ML17264A402

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

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: ML17264A402 ML17264A404 ML17264A405
References
GL-96-03, GL-96-3, TAC-M92320, NUDOCS 9603210226
Download: ML17264A402 (5)

Text

CATEGORY j.

r~

REGULATCI INFORMATION DISTRIBUTIONSTEM (RIDE)

ACCESSION NBR:9603210226 DOC.DATE: 96/03/3."5 NOTARIZED: NO DOCKET

FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244

!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 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 LA 1 1 PD1-1 PD 1 1 JOHNSON,A 1 1 INTERNAL:p LE CE ~l 1 1 NRR/DE/EMCB 1 1 NRRQDR H HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

0 U

E N

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D"5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR I

12 ENCL ll

AND ROCHESTER GAS ANDElECTRIC 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:

Application for Amendment to Facility Operating License, Methodology for Low Temperature Overpressure Protection (LTOP) Limits, dated February 9, 1996.

(b) Generic Letter 96-03, Relocation of the 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 for Referencing ofPressure Temperature Limits Report (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 of the methodology for the P/T limits was not requested at the time since the NRC's review of the latest reactor vessel capsule data (which would provide input into the P/T limit determination) was incomplete.

21AA c t"

'tttrt032i0226 cst603i 5 PDR ADQCK 05000244 P PDR

0 ~

gpss lt

However, the NRC's review of the latest reactor vessel capsule data is nearing completion which would allow use of previously 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 following in their LAR:

1. Provide a reference to the NRC approved P/T limit and LTOP limit methodology 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 of the P/T and LTOP limits.

The purpose of this LAR is to provide the reference to the P/T limit and LTOP limit methodology 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 of the 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 of the reactor vessel capsule is complete, RG&:E willprovide 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 of this LAR in order to support a planned startup date of May 30, 1996. To provide a necessary implementation period, RGB should receive NRC acceptance of this LAR by May 10, 1996. The revised PTLR using the proposed methodology will be submitted shortly after receipt of the 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 of Prussia, PA 19406 Ginna Senior Resident Inspector Mr. F. William Valentine, President New York State Energy, Research, and Development Authority 2 Rockefeller Plaza Albany, NY 12223-1253