ReortSummarOperations ManagerPalternates:
I 3  ' '    PORC  shall determine stions are resolved.
Operations Supervisor DutyEngineerStartuPlansandSeuencePlanner A-25':7ATTACHMENT CPORCREVIEWCRITERIA2~3~4~5~6.7~8.Rootcauseofproblem(s) hasbeenidentified.
if all safety  or Tech Spec. que-3.7.4    PORC    shall  recommend  to the Plant Superintendent whether or not to allow a Reactor    restart.
Aclearsequenceofeventshasbeendetermined.
 
Allneartermcorrective actionshavebeentakentoresolvetherootcauseofthetrip.Longtermcorrective actionsareoutlineandamethodfortrackingthemhasbeenestablished.
l A-25.4:4 3 '     0 erations    Mana  er 3.8 ~ 1 Operations Manager or his alternate shall review this material and concur with PORC's assessment prior to taking the reactor critical.
Allmajorsafetysystemsandotherimportant equipment responded properlyortherootcauseoftheproblem(s) foundandcircumstances reviewedtoassurethatnonewpotential safetyconcernswereidentified.
3.9    Corrective Actions 3.9.1  Any member of the plant staff may initiate corrective action by bringing the matter to the attention of plant management or the Shift Supervisor.
Operation ofplantsystemsduringthetripwasconsistent toanyapplicable information providedintheUFSAR.Wherepossible, comparison withprevioussimilareventshasbeenmadeandnounexplained differences inoperation ofplantsystemsoccurred.
3.9 '   The  plant shall not      be made  critical after    a trip until  the event has been reviewed      and  the cause is known.
Failureofanyitemsfromg5shallbecomparedagainstA-25.4reportsandifnecessary equipment historyfilestodetermine ifanyfailuresarerepetitive innatureorinvolvecommonmodefailures.
 
Separatetrackingdocuments maybeinitiated tofollowcorrective actionontheseitems.Items6,7,and8shouldincludetheinformation beingusedforcomparison.}}
==4.0 RECORDS==
4.1    Records  of the review shall    be noted  in the minutes of the  PORC  meeting.
4.2    The  PORC  minutes shall be the permanent record of the review.
4.3    All material      used  in the Post Trip    Review to shall be attached to this procedure and        forwarded      Central Records.
COMPLETION DATE COMPLETED BY:
OPERATIONS MANAGER:
 
A-25.4:5 REACTOR POST  TRIP REVIEW (Refer to A-25.4  for Instructions)
A-25.4 TIME OF TRIP:                       DATE:
II. DESCRIPTION OF EVENT:
III. ACTIONS PERFORMED BY STA:
a)   Procedures referred to:
b)   Parameters observed:
c)   Recognition/Diagnosis reached:
d)   Advice given to  Shift Supervisor:
IV. CAUSE OF EVENT:
V. ADDITIONAL COMMENTS:
SHIFT TECHNICAL ADVISOR:
 
A-25.4:6 ATTACHMENT B PORC SUBCOMMITTEE CHAIRMAN ASSIGNMENTS Evaluation of Safet        Technical and Tech. S  ec. uestions and Review  A  ainst  A  licable Information from the    UFSAR and  Prior Transients Technical Manager            alternates: Nuclear Engineer Duty Engineer Evaluation of  E  i ment  Malfunctions and Re air  Plans Maintenance Manager          alternates: I&C Supervisor Maintenance Supervisor Post  Tri  Review  Cause  Identification A-25.4  Re  ort Summar P
Operations Manager            alternates: Operations Supervisor Duty Engineer Startu  Plans and  Se uence Planner
 
A-25 ':7 ATTACHMENT C PORC REVIEW CRITERIA Root cause  of problem(s) has been identified.
2 ~    A clear sequence of events has been determined.
3 ~    All near term corrective actions have been taken to resolve the root cause of the trip.
4 ~    Long term corrective actions are outline and a method for tracking them has been established.
5 ~    All ma j or sa fety systems and other important equipment responded properly or the root cause of the problem(s) found and circumstances reviewed to assure that no new potential safety concerns were identified.
: 6. Operation of plant systems during the trip was consistent to any applicable information provided in the UFSAR.
7  ~  Where possible, comparison with previous similar events has been made and no unexplained differences in operation of plant systems occurred.
: 8. Failure of any items from g5 shall be compared against A-25.4 reports and if necessary equipment history files to determine if any failures are repetitive in nature or involve common mode failures. Separate tracking documents may be initiated to follow corrective action on these items.
Items 6, 7, and 8 should include the information being used for comparison.}}

