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| | issue date = 12/17/1998 | | | issue date = 12/17/1998 |
| | title = Forwards LER 98-004-00 Re Improperly Performed Surveillance Due to Procedure non-adherence.Licensee Does Not Agree That, for Equipment Item That Is Otherwise Known to Be Operable, Reporting of Missed Surveillance Should Be Required | | | title = Forwards LER 98-004-00 Re Improperly Performed Surveillance Due to Procedure non-adherence.Licensee Does Not Agree That, for Equipment Item That Is Otherwise Known to Be Operable, Reporting of Missed Surveillance Should Be Required |
| | 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:CATEGORY 1REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) | | {{#Wiki_filter:CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| | ACCESSION NBR:9812240091 DOC.DATE: 98/12/17 . NOTARIZED: NO - DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAM i AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp. |
| | RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Forwards LER 98-004-00 re improperly performed surveillance due to procedure non-adherence. | | Forwards LER 98-004-00 re improperly performed surveillance due to procedure non-adherence. Licensee does not agree that, for equipment item that is otherwise known to be operable, A |
| Licensee does not agree that, for equipment item that is otherwise known to be operable,-reporting of missed surveillance'hould be required.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR I ENCL I SIZE: Zr$TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.A E 05000244 Q NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72) | | -reporting of missed surveillance'hould be required. |
| .ACCESSION NBR:9812240091 DOC.DATE: 98/12/17.NOTARIZED:
| | DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR I ENCL I SIZE: Zr $ |
| NO-DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAM i AUTHOR AFFILIATION MECREDY,R.C.
| | TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. E NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72) . 05000244 Q |
| Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: AEOD/SPD CE E NRR/DE/EELB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RGN1 FILE 01 COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME VZSSING,G.
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 PD 1 1 VZSSING,G. 1 1 INTERNAL: AEOD/SPD 2 2 AEOD/SPD/RRAB 1 1 CE E 1 1 NRR/DE/ECGB 1 1 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOHB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 RES/DET/EIB 1 1 RGN1 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE,J H 1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 |
| AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HOHB NRR/DRPM/PECB RES/DET/EIB COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 EXTERNAL: L ST LOBBY WARD NOAC POORE,W.NRC PDR 1 1 1 1 1 1 LITCO BRYCE,J H NOAC QUEENER,DS NUDOCS FULL TXT 1 1 1 1 1 1%epee P A s NTS thy N%'Dt 1I"-I-"c C>"'"'0 S" M'J-'CUR JA~C..ORGA 4 ZA EON RSMOV~"RCM I.STRT U ON L~'hl t g t Is+1 I 0~'rt FULL TEXT CONVERSION REQUIRED warrior AND ROCHESTER GAS AND EIECTRIC CORPORATION
| | %epee P A s NTS |
| ~B9 EASTAVENUE, ROCHESTER, N.Y 14649-000I AREA CODE 716 5'.2700 ROBERT C.MECREDY Vice President Nvcteor Operations December 17, 1998 U.S.Nuclear Regulatory Commission | | "-I - "c thy C |
| ~Document Control Desk Attn:Guy'S.Vissing Project Directorate I-1 Washington, D.C.20555 | | N |
| | % 'Dt 1I |
| | '0 S " M'J |
| | 'hl |
| | -'CUR JA~ |
| | ~ |
| | C.. ORGA 4 ZA EON RSMOV ~ "RCM t g t Is+ 1 I 0 ~ 'rt I.STRT U ON L FULL TEXT CONVERSION REQUIRED warrior |
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| | AND 14649-000I AREA CODE 716 5'.2700 ROCHESTER GAS AND EIECTRIC CORPORATION ~ B9 EASTAVENUE, ROCHESTER, N. Y ROBERT C. MECREDY Vice President Nvcteor Operations December 17, 1998 U.S. Nuclear Regulatory Commission |
