ML17334B745: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:eCATEGORYREGULATORY INFORMATION DXSTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9804280038 DOC.DATE:
{{#Wiki_filter:e CATEGORY REGULATORY INFORMATION DXSTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9804280038 DOC.DATE: 98/04/23 NOTARIZED:
98/04/23NOTARIZED:
NO DOCKET FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTK.NAME AUTHOR AFFILIATION KZAGSEED,J.
NODOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM05000315AUTK.NAME AUTHORAFFILIATION KZAGSEED,J.
Indiana Michigan Power Co.SAMPSON,J.R.
IndianaMichiganPowerCo.SAMPSON,J.R.
Indiana Michigan Power Co.RECIP.NAME RECIPIENT AFFILIATION
IndianaMichiganPowerCo.RECIP.NAME RECIPIENT AFFILIATION


==SUBJECT:==
==SUBJECT:==
LER98-020-00:on 980408,interimLER-determined thatcontainment recirculation sumppHupperlimitexceeded.
LER 98-020-00:on 980408, interim LER-determined that containment recirculation sump pH upper limit exceeded.Caused by analysis input omission.Condition remains under evaluation to determine appropriate action.W/980423 ltr.DISTRIBUT10N CODE: ZE22T COPIES RECEIVED:LTR ENCL SIZE: TXTLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: E RECIPIENT ID CODE/NAME PD3-3 PD INTERNAL:.8 FILE CENT EELB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRZB RGN3'ILE 01 EXTERNAL: L ST LOBBY WARD NOAC POORE,W.NRC PDR COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPXENT XD CODE/NAME STANG,J AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB LITCO BRYCE, J H NOAC QUEENER,DS NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 1 1'1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D U E N NOTE TO ALL"RIDS" RECIPIENTS:
Causedbyanalysisinputomission.
PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 24 Indiana Michigan Power Company aeC'ac<=ace
Condition remainsunderevaluation todetermine appropriate action.W/980423 ltr.DISTRIBUT10N CODE:ZE22TCOPIESRECEIVED:LTR ENCLSIZE:TXTLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTES:ERECIPIENT IDCODE/NAME PD3-3PDINTERNAL:
'l Is~a'I v<~C IMDIAbfA NICHIGAM POSER April 23, 1998 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Operating Licenses DPR-58 Docket No.50-315 Document Control Manager: In accordance with the criteria established by 10 CFR 50.73 entitled the following report is being submitted:
.8FILECENTEELBNRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRZB RGN3'ILE01EXTERNAL:
98-020-00 Sincerely,$Q J.R.Sampson.Site Vice President lmbd Attachment A.B.Beach, Region III E.E.Fitzpatrick P.A.Barrett S.J.Brewer R.Whale D.Hahn Records Center, INPO NRC Resident Inspector yV'804280038 980423 PDR ADOCK 050003i5 8 PDR HRC FORH 366 (5-92)U.S.HUCLEAR REGULATORY COMMISSIOH LICENSEE EVENT REPORT (LER), PPROVEO BY OMB HO.3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY NITH THI IHFDRHATIDH coLLEGTIDN REGUEsT: 50.0 HRs.FDRNAR COMMENTS REGARDING BURDEN ESTIHATE To TH IHFORHATIOH AND RECORDS MANAGEMENT BRANCH (HNB 7714), U.S.NUCLEAR REGULATORY COMMISSIONg IIASMINGTOH, DC 20555-0001, AND TO THE PAPERNOR REDUCTION PROJECT (3150-0104), OFFICE 0 MANAGEHENT AND BUDGET IIASHINGTOH DC 20503.FACILITY NAHE (1)Donald C.Cook Nuclear Plant-Unit 1 DOCKET NUHBER (2)50.315 Page1 of1 TITLE (4)Interim LER-Containment Recirculation Sump pH Upper Limit Exceeded Due to Analysis Input Omission EVENT DATE 5 LER HUMBER 6 REPORT DATE 7 OTHER FACILITIES INVOLVED 8 MONTH DAY YEAR YEAR 04 08 98 98 SEQUENTIAL NUMBER 020 REVISION NUMBER 00 MON'IH OAY 04 23 FACILITY NAME Cook-Unit 2 FACILITY HAME DOCKET HUHBER 50-316 DOCKET NUMBER OPERAT IHG MODE (9)PONER LEVEL (10)0 TH 50.73(a)(2)(iii) 50.73 a 2 iv 50.73(a)(2)(v) 50.73 a 2 vii 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 20.2203(a)(3)(I) 20.2203 a 3 ii 20.2203(a)(4) 50.36 c 1 50.36(c)(2) 50.73(a)(2)(I) 73.71(b)73.71o 20.2201(b) 20.2203 a 1 20.2203(a)(2)(I) 20.2203 a 2 ii 20.2203(a)(2)(iii) 20.2203(a)(2)(iv)
