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| | issue date = 07/22/1999 | | | issue date = 07/22/1999 |
| | title = Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations | | | title = Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations |
| | author name = MECREDY R C | | | author name = Mecredy R |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = VISSING G S | | | addressee name = Vissing G |
| | addressee affiliation = NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) | | | addressee affiliation = NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| | docket = 05000244 | | | docket = 05000244 |
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| =Text= | | =Text= |
| {{#Wiki_filter:CATEGORYREGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9907280113DOC.DATE:99/07/22NOTARIZED:NOFACXL:50-244RobertEmmetGinnaNuclearPlant,Unit1,RochesterGAUTH.NAMEAUTHORAFFILIATIONMECREDY,R.C.RochesterGas8ElectricCorp..-RECXP.NAMERECIPIENTAFFILIATIONVISSZNG,G.S. | | {{#Wiki_filter:CATEGORY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| | ACCESSION NBR:9907280113 DOC.DATE: 99/07/22 NOTARIZED: NO DOCKET FACXL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas 8 Electric Corp..- |
| | RECXP.NAME RECIPIENT AFFILIATION VISSZNG,G.S. |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ForwardsLER98-003-02,reactuationsofCRemergencyairtreatmentsys.All'REATSactuations,includingthoseoriginallybelievedtobevalidactuations,were,infactinvalidactuations.'DOCKET05000244DISTRIBUTIONCODE:IE22TCOPIESRECEIVED:LTRENCLJSIZE:TITLE:50.73/50.9LicenseeEventReport(LER),IncidentRpt,etc.NOTES:LicenseExpdateinaccordancewith10CFR2,2.109(9/19/72).05000244RECIPIENTZDCODE/NAMELPD1-1PDINTERNAL'/DRIP/REXBRES/DET/ERABRGN1FILE01COPIESLTTRENCL111111~1111RECIPIENTIDCODE/NAMEVZSSING,G.NRR/DIPM/ZOLBNRR/DSSA/SPLBRES/DRAA/OERABCOPIESLTTRENCL11111'11EXTERNAL:LSTLOBBYWARDNOACPOORE,W.NRCPDR111111LMITCOMARSHALLNOACQUEENER,DSNUDOCSFULLTXT111~111NOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATIONREMOVEDFROMDISTRIBUTIONLIS'RREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION,CONTACTTHEDOCUMENTCONTRiDESK(DCD)ONEXTENSION415-2083FULLTEXTCONVERSIONREQUIREDTOTALNUMBEROFCOPIESREQUIRED:LTTR15ENCL15 04NDROCHESTERGASANDElECTRICCORPORATION~89EASTAtrrENUE,ROCHESTER,N.Y.Id6d9-OOOIl'OBERTC.MECREDYVicePresidentNvcleorOperotionsAREACODE7165'-2700July22,1999U.S.NuclearRegulatoryCommissionDocumentControlDeskAttn:GuyS.VissingProjectDirectorateI-1Washington,D.C.20555
| | Forwards LER 98-003-02,re actuations of CR emergency air treatment sys.All'REATS actuations,including those originally believed to be valid actuations,were, in fact invalid actuations. |
| | DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL J SIZE: |
| | TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| | NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ZD CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL LPD1-1 PD 1 1 VZSSING,G. 1 1 INTERNAL 1 1 NRR/DIPM/ZOLB 1 1 |
| | '/DRIP/REXB 1 1 ~ |
| | NRR/DSSA/SPLB 1 ' |
| | RES/DET/ERAB 1 1 RES/DRAA/OERAB 1 1 RGN1 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LMITCO MARSHALL 1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 1 ~ 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT LIS'R DESK (DCD) ON EXTENSION 415-2083 THE DOCUMENT CONTRi FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 15 |
| | |
| | 0 4ND ROCHESTER GAS AND ElECTRIC CORPORATION ~ 89 EAST AtrrENUE, ROCHESTER, N.Y. Id6d9-OOOI AREA CODE 716 5'-2700 l'OBERT C. MECREDY Vice President Nvcleor Operotions July 22, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555 |
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| |
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| ==Subject:== | | ==Subject:== |
| LER1998-003,Revision2,ActuationsofControlRoomEmergencyAirTreatmentSystemDuetoInvalidCausesR.EDGinnaNuclearPowerPlantDocketNo.50-244
| | LER 1998-003, Revision 2, Actuations of Control Room Emergency Air Treatment System Due to Invalid Causes R.ED Ginna Nuclear Power Plant Docket No. 50-244 |
| | |
| | ==Dear Mr. Vissing:== |
| | |
| | In accordance with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (iv), which requires a report of, "any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS)", the attached Licensee Event Report LER 1998-003 (Revision 2) is hereby submitted. |
| | It has been determined that there were various degraded components in the Control Room Radiation Monitoring system. |
| | These degraded components resulted in electronic spikes in the readings on the monitors. The higher concentrations of Radon and Radon decay products caused the margin to the trip setpoint to be reduced. Thus, in the presence of elevated Radon levels, the electronic spikes caused a setpoint to be exceeded. When elevated Radon levels were not present, larger spikes also caused a setpoint to be exceeded. The degraded components, resulting in electronic spikes, were the root cause of the Control Room Emergency Air Treatment System (CREATS) actuations. All CREATS actuations, including those originally believed to be valid actuations, were, in fact, invalid actuations. |
