ML17264A919

Requests Extension for Using Ginna Station Pressure Temp Limits Rept,Rev 1 Until 971231 from 970731 Based on Listed Reasons

ML17264A919
Person / Time
Site:	Ginna
Issue date:	06/13/1997
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17264A920	List: ML17264A919 ML17264A921
References
TAC-M97313, NUDOCS 9706180461
Download: ML17264A919 (6)

Text

CATEGORY REGULA ..Y INFORMATION DISTRIBUTIO . YSTEM (RIDS)

ACCESSION NBR:9706180461 DOC.DATE: 97/06/13 NOTARIZED: NO DOCKET FAClL: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 VISS:NG,G.S.

SUBJECT:

Requests extension for using Ginna Station Pressure Temp Limits Rept,rev 1 until 971231 from 970731 based on listed reasons.

DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR ( ENCL ( SIZE:

TITLE: OR Submittal: General Distribution T NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL 0

PD1-1 LA 1 1 PDl-1 PD 1 1 VISSING, G. 1 1 INTERNA . FIL CENTER 1 1 NRR/DE/ECGB/A 1 1 1 1 NRR/DRCH/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

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 13 ENCL 12

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AND ROCHESTER GAS AIVDELECTRIC CORPORATION ~ 89 EASTAYENLIE, ROCHESTER, N. Y 14649.0001 AREA CODE7I6 546-27M ROSERT C. MECREDY Vice President June 13, 1997 Hvcteor Operotions U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy Vissing Project Directorate I-1 Washington, D.C. 20555

Subject:

Request to Extend Time for Approval of Revision of Pressure Temperature Limits Report (PTLR) to December 31, 1997 R.E. Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a): Letter from Guy S. Vissing, (NRC), to Robert C. Mecredy, (RG&E) "R.E. Ginna Acceptance of Request to Extend Time for Approval of Revision of Pressure Temperature Limits Report (PTLR) (TAC No. M97313)," dated December 10, 1996

Dear Mr. Vissing:

The referenced letter granted Rochester Gas and Electric (RG&E) an extension to July 1, 1997 to submit revision 2 to the Ginna Station Pressure Temperature Limits Report (PTLR). The extension was granted to allow for resolution of instrument inaccuracies that affected LTOP enable temperature and reactor vessel bolt-up temperature. It was found, during this resolution process, that the instrumentation uncertainties also impacted the LTOP pressure setpoint such that RG&E will seek an exemption to apply the guidance provided in American Society of Mechanical Engineers (ASME) Code Case N-514, "Low Temperature Overpressure Protection (LTOP)", for the pressure setpoint of the LTOP function. This request for exemption has been submitted. However, to allow for adequate time for NRC review, RGE requires an extension for using the Ginna Station PTLR revision 1 until December 31, 1997 from July 1, 1997. This request, is based on:

a ~ There was no technical reason for selecting the July 1, 1997 date since the fluence factor values used by RG&E were an engineering based conservative estimate based on previous Westinghouse experience in this area. As a result of further analysis, it was determined that these fluence factors were within 34 of each other. Instead, the date was chosen to ensure that a rapid closure of this issue would be obtained so that RG&E could place the PTLR under licensee control as originally intended.

b. The existing pressure/temperature (P/T) curves are valid until 22 effective full-power years (EFPY) which is not expected to be reached at Ginna Station until late 1998.

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c. RGGE has submitted a request to allow the use of ASME Code Case N-514 to resolve the instrument uncertainty issues.

Your action on this item is requested by June 30, 1997 to avoid an unscheduled plant shutdown. Should you have any further questions.

concerning this request, please contact George Wrobel at (716) 724-8070.

Very truly yours, Robert C. Mecredy REJ4466 xc: Mr. Guy Vissing (Mail Stop 14B2)

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

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