LSTLOBBYWARDNOACPOORE,W.NRCPDRCOPIESLTTRENCL112211111111111111111111RECIPXENT XDCODE/NAME STANG,JAEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB LITCOBRYCE,JHNOACQUEENER,DS NUDOCSFULLTXTCOPIESLTTRENCL111111'111111111111111DUENNOTETOALL"RIDS"RECIPIENTS:
OTHER (Specify in Abstract below and in Text, HRC Form 366A)20.2203(a)(2)(v) 50 73(a)(2)(il) 50'73(a)(2)(x)
PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
LICENSEE CONTACT FOR THIS LER 12 S REPORT IS SUBHITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR: Check one or mo e 11 NAHE Mr.Jeb Kingseed, Nuclear Safety Analysis Manager TELEPHOHE NUMBER (Include Area Code)616 697-5106 COMPLETE ONE LINE FOR EACH COMPOHENT FAILURE DESCRIBED IN THIS REPORT CAUSE SYSTEH COMPOHEHT MANUFACTURER REPORTABLE TO HPRDS CAUSE SYSTEM COMPONENT MAHUFACTURER REPORTABLE TO HPRDS gyes:;;4):
LTTR24ENCL24 IndianaMichiganPowerCompanyaeC'ac<=ace
SUPPLEHENTAL REPORT EXPECTED 14 X YES (If yes, complete EXPECTED SUBMISSION DATE).NO EXPECTED SUBMISSION DATE (15)MONTH DAY YEAR 07 31 98 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten tines)(16)On April 9, 1998, an ENS notification was made in accordance with 10 CFR 50.72(b)(2)(i), for a condition which was found while both units were shutdown, which had it been found while the reactor was in operation, could have resulted in the nuclear plant being in an unanalyzed condition.
'lIs~a'Iv<~CIMDIAbfANICHIGAMPOSERApril23,1998UnitedStatesNuclearRegulatory Commission DocumentControlDeskWashington, DC20555Operating LicensesDPR-58DocketNo.50-315DocumentControlManager:Inaccordance withthecriteriaestablished by10CFR50.73entitledthefollowing reportisbeingsubmitted:
This notiTication is a result of an issue discovered during a safety system functional inspection of the containment spray system.It has been determined that the Westinghouse method for calculating the maximum pH in the containment sump after an accident might result in a pH that is too basic.While responding to an AEP audit question, Westinghouse discovered that the sodium hydroxide contained within the ice condenser ice beds had not been included in any of the BORDER analysis performed for Cook Plant.BORDER is a computer program used to determine the pH in the containment sump.The impact of this is that the actual containment sump pH value following a toss of coolant accident exceeds the maximum pH limit in the Bases for Technical Specification (T/S)9.5.Preliminary calculations indicate a pH value of approximately 9.7 is possible.The T/S is based on Branch Technical Position MTEB 6-1 on the pH for emergency cooling water for PWRs.The reference states that the pH should be in the high end of the range of 7.0 to 9.5 for greater assurance that stress corrosion cracking will not occur.The reference does not give any guidance on what the affects would be if 9.5 is exceeded, thus the unanalyzed condition.
98-020-00 Sincerely,
The significance of the impact of the pH above the range in the T/S requires further evaluation.
$QJ.R.Sampson.SiteVicePresident lmbdAttachment A.B.Beach,RegionIIIE.E.Fitzpatrick P.A.BarrettS.J.BrewerR.WhaleD.HahnRecordsCenter,INPONRCResidentInspector yV'804280038 980423PDRADOCK050003i58PDR HRCFORH366(5-92)U.S.HUCLEARREGULATORY COMMISSIOH LICENSEEEVENTREPORT(LER),PPROVEOBYOMBHO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYNITHTHIIHFDRHATIDH coLLEGTIDN REGUEsT:50.0HRs.FDRNARCOMMENTSREGARDING BURDENESTIHATEToTHIHFORHATIOH ANDRECORDSMANAGEMENT BRANCH(HNB7714),U.S.NUCLEARREGULATORY COMMISSIONg IIASMINGTOH, DC20555-0001, ANDTOTHEPAPERNORREDUCTION PROJECT(3150-0104),
This condition remains under evaluation to determine appropriate action to rectify this issue.Additionally, this issue is being evaluated for potential 10CFR Part 21 reportability.
OFFICE0MANAGEHENT ANDBUDGETIIASHINGTOH DC20503.FACILITYNAHE(1)DonaldC.CookNuclearPlant-Unit1DOCKETNUHBER(2)50.315Page1of1TITLE(4)InterimLER-Containment Recirculation SumppHUpperLimitExceededDuetoAnalysisInputOmissionEVENTDATE5LERHUMBER6REPORTDATE7OTHERFACILITIES INVOLVED8MONTHDAYYEARYEAR04089898SEQUENTIAL NUMBER020REVISIONNUMBER00MON'IHOAY0423FACILITYNAMECook-Unit2FACILITYHAMEDOCKETHUHBER50-316DOCKETNUMBEROPERATIHGMODE(9)PONERLEVEL(10)0TH50.73(a)(2)(iii) 50.73a2iv50.73(a)(2)(v) 50.73a2vii50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 20.2203(a)(3)(I) 20.2203a3ii20.2203(a)(4) 50.36c150.36(c)(2) 50.73(a)(2)(I) 73.71(b)73.71o20.2201(b) 20.2203a120.2203(a)(2)(I) 20.2203a2ii20.2203(a)(2)(iii) 20.2203(a)(2)(iv)
An update to this interim LER will be submitted by July 31, 1998.}}
OTHER(SpecifyinAbstractbelowandinText,HRCForm366A)20.2203(a)(2)(v) 5073(a)(2)(il) 50'73(a)(2)(x)
LICENSEECONTACTFORTHISLER12SREPORTISSUBHITTED PURSUANTTOTHEREOUIREMENTS OF10CFR:Checkoneormoe11NAHEMr.JebKingseed, NuclearSafetyAnalysisManagerTELEPHOHE NUMBER(IncludeAreaCode)616697-5106COMPLETEONELINEFOREACHCOMPOHENT FAILUREDESCRIBED INTHISREPORTCAUSESYSTEHCOMPOHEHT MANUFACTURER REPORTABLE TOHPRDSCAUSESYSTEMCOMPONENT MAHUFACTURER REPORTABLE TOHPRDSgyes:;;4):
SUPPLEHENTAL REPORTEXPECTED14XYES(Ifyes,completeEXPECTEDSUBMISSION DATE).NOEXPECTEDSUBMISSION DATE(15)MONTHDAYYEAR073198ABSTRACT(Limitto1400spaces,i.e.,approximately 15single-spaced typewritten tines)(16)OnApril9,1998,anENSnotification wasmadeinaccordance with10CFR50.72(b)(2)(i),
foracondition whichwasfoundwhilebothunitswereshutdown, whichhaditbeenfoundwhilethereactorwasinoperation, couldhaveresultedinthenuclearplantbeinginanunanalyzed condition.
ThisnotiTication isaresultofanissuediscovered duringasafetysystemfunctional inspection ofthecontainment spraysystem.Ithasbeendetermined thattheWestinghouse methodforcalculating themaximumpHinthecontainment sumpafteranaccidentmightresultinapHthatistoobasic.Whileresponding toanAEPauditquestion, Westinghouse discovered thatthesodiumhydroxide contained withintheicecondenser icebedshadnotbeenincludedinanyoftheBORDERanalysisperformed forCookPlant.BORDERisacomputerprogramusedtodetermine thepHinthecontainment sump.Theimpactofthisisthattheactualcontainment sumppHvaluefollowing atossofcoolantaccidentexceedsthemaximumpHlimitintheBasesforTechnical Specification (T/S)9.5.Preliminary calculations indicateapHvalueofapproximately 9.7ispossible.
TheT/SisbasedonBranchTechnical PositionMTEB6-1onthepHforemergency coolingwaterforPWRs.Thereference statesthatthepHshouldbeinthehighendoftherangeof7.0to9.5forgreaterassurance thatstresscorrosion crackingwillnotoccur.Thereference doesnotgiveanyguidanceonwhattheaffectswouldbeif9.5isexceeded, thustheunanalyzed condition.
Thesignificance oftheimpactofthepHabovetherangeintheT/Srequiresfurtherevaluation.
Thiscondition remainsunderevaluation todetermine appropriate actiontorectifythisissue.Additionally, thisissueisbeingevaluated forpotential 10CFRPart21reportability.
AnupdatetothisinterimLERwillbesubmitted byJuly31,1998.}}