| | Very truly yours, F' |
| | Robert C. Mecred 9907280i13 990722 PDR ADOCK 05000244 8 PDR |
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| |
|
| ==DearMr.Vissing:==
| | xc: Mr. Guy S. Vissing (Mail Stop 8C2) |
| Inaccordancewith10CFR50.73,LicenseeEventReportSystem,item(a)(2)(iv),whichrequiresareportof,"anyeventorconditionthatresultedinmanualorautomaticactuationofanyEngineeredSafetyFeature(ESF),includingtheReactorProtectionSystem(RPS)",theattachedLicenseeEventReportLER1998-003(Revision2)isherebysubmitted.IthasbeendeterminedthattherewerevariousdegradedcomponentsintheControlRoomRadiationMonitoringsystem.Thesedegradedcomponentsresultedinelectronicspikesinthereadingsonthemonitors.ThehigherconcentrationsofRadonandRadondecayproductscausedthemargintothetripsetpointtobereduced.Thus,inthepresenceofelevatedRadonlevels,theelectronicspikescausedasetpointtobeexceeded.WhenelevatedRadonlevelswerenotpresent,largerspikesalsocausedasetpointtobeexceeded.Thedegradedcomponents,resultinginelectronicspikes,weretherootcauseoftheControlRoomEmergencyAirTreatmentSystem(CREATS)actuations.AllCREATSactuations,includingthoseoriginallybelievedtobevalidactuations,were,infact,invalidactuations.Verytrulyyours,RobertC.MecredF'9907280i13990722PDRADOCK050002448PDR xc:Mr.GuyS.Vissing(MailStop8C2)ProjectDirectorateI-1DivisionofReactorProjects-I/IIOfficeofNuclearReactorRegulationU.S.NuclearRegulatoryCommissionWashington,D.C.20555RegionalAdministrator,RegionIU.S.NuclearRegulatoryCommission475AllendaleRoadKingofPrussia,PA19406U.S.NRCGinnaSeniorResidentInspector}}
| | Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector}} |
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Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii)
ML17309A6491999-02-12012 February 1999
Forwards Ginna Station EOPs
ML17265A5431999-02-0909 February 1999
Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301
ML17265A5361999-02-0202 February 1999
Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl
ML17311A0691999-01-25025 January 1999
Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
ML17311A0671999-01-14014 January 1999
Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
ML17265A5111999-01-11011 January 1999
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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Text
CATEGORY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9907280113 DOC.DATE: 99/07/22 NOTARIZED: NO DOCKET FACXL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas 8 Electric Corp..-
RECXP.NAME RECIPIENT AFFILIATION VISSZNG,G.S.
SUBJECT:
Forwards LER 98-003-02,re actuations of CR emergency air treatment sys.All'REATS actuations,including those originally believed to be valid actuations,were, in fact invalid actuations.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL J SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ZD CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL LPD1-1 PD 1 1 VZSSING,G. 1 1 INTERNAL 1 1 NRR/DIPM/ZOLB 1 1
'/DRIP/REXB 1 1 ~
NRR/DSSA/SPLB 1 '
RES/DET/ERAB 1 1 RES/DRAA/OERAB 1 1 RGN1 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LMITCO MARSHALL 1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 1 ~ 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT LIS'R DESK (DCD) ON EXTENSION 415-2083 THE DOCUMENT CONTRi FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 15
0 4ND ROCHESTER GAS AND ElECTRIC CORPORATION ~ 89 EAST AtrrENUE, ROCHESTER, N.Y. Id6d9-OOOI AREA CODE 716 5'-2700 l'OBERT C. MECREDY Vice President Nvcleor Operotions July 22, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555
Subject:
LER 1998-003, Revision 2, Actuations of Control Room Emergency Air Treatment System Due to Invalid Causes R.ED Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Vissing:
In accordance with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (iv), which requires a report of, "any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS)", the attached Licensee Event Report LER 1998-003 (Revision 2) is hereby submitted.
It has been determined that there were various degraded components in the Control Room Radiation Monitoring system.
These degraded components resulted in electronic spikes in the readings on the monitors. The higher concentrations of Radon and Radon decay products caused the margin to the trip setpoint to be reduced. Thus, in the presence of elevated Radon levels, the electronic spikes caused a setpoint to be exceeded. When elevated Radon levels were not present, larger spikes also caused a setpoint to be exceeded. The degraded components, resulting in electronic spikes, were the root cause of the Control Room Emergency Air Treatment System (CREATS) actuations. All CREATS actuations, including those originally believed to be valid actuations, were, in fact, invalid actuations.
Very truly yours, F'
Robert C. Mecred 9907280i13 990722 PDR ADOCK 05000244 8 PDR
xc: Mr. Guy S. Vissing (Mail Stop 8C2)
Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector
