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| =Text= | | =Text= |
| {{#Wiki_filter:ACCEI.ERATED DOCUMENTDISTIUBUTION SYSTEMREGULA2YINFORMATION DISTRIBUTICSYSTEM (RIDE)ACCESSION NBR:9307280203 DOC.DATE: | | {{#Wiki_filter:ACCEI.ERATED DOCUMENT DISTIUBUTION SYSTEM REGULA2Y INFORMATION DISTRIBUTICSYSTEM (RIDE)ACCESSION NBR:9307280203 DOC.DATE: 93/07/20 NOTARIZED: |
| 93/07/20NOTARIZED: | | NO DOCKET FA IL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C. |
| NODOCKETFAIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester G05000244AUTH.NAMEAUTHORAFFILIATION MECREDY,R.C.
| | Rochester Gas 6 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
| Rochester Gas6ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk) | |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| ForwardsLER93-003-00 rediscovered failuresofSafeguard svcwatersysvalvesduringplannedmaintenance.
| | Forwards LER 93-003-00 re discovered failures of Safeguard svc water sys valves during planned maintenance. |
| DISTRIBUTION CODE:IE22DCOPIESRECEIVED:LTR JENCLQSIZE:l+7TITLE:50.73/50.9 LicenseeEventReport(LER),incidentRpt,etc.DNOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72). | | DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR J ENCL Q SIZE: l+7 TITLE: 50.73/50.9 Licensee Event Report (LER), incident Rpt, etc.D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). |
| 05000244IRECIPIENT IDCODE/NAME PD1-3LAJOHNSON,A INTERNAL:
| | 05000244 I RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: ACNW AEOD/DSP/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB NKtQDSS-SPLB 02 RGN1 FILE 01 EXTERNAL: EGSG BRYCE,J.H NRC PDR NSIC POOREFW.COPIES LTTR ENCL 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD AEOD/DOA AEOD/ROAB/DSP NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB L ST LOBBY WARD NSIC MURPHYFG.A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 D D NOTE TO ALL"RIDS" RECIPIENTS: |
| ACNWAEOD/DSP/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB NKtQDSS-SPLB02RGN1FILE01EXTERNAL:
| | PLEASE HELP US TO REDUCE WASTE!CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl D TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 30 |
| EGSGBRYCE,J.H NRCPDRNSICPOOREFW.COPIESLTTRENCL1111RECIPIENT IDCODE/NAME PD1-3PDAEOD/DOAAEOD/ROAB/DSP NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB LSTLOBBYWARDNSICMURPHYFG.A NUDOCSFULLTXTCOPIESLTTRENCL111122111111221111111111DDNOTETOALL"RIDS"RECIPIENTS:
| |
| PLEASEHELPUSTOREDUCEWASTE!CONTACI'HE DOCUMENTCONTROLDESK,ROOMPl-37(EXT.504-2065)
| |
| TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEEDlDTOTALNUMBEROFCOPIESREQUIRED:
| |
| LTTR30ENCL30
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|
| |
|
| IIROCHESTER GASANDELECTRICCORPORATION
| | I I ROCHESTER GAS AND ELECTRIC CORPORATION |
| ~~~~44~~4rrtei'.,Totetea'rc89EASTAVENUE,ROCHESTER N.Y.14649.0001 ROBERTC.MECREOYVicePrerldent CinnaNuclearProduction TELEPHONE AREACODE7165462700July20,1993U.S.NuclearRegulatory Commission DocumentControlDeskWashington, DC20555 | | ~~~~44~~4 rrte i'., Tote tea'rc 89 EAST AVENUE, ROCHESTER N.Y.14649.0001 ROBERT C.MECREOY Vice Prerldent Cinna Nuclear Production TELEPHONE AREA CODE 716 546 2700 July 20, 1993 U.S.Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 |
|
| |
|
| ==Subject:== | | ==Subject:== |
| LER93-003,DuringPlannedMaintenance, FailuresofSafeguard ServiceWaterSystemValvesWereDiscovered.
| | LER 93-003, During Planned Maintenance, Failures of Safeguard Service Water System Valves Were Discovered. |
| R.E.GinnaNuclearPowerPlantDocketNo.50-244Theseeventsarebeingvoluntarily reportedusingtheguidanceofNUREG-1022 (Licensee EventReportSystem),andSupplement 1toNUREG-1022. | | R.E.Ginna Nuclear Power Plant Docket No.50-244 These events are being voluntarily reported using the guidance of NUREG-1022 (Licensee Event Report System), and Supplement 1 to NUREG-1022. |
| Whilethesafetysignificance ofthesespecificeventsdoesnotrequiresubmittal ofaLicenseeEventReport,thesetypesofdegradation couldbesafety-significant atotherplants,depending onthevalveapplication.