| | ~ |
| | Document Control Desk Attn:Guy 'S. Vissing Project Directorate I-1 Washington, D.C. 20555 |
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| ==Subject:== | | ==Subject:== |
| LER 1998-004, Improperly Performed Surveillance, Due to Procedure Non-Adherence, Resulted in Condition Prohibited by Technical Specifications R.E.Ginna Nuclear Power Plant Docket No.50-244 | | LER 1998-004, Improperly Performed Surveillance, Due to Procedure Non-Adherence, Resulted in Condition Prohibited by Technical Specifications R.E. Ginna Nuclear Power Plant Docket No. 50-244 |
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| | ==Dear Mr. Vissing:== |
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| ==Dear Mr.Vissing:==
| | In accordance with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (i) (B), which requires a report of, "Any operation or condition prohibited by the plant's Technical Specifications", |
| In accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(i)(B), which requires a report of,"Any operation or condition prohibited by the plant's Technical Specifications", the attached Licensee Event Report LER 1998-004 is hereby submitted. | | the attached Licensee Event Report LER 1998-004 is hereby submitted. |
| Although we are submitting this LER in accordance with the guidance provided in NUREG-1022, Revision 1, we do not agree that, for an equipment item that is otherwise known to be operable, the reporting of a missed surveillance should be required.The Ginna Station Technical Specifications Bases for Surveillance Requirement | | Although we are submitting this LER in accordance with the guidance provided in NUREG-1022, Revision 1, we do not agree that, for an equipment item that is otherwise known to be be operable, the reporting of a missed surveillance should required. The Ginna Station Technical Specifications Bases for Surveillance Requirement 3.0.3 allows the plant to defer declaring equipment inoperable for up to 24 hours for a missed surveillance. No Limiting Condition for Operation (LCO) is entered and no equipment is declared inoperable, surveillance test proves that the equipment is operable. Since if the resultant there is no operation or condition prohibited by the Technical Specifications, 10 CFR 50.72 and 10 CFR 50.73 do 'not apply, and no report should be made. |
| | /f~ P 98i224009i 98i21T PDR ADOCK 05000244 PDR .' |
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| ====3.0.3 allows====
| | The philosophy behind the Ginna Station Technical Specifications and Bases were presented to the NRC in a letter from RG&E (Mecredy) to NRC, dated May 14, 1996, which is attached. RG&E has never received a formal response to this letter, and hereby requests such a response. We note that the advanced notice of ProPosed rulemaking (ANPR) for 10 CFR 50.72 and 10 CFR 50.73, dated July 23, 1998, indicates that singular events such as missed surveillances should not be reported. We believe that a conforming response to our May 14, 1996, letter will supersede NUREG-1022, Revision 1, which is a guidance document, and allow us not to report missed surveillances for operable equipment in the future. |
| the plant to defer declaring equipment inoperable for up to 24 hours for a missed surveillance. | | This event has in no way affected the public's health and safety. |
| No Limiting Condition for Operation (LCO)is entered and no equipment is declared inoperable, if the resultant surveillance test proves that the equipment is operable.Since there is no operation or condition prohibited by the Technical Specifications, 10 CFR 50.72 and 10 CFR 50.73 do'not apply, and no report should be made./f~P 98i224009i 98i21T PDR ADOCK 05000244 PDR.'
| | Ver ruly your Robert C. Mecredy Attachments: 1. LER 1998-004 |
| | : 2. Letter dated May 14, 1996 xc: U.S. Nuclear Regulatory Commission Mr. Guy S. Vissing (Mail Stop 14C7) |
| | Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector |
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| The philosophy behind the Ginna Station Technical Specifications and Bases were presented to the NRC in a letter from RG&E (Mecredy)to NRC, dated May 14, 1996, which is attached.RG&E has never received a formal response to this letter, and hereby requests such a response.We note that the advanced notice of ProPosed rulemaking (ANPR)for 10 CFR 50.72 and 10 CFR 50.73, dated July 23, 1998, indicates that singular events such as missed surveillances should not be reported.We believe that a conforming response to our May 14, 1996, letter will supersede NUREG-1022, Revision 1, which is a guidance document, and allow us not to report missed surveillances for operable equipment in the future.This event has in no way affected the public's health and safety.Ver ruly your Robert C.Mecredy Attachments:
| | t,}} |
| 1.LER 1998-004 2.Letter dated May 14, 1996 xc: U.S.Nuclear Regulatory Commission Mr.Guy S.Vissing (Mail Stop 14C7)Project Directorate I-1 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 U.S.NRC Ginna Senior Resident Inspector t,}}
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Forwards Revised Ginna Station EOPs & Procedures Index
ML17265A6121999-03-29029 March 1999
Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231
ML17265A6041999-03-24024 March 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618
ML17265A5641999-03-0101 March 1999
Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl
ML17265A5671999-03-0101 March 1999
Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl
ML17265A5551999-02-25025 February 1999
Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr
ML17265A5561999-02-22022 February 1999
Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d)
ML17265A5451999-02-12012 February 1999
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 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9812240091 DOC.DATE: 98/12/17 . NOTARIZED: NO - DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAM i AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)
SUBJECT:
Forwards LER 98-004-00 re improperly performed surveillance due to procedure non-adherence. Licensee does not agree that, for equipment item that is otherwise known to be operable, A
-reporting of missed surveillance'hould be required.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR I ENCL I SIZE: Zr $
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. E NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72) . 05000244 Q
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 PD 1 1 VZSSING,G. 1 1 INTERNAL: AEOD/SPD 2 2 AEOD/SPD/RRAB 1 1 CE E 1 1 NRR/DE/ECGB 1 1 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOHB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 RES/DET/EIB 1 1 RGN1 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE,J H 1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1
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AND 14649-000I AREA CODE 716 5'.2700 ROCHESTER GAS AND EIECTRIC CORPORATION ~ B9 EASTAVENUE, ROCHESTER, N. Y ROBERT C. MECREDY Vice President Nvcteor Operations December 17, 1998 U.S. Nuclear Regulatory Commission
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Document Control Desk Attn:Guy 'S. Vissing Project Directorate I-1 Washington, D.C. 20555
Subject:
LER 1998-004, Improperly Performed Surveillance, Due to Procedure Non-Adherence, Resulted in Condition Prohibited by Technical Specifications R.E. 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) (i) (B), which requires a report of, "Any operation or condition prohibited by the plant's Technical Specifications",
the attached Licensee Event Report LER 1998-004 is hereby submitted.
Although we are submitting this LER in accordance with the guidance provided in NUREG-1022, Revision 1, we do not agree that, for an equipment item that is otherwise known to be be operable, the reporting of a missed surveillance should required. The Ginna Station Technical Specifications Bases for Surveillance Requirement 3.0.3 allows the plant to defer declaring equipment inoperable for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for a missed surveillance. No Limiting Condition for Operation (LCO) is entered and no equipment is declared inoperable, surveillance test proves that the equipment is operable. Since if the resultant there is no operation or condition prohibited by the Technical Specifications, 10 CFR 50.72 and 10 CFR 50.73 do 'not apply, and no report should be made.
/f~ P 98i224009i 98i21T PDR ADOCK 05000244 PDR .'
The philosophy behind the Ginna Station Technical Specifications and Bases were presented to the NRC in a letter from RG&E (Mecredy) to NRC, dated May 14, 1996, which is attached. RG&E has never received a formal response to this letter, and hereby requests such a response. We note that the advanced notice of ProPosed rulemaking (ANPR) for 10 CFR 50.72 and 10 CFR 50.73, dated July 23, 1998, indicates that singular events such as missed surveillances should not be reported. We believe that a conforming response to our May 14, 1996, letter will supersede NUREG-1022, Revision 1, which is a guidance document, and allow us not to report missed surveillances for operable equipment in the future.
This event has in no way affected the public's health and safety.
Ver ruly your Robert C. Mecredy Attachments: 1. LER 1998-004
- 2. Letter dated May 14, 1996 xc: U.S. Nuclear Regulatory Commission Mr. Guy S. Vissing (Mail Stop 14C7)
Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector
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