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| | issue date = 07/20/1993 | | | issue date = 07/20/1993 |
| | title = Forwards LER 93-003-00 Re Discovered Failures of Safeguard Svc Water Sys Valves During Planned Maintenance | | | title = Forwards LER 93-003-00 Re Discovered Failures of Safeguard Svc Water Sys Valves During Planned Maintenance |
| | author name = MECREDY R C | | | author name = Mecredy R |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:ACCEI.ERATED DOCUMENT DISTIUBUTION SYSTEM REGULA2Y INFORMATION DISTRIBUTICSYSTEM (RIDE)ACCESSION NBR:9307280203 DOC.DATE: 93/07/20 NOTARIZED: | | {{#Wiki_filter:ACCEI.ERATED DOCUMENT DISTIUBUTION SYSTEM REGULA2Y INFORMATION DISTRIBUTICSYSTEM (RIDE) |
| NO DOCKET FA IL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C. | | 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. |
| Rochester Gas 6 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) | | RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Forwards LER 93-003-00 re discovered failures of Safeguard svc water sys valves during planned maintenance. | | 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). | | DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR TITLE: 50.73/50.9 Licensee Event Report (LER), incidentQRpt, etc. |
| 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: | | J ENCL SIZE: l+ 7 D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 I |
| 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 | | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 1 1 PD1-3 PD 1 1 JOHNSON,A 1 1 D |
| | INTERNAL: ACNW AEOD/DOA 1 1 AEOD/DSP/TPAB AEOD/ROAB/DSP 2 2 NRR/DE/EELB NRR/DE/EMEB 1 1 NRR/DORS/OEAB NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB NRR/DRCH/HOLB 1 1 NRR/DRIL/RPEB NRR/DRSS/PRPB 2 2 NKtQDSS - SPLB NRR/DSSA/SRXB 1 1 02 RES/DSIR/EIB 1 1 RGN1 FILE 01 EXTERNAL: EGSG BRYCE,J.H L ST LOBBY WARD 1 1 NRC PDR NSIC MURPHYFG.A 1 1 NSIC POOREFW. NUDOCS FULL TXT 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 ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 30 |
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| |
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| I I ROCHESTER GAS AND ELECTRIC CORPORATION
| | ~ ~ ~ 44 ~ ~ 4 rrte I |
| ~~~~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
| | i '., Tote I tea'rc ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER N.Y. 14649.0001 ROBERT C. MECREOY TELEPHONE Vice Prerldent AREA CODE 716 546 2700 Cinna Nuclear Production July 20, 1993 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 |
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| ==Subject:== | | ==Subject:== |
| LER 93-003, During Planned Maintenance, Failures of Safeguard Service Water System Valves Were Discovered. | | 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. | | 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. |
| 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 event has in no way affected the public's health and safety. |
| 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. | | Ve truly yours, C~ |
| 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". | | Robert C. Mecredy xc4 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident inspector 2800~;: |
| The attached Licensee Event Report LER 93-003 is hereby voluntarily submitted. | | 9307280203 Tt30720 PDR ADDCK 05000244 8 PDR |
| 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'}} | | /pd'r'}} |
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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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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 TITLE: 50.73/50.9 Licensee Event Report (LER), incidentQRpt, etc.
J ENCL SIZE: l+ 7 D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 I
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 1 1 PD1-3 PD 1 1 JOHNSON,A 1 1 D
INTERNAL: ACNW AEOD/DOA 1 1 AEOD/DSP/TPAB AEOD/ROAB/DSP 2 2 NRR/DE/EELB NRR/DE/EMEB 1 1 NRR/DORS/OEAB NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB NRR/DRCH/HOLB 1 1 NRR/DRIL/RPEB NRR/DRSS/PRPB 2 2 NKtQDSS - SPLB NRR/DSSA/SRXB 1 1 02 RES/DSIR/EIB 1 1 RGN1 FILE 01 EXTERNAL: EGSG BRYCE,J.H L ST LOBBY WARD 1 1 NRC PDR NSIC MURPHYFG.A 1 1 NSIC POOREFW. NUDOCS FULL TXT 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 ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 30
~ ~ ~ 44 ~ ~ 4 rrte I
i '., Tote I tea'rc ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER N.Y. 14649.0001 ROBERT C. MECREOY TELEPHONE Vice Prerldent AREA CODE 716 546 2700 Cinna Nuclear Production 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.
Ve truly yours, C~
Robert C. Mecredy xc4 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'