Latest revision as of 19:56, 29 October 2019

Rev 8 to Procedure A-25.4, Reactor Post-Trip Review.
ML17254A536
Person / Time
Site: Ginna Constellation icon.png
Issue date: 09/04/1985
From: Spector S
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17254A535 List:
References
A-25.4, NUDOCS 8509100077
Download: ML17254A536 (10)
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Text

GlNNA STAmpg UNlT ¹S COMPt Eon OATE:-

ROCHESTER GAS AND ELECTRIC CORPORATIO T!IVIE;

'GINNA STATION CONTROLLED COPY NUMBER PROCEDURE NO. J A-25.4 REV. NO. 8 REACTOR POST TRIP REVIEW TECHNICAL REVIEW PORC REVIEW DATE QO REVIEW PLANT S ERINTENDENT EFFECTIVE DATE QA~ NON-QA CATEGORY 1.0 REVIEWED BY:

THIS PROCEDURE CONTAINS 7 PAGES S509>00077 S50903'-

.".. P.: ",PDR PDR "ADOCK,05000244'

i 1

1

A-25 ':1 A-25.4 REACTOR POST TRIP REVIEW 1~0 PURPOSE:

To define duties and responsibilities for the conduct of a reactor post trip review. This review will be conducted to determine the causes of all unplanned reactor trips (i.e. opening of trip breakers without all control rods fully inserted) at Ginna Station.

1~2 To define the scope of the review and the records that must be reviewed to perform this assessment.

2 '

REFERENCES:

2.1 Facility Technical Specifications 2.2 A-25 "Reporting of Unusual Plant Conditions" 2 ' A-25.1 "Ginna Station Event Report" 2 ' ,0-9.3 "NRC Immediate Notification" 2.5 Internal NRC Memo From R.W. Starostecki, Director, .DPRP

3.0 INSTRUCTIONS

3.1 Control Room 0 erator 3~1~1 Submit an A-25.1, "Unusual Event Report"'.

3 ~ 1.2 Inform Shift Supervisor of unusual conditions or observations made during the event.

3 ' Shift Technical Advisor 3.2.1 The Shift Technical Advisor shall perform a preliminary assessment of the event. This shall be documented by completion of the attached Post-Trip Review Form.

A-25 ~ 4 2 3 ' ' Upon completion of the form, forward it to the Shift Supervisor for inclusion with the A-25.4 Review.

3.2.3 The Shift Technical Advisor will also, upon request of the Shift Supervisor, assist with the Shift Supervisor's assessment.

3.3 Other Plant Personnel 3 ~ 3 ~ 1 Any other plant personnel that are involved with the event (Auxiliary Operators, I&C Techs, Electricians, etc.) should make themselves available to the Shift Supervisor to answer any question(s) about their involvement in the event.

3 ' Shift Su ervisor 3 '.1 The Shift Supervisor is to review the A-25.1 report, Operator notes, the Shift Technical Advisors assessment and any other information available to make a prelim-inary assessment of the cause of the Reactor Trip. The Shift Supervisor may call upon the Shift Technical Advisor and any other plant personnel to assist him in his assessment. The Shift Superviso'r Assessment and material used in the assessment will be passed to the Duty Engineer after the Shift Supervisor completes his assessment.

3.4.2 The Shift Supervisor shall review the event and assign one of the following classifications to the event. (Mark other classifications N/A) .

3 ' '.1 Condition One the cause of the trip is positively known. All safety-related and other important equipment functioned properly during the trip.

3 ' '.2 Condition Two - the cause of the trip is positively known. Some sa fety-related and/or other important equipment functioned in an abnormal or degraded manner.

3.4.2 ' Condition Three - the cause of the trip is not positively known.

A-25.4:3 3 ' Dut En ineer 5~1 The Duty Engineer shall review the Shift Supervisor's 3 ~

"assessment of the eve'nt.

review'rintout is available Ifit shall the computer post trip also be review-ed. The Duty Engineer shall make an assessment of the cause of the event. The Duty Engineer shall forward all materials, including his assessment, to the Plant Superintendent.

3.5.2 The Duty Engineer shall review the event classificat-ion. If the Duty Engineer does not concur with the Shift Supervisor's classification, the PORC will review the event and classify it.

3.6 Plant Su erintendent 3.6 ~ 1 The Plant Superintendent shall schedule a meeting of the Plant Operations Review Committee (PORC) with the purpose of reviewing the event.

3 ~ 6.2 All events regardless of classification shall be reviewed by the PORC and the Plant Superintendent's permission granted before the Reactor may be restarted.

3. 6.3 In the event that the cause of the trip is positively known and all Safety Related equipment functioned properly, the Plant Superintendent may authorize the Reactor restart prior to completion of all the attachments to this procedure.

3 ' PORC 3.7.1 Reports shall be presented by Subcommittee Chairman as identified on Attachment B.

3.7 ' PORC shall review the event and either concur with the assessment presented to it or initiate its own investigation into the cause of the event. Attachment C identifies necessary criteria for plant restart.

I 3 ' ' PORC shall determine stions are resolved.

if all safety or Tech Spec. que-3.7.4 PORC shall recommend to the Plant Superintendent whether or not to allow a Reactor restart.

l A-25.4:4 3 ' 0 erations Mana er 3.8 ~ 1 Operations Manager or his alternate shall review this material and concur with PORC's assessment prior to taking the reactor critical.

3.9 Corrective Actions 3.9.1 Any member of the plant staff may initiate corrective action by bringing the matter to the attention of plant management or the Shift Supervisor.

3.9 ' The plant shall not be made critical after a trip until the event has been reviewed and the cause is known.

4.0 RECORDS

4.1 Records of the review shall be noted in the minutes of the PORC meeting.

4.2 The PORC minutes shall be the permanent record of the review.

4.3 All material used in the Post Trip Review to shall be attached to this procedure and forwarded Central Records.

COMPLETION DATE COMPLETED BY:

OPERATIONS MANAGER:

A-25.4:5 REACTOR POST TRIP REVIEW (Refer to A-25.4 for Instructions)

A-25.4 TIME OF TRIP: DATE:

II. DESCRIPTION OF EVENT:

III. ACTIONS PERFORMED BY STA:

a) Procedures referred to:

b) Parameters observed:

c) Recognition/Diagnosis reached:

d) Advice given to Shift Supervisor:

IV. CAUSE OF EVENT:

V. ADDITIONAL COMMENTS:

SHIFT TECHNICAL ADVISOR:

A-25.4:6 ATTACHMENT B PORC SUBCOMMITTEE CHAIRMAN ASSIGNMENTS Evaluation of Safet Technical and Tech. S ec. uestions and Review A ainst A licable Information from the UFSAR and Prior Transients Technical Manager alternates: Nuclear Engineer Duty Engineer Evaluation of E i ment Malfunctions and Re air Plans Maintenance Manager alternates: I&C Supervisor Maintenance Supervisor Post Tri Review Cause Identification A-25.4 Re ort Summar P

Operations Manager alternates: Operations Supervisor Duty Engineer Startu Plans and Se uence Planner

A-25 ':7 ATTACHMENT C PORC REVIEW CRITERIA Root cause of problem(s) has been identified.

2 ~ A clear sequence of events has been determined.

3 ~ All near term corrective actions have been taken to resolve the root cause of the trip.

4 ~ Long term corrective actions are outline and a method for tracking them has been established.

5 ~ All ma j or sa fety systems and other important equipment responded properly or the root cause of the problem(s) found and circumstances reviewed to assure that no new potential safety concerns were identified.

6. Operation of plant systems during the trip was consistent to any applicable information provided in the UFSAR.

7 ~ Where possible, comparison with previous similar events has been made and no unexplained differences in operation of plant systems occurred.

8. Failure of any items from g5 shall be compared against A-25.4 reports and if necessary equipment history files to determine if any failures are repetitive in nature or involve common mode failures. Separate tracking documents may be initiated to follow corrective action on these items.

Items 6, 7, and 8 should include the information being used for comparison.

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