ML17264A597

Forwards Application for Amend to License DPR-18,revising RCS Pressure & Temp Limits Rept,Per GL 96-03.Non-proprietary WCAP-14684 Rept Encl

ML17264A597
Person / Time
Site:	Ginna
Issue date:	09/13/1996
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17264A598	List: ML17264A597 ML17264A599 ML17264A600 ML17309A605 ML17309A606
References
GL-96-03, GL-96-3, TAC-M93827, TAC-M94770, NUDOCS 9609180176
Download: ML17264A597 (5)

Text

CATEGORY 1 REGULMY INFURIATION DZSTRZBUTZOAYSTEM '(RZDS)

ACCESSION NBR:9609180176 DOC.DATE: 96/09/13 NOTARIZED: YES DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 0500024'4

• AUTH. NAME AUTHOR AFFILIATION MECREDY.,R.C. Rochester Gas 6 Electric Corp.

RECIP.NAME . RECIPIENT AFFILIATION v'~d VISSING,G.S.

SUBJECT:

Forwards application for amend to License DPR-18,revising RCS pressure 6 Temp limits rept,per GL 96-03.Non-proprietary C, WCAP-14684 rept encl.

IZ DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: )t(

TITLE: OR Submittal: General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-1 LA 1 1 PD1-1 PD 1 1 VISSING,G. 1 1 INTERNA . FILE CENTER 1 1 NRR/DE/EMCB 1 1 RR DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 EXTERNAL: NOAC 1

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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 12 ENCL'l

AND ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 FASTAVENUE, ROCHESTER, N. Y Iddd9.0001 ARFA CODE716 54'6-2100 ROBERT C. MCCREDY Vice President Nuclear Operations September 13, 1996 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555

Subject:

Application for Amendment to Facility Operating License, Revision to Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)

Rochester Gas Ec Electric Corporation R E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Vissing,

By Reference (a), the NRC approved changes to Administrative Controls Section 5.6.6 of the Ginna Station Technical Specifications which allowed referencing of Revision 1 of the Ginna Station PTLR for the RCS pressure and temperature (P/T) limits and low temperature overpressure protection (LTOP) limits. However, this approval was only provided until December 31, 1996 since the fluence factors used to generate the values provided in PTLR Revision 1 were estimated and not based on the methodology required