ML17264A402
| ML17264A402 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/15/1996 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17264A403 | List: |
| References | |
| GL-96-03, GL-96-3, TAC-M92320, NUDOCS 9603210226 | |
| Download: ML17264A402 (5) | |
Text
CATEGORY j.
REGULATCI INFORMATION DISTRIBUTIONSTEM (RIDE) r~
ACCESSION NBR:9603210226 DOC.DATE: 96/03/3."5 NOTARIZED: NO
FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
!tAUTH.NAME AUTHOR AFFILIATiON MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
SUBJECT:
Forwards application for amend to license DPR-18,to incorporate methodology for determining LTOP limits into Administrative Controls Section 5.6.6,RCS Pressure Temp Limits Rept.
DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution DOCKET 05000244 E
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 Q
RECIPIENT ID CODE/NAME PD1-1 LA JOHNSON,A INTERNAL:p LE CE
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1 RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR COPIES LTTR ENCL 1
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NOTE TO ALL "RIDS" RECIPIENTS:
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LTTR 12 ENCL ll I
AND ROCHESTER GASANDElECTRIC CORPORA71ON
~ 89 EASTAV&IUE,ROCHESTER, N.Y. 146d9-0001 AREA CODE71rS $6-2700 ROBERT C. MECREDY Vice President Nvdeor operations March 15, 1996 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555
Subject:
Application for Amendment to Facility Operating License Implementation of Generic Letter 96-03 Rochester Gas &Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244
References:
(a)
Letter from R.C. Mecredy, RG&E, to A.R. Johnson, NRC,
Subject:
ApplicationforAmendment to Facility Operating License, Methodologyfor Low Temperature Overpressure Protection (LTOP) Limits, dated February 9, 1996.
(b)
Generic Letter 96-03, Relocation ofthe Pressure Temperature Li1nit Curves and Loiv Teniperature Overpressure Protection System Limits (c)
Letter from L.T. Marsh, NRC, to R.C. Mecredy, RG&E,
Subject:
RLr. Ginna
- Acceptance forReferencing ofPressure Temperature LimitsReport (TAC I/M92320), dated December 26, 1995.
Dear Mr. Johnson,
By Reference (a), RG&E proposed to revise the Ginna Station Technical Specifications to incorporate the methodology for determining the low temperature overpressure protection (LTOP) limits into Administrative Controls Section 5.6.6, RCS Pressure and Temperature Limits Report (PTLR).
This change would allow RG&E to perform future LTOP evaluations using NRC approved methodology without requiring a potential technical specification change.
However, any changes to the RCS pressure temperature (P/T) limits, which are also included in the PTLR, would still require prior NRC review and approval.
Incorporation ofthe methodology for the P/T limits was not requested at the time since the NRC's review ofthe latest reactor vessel capsule data (which would provide input into the P/T limitdetermination) was incomplete.
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lt gpss However, the NRC's review of the latest reactor vessel capsule data is nearing completion which would allow use ofpreviously NRC approved methodology. In addition, Generic Letter 96-03 (Ref.
(b)) has been released by the NRC. This generic letter provides guidance for licensees to relocate the P/T limits and LTOP limits from technical specifications and to provide a mechanism for licensees to make changes to the limits using NRC approved methodology.
RG8cE has previously relocated these limits; however, a license amendment is still required for all changes to the actual limits since the methodology for determining these limits has not been approved for future applications (Ref. (c)). As such, RGB is submitting this license amendment request (LAR) to incorporate the methodology for determining both LTOP limits and RCS P/T limits into Administrative Controls Section 5.6.6 consistent with Generic Letter 96-03. Therefore, this LAR supersedes that provided in Reference (a).
Generic Letter 96-03 requests that licensees provide the followingin their LAR:
1.
Provide a reference to the NRC approved P/T limitand LTOP limitmethodology in the technical specifications; 2.
Develop a PTLR or similar document that contains the figures, values, parameters, and any explanations derived from the methodology; and 3.
Provide other required changes to various technical specifications (e.g., definitions section) to support the relocation ofthe P/T and LTOP limits.
The purpose ofthis LARis to provide the reference to the P/T limitand LTOP limitmethodology in the technical specifications (item 1). A PTLR has been previously developed as part of the conversion to improved standard technical specifications (Ref. (c)). However, the revised PTLR required to support use ofthe proposed methodology is dependant upon the input data which is used, including that derived from the latest reactor vessel capsule.
Once the NRC's review ofthe reactor vessel capsule is complete, RG&:Ewillprovide the revised PTLR using the proposed methodology.
Therefore, item 2 is not being provided at this time. No other technical specification changes are required to implement Generic Letter 96-03 (item 3) since this was addressed during the conversion to the improved technical specifications.
Following the NRC's review of the latest reactor vessel capsule data, it is anticipated that the P/T limits may not be valid for startup from the 1996 refueling outage.
As such, RGkE requests NRC consideration ofthis LARin order to support a planned startup date ofMay 30, 1996. To provide a necessary implementation period, RGB should receive NRC acceptance ofthis LARby May 10, 1996.
The revised PTLR using the proposed methodology willbe submitted shortly after receipt ofthe NRC's review of the latest reactor vessel capsule in order to support this short schedule.
Very truly yours, Robert C. Mecredy MDF>817 Attachments xc:
U.S. Nuclear Regulatory Commission Mr. Allen R. Johnson (Mail Stop 14B2)
PWR Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King ofPrussia, PA 19406 Ginna Senior Resident Inspector Mr. F. WilliamValentine, President New York State Energy, Research, and Development Authority 2 Rockefeller Plaza Albany, NY 12223-1253