| | While the safety significance of these specific events does not require submittal of a Licensee Event Report, these types of degradation could be safety-significant at other plants, depending on the valve application. |
| Thisreportisintendedtoalertotherutilities andtheNRCofproblemsinapplications wherecorrosion canoccurbetweenthevalvestemanddisk,inrawwaterapplications, andofthepotential fordegrada-tionofisolation capabilities duetovalvedeterioration.
| | This report is intended to alert other utilities and the NRC of problems in applications where corrosion can occur between the valve stem and disk, in raw water applications, and of the potential for degrada-tion of isolation capabilities due to valve deterioration. |
| Theseeventsarerelatedto,butdonotmeet,thereporting require-mentsof10CFR50.73,item(a)(2)(v) and(a)(2)(vi),
| | These events are related to, but do not meet, the reporting require-ments of 10 CFR 50.73, item (a)(2)(v)and (a)(2)(vi), which requires reporting of conditions,"that alone could have prevented the fulfillment of the safety function", but where,"individual component failures need not be reported". |
| whichrequiresreporting ofconditions, "thatalonecouldhaveprevented thefulfillment ofthesafetyfunction",
| | The attached Licensee Event Report LER 93-003 is hereby voluntarily submitted. |
| butwhere,"individual component failuresneednotbereported".
| | This event has in no way affected the public's health and safety.xc4 Ve truly yours, C~Robert C.Mecredy U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident inspector 2800~;: 9307280203 Tt30720 PDR ADDCK 05000244 8 PDR/pd'r'}} |
| TheattachedLicenseeEventReportLER93-003isherebyvoluntarily submitted.
| |
| Thiseventhasinnowayaffectedthepublic'shealthandsafety.xc4Vetrulyyours,C~RobertC.MecredyU.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaUSNRCSeniorResidentinspector 2800~;:9307280203 Tt30720PDRADDCK050002448PDR/pd'r'}}
| |
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Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl
ML17265A5101999-01-11011 January 1999
Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl
1999-09-30
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ACCEI.ERATED DOCUMENT DISTIUBUTION SYSTEM REGULA2Y INFORMATION DISTRIBUTICSYSTEM (RIDE)ACCESSION NBR:9307280203 DOC.DATE: 93/07/20 NOTARIZED:
NO DOCKET FA IL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards LER 93-003-00 re discovered failures of Safeguard svc water sys valves during planned maintenance.
DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR J ENCL Q SIZE: l+7 TITLE: 50.73/50.9 Licensee Event Report (LER), incident Rpt, etc.D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 I RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: ACNW AEOD/DSP/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB NKtQDSS-SPLB 02 RGN1 FILE 01 EXTERNAL: EGSG BRYCE,J.H NRC PDR NSIC POOREFW.COPIES LTTR ENCL 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD AEOD/DOA AEOD/ROAB/DSP NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB L ST LOBBY WARD NSIC MURPHYFG.A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 D D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl D TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 30
I I ROCHESTER GAS AND ELECTRIC CORPORATION
~~~~44~~4 rrte i'., Tote tea'rc 89 EAST AVENUE, ROCHESTER N.Y.14649.0001 ROBERT C.MECREOY Vice Prerldent Cinna Nuclear Production TELEPHONE AREA CODE 716 546 2700 July 20, 1993 U.S.Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
LER 93-003, During Planned Maintenance, Failures of Safeguard Service Water System Valves Were Discovered.
R.E.Ginna Nuclear Power Plant Docket No.50-244 These events are being voluntarily reported using the guidance of NUREG-1022 (Licensee Event Report System), and Supplement 1 to NUREG-1022.
While the safety significance of these specific events does not require submittal of a Licensee Event Report, these types of degradation could be safety-significant at other plants, depending on the valve application.
This report is intended to alert other utilities and the NRC of problems in applications where corrosion can occur between the valve stem and disk, in raw water applications, and of the potential for degrada-tion of isolation capabilities due to valve deterioration.
These events are related to, but do not meet, the reporting require-ments of 10 CFR 50.73, item (a)(2)(v)and (a)(2)(vi), which requires reporting of conditions,"that alone could have prevented the fulfillment of the safety function", but where,"individual component failures need not be reported".
The attached Licensee Event Report LER 93-003 is hereby voluntarily submitted.
This event has in no way affected the public's health and safety.xc4 Ve truly yours, C~Robert C.Mecredy U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident inspector 2800~;: 9307280203 Tt30720 PDR ADDCK 05000244 8 PDR/pd'r'