Revision as of 07:11, 6 July 2018

LER 98-020-00:on 980408,interim LER - Determined That Containment Recirculation Sump Ph Upper Limit Exceeded. Caused by Analysis Input Omission.Condition Remains Under Evaluation to Determine Appropriate action.W/980423 Ltr
ML17334B745
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 04/23/1998
From: KINGSEED J, SAMPSON J R
AMERICAN ELECTRIC POWER CO., INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-98-020, LER-98-20, NUDOCS 9804280038
Download: ML17334B745 (3)


Text

e CATEGORY REGULATORY INFORMATION DXSTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9804280038 DOC.DATE: 98/04/23 NOTARIZED:

NO DOCKET FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTK.NAME AUTHOR AFFILIATION KZAGSEED,J.

Indiana Michigan Power Co.SAMPSON,J.R.

Indiana Michigan Power Co.RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 98-020-00:on 980408, interim LER-determined that containment recirculation sump pH upper limit exceeded.Caused by analysis input omission.Condition remains under evaluation to determine appropriate action.W/980423 ltr.DISTRIBUT10N CODE: ZE22T COPIES RECEIVED:LTR ENCL SIZE: TXTLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: E RECIPIENT ID CODE/NAME PD3-3 PD INTERNAL:.8 FILE CENT EELB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRZB RGN3'ILE 01 EXTERNAL: L ST LOBBY WARD NOAC POORE,W.NRC PDR COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPXENT XD CODE/NAME STANG,J AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB LITCO BRYCE, J H NOAC QUEENER,DS NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 1 1'1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D U E N NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 24 Indiana Michigan Power Company aeC'ac<=ace

'l Is~a'I v<~C IMDIAbfA NICHIGAM POSER April 23, 1998 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Operating Licenses DPR-58 Docket No.50-315 Document Control Manager: In accordance with the criteria established by 10 CFR 50.73 entitled the following report is being submitted:

98-020-00 Sincerely,$Q J.R.Sampson.Site Vice President lmbd Attachment A.B.Beach, Region III E.E.Fitzpatrick P.A.Barrett S.J.Brewer R.Whale D.Hahn Records Center, INPO NRC Resident Inspector yV'804280038 980423 PDR ADOCK 050003i5 8 PDR HRC FORH 366 (5-92)U.S.HUCLEAR REGULATORY COMMISSIOH LICENSEE EVENT REPORT (LER), PPROVEO BY OMB HO.3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY NITH THI IHFDRHATIDH coLLEGTIDN REGUEsT: 50.0 HRs.FDRNAR COMMENTS REGARDING BURDEN ESTIHATE To TH IHFORHATIOH AND RECORDS MANAGEMENT BRANCH (HNB 7714), U.S.NUCLEAR REGULATORY COMMISSIONg IIASMINGTOH, DC 20555-0001, AND TO THE PAPERNOR REDUCTION PROJECT (3150-0104), OFFICE 0 MANAGEHENT AND BUDGET IIASHINGTOH DC 20503.FACILITY NAHE (1)Donald C.Cook Nuclear Plant-Unit 1 DOCKET NUHBER (2)50.315 Page1 of1 TITLE (4)Interim LER-Containment Recirculation Sump pH Upper Limit Exceeded Due to Analysis Input Omission EVENT DATE 5 LER HUMBER 6 REPORT DATE 7 OTHER FACILITIES INVOLVED 8 MONTH DAY YEAR YEAR 04 08 98 98 SEQUENTIAL NUMBER 020 REVISION NUMBER 00 MON'IH OAY 04 23 FACILITY NAME Cook-Unit 2 FACILITY HAME DOCKET HUHBER 50-316 DOCKET NUMBER OPERAT IHG MODE (9)PONER LEVEL (10)0 TH 50.73(a)(2)(iii) 50.73 a 2 iv 50.73(a)(2)(v) 50.73 a 2 vii 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 20.2203(a)(3)(I) 20.2203 a 3 ii 20.2203(a)(4) 50.36 c 1 50.36(c)(2) 50.73(a)(2)(I) 73.71(b)73.71o 20.2201(b) 20.2203 a 1 20.2203(a)(2)(I) 20.2203 a 2 ii 20.2203(a)(2)(iii) 20.2203(a)(2)(iv)

OTHER (Specify in Abstract below and in Text, HRC Form 366A)20.2203(a)(2)(v) 50 73(a)(2)(il) 50'73(a)(2)(x)

LICENSEE CONTACT FOR THIS LER 12 S REPORT IS SUBHITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR: Check one or mo e 11 NAHE Mr.Jeb Kingseed, Nuclear Safety Analysis Manager TELEPHOHE NUMBER (Include Area Code)616 697-5106 COMPLETE ONE LINE FOR EACH COMPOHENT FAILURE DESCRIBED IN THIS REPORT CAUSE SYSTEH COMPOHEHT MANUFACTURER REPORTABLE TO HPRDS CAUSE SYSTEM COMPONENT MAHUFACTURER REPORTABLE TO HPRDS gyes:;;4):

SUPPLEHENTAL REPORT EXPECTED 14 X YES (If yes, complete EXPECTED SUBMISSION DATE).NO EXPECTED SUBMISSION DATE (15)MONTH DAY YEAR 07 31 98 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten tines)(16)On April 9, 1998, an ENS notification was made in accordance with 10 CFR 50.72(b)(2)(i), for a condition which was found while both units were shutdown, which had it been found while the reactor was in operation, could have resulted in the nuclear plant being in an unanalyzed condition.

This notiTication is a result of an issue discovered during a safety system functional inspection of the containment spray system.It has been determined that the Westinghouse method for calculating the maximum pH in the containment sump after an accident might result in a pH that is too basic.While responding to an AEP audit question, Westinghouse discovered that the sodium hydroxide contained within the ice condenser ice beds had not been included in any of the BORDER analysis performed for Cook Plant.BORDER is a computer program used to determine the pH in the containment sump.The impact of this is that the actual containment sump pH value following a toss of coolant accident exceeds the maximum pH limit in the Bases for Technical Specification (T/S)9.5.Preliminary calculations indicate a pH value of approximately 9.7 is possible.The T/S is based on Branch Technical Position MTEB 6-1 on the pH for emergency cooling water for PWRs.The reference states that the pH should be in the high end of the range of 7.0 to 9.5 for greater assurance that stress corrosion cracking will not occur.The reference does not give any guidance on what the affects would be if 9.5 is exceeded, thus the unanalyzed condition.

The significance of the impact of the pH above the range in the T/S requires further evaluation.

This condition remains under evaluation to determine appropriate action to rectify this issue.Additionally, this issue is being evaluated for potential 10CFR Part 21 reportability.

An update to this interim LER will be submitted by July 31, 1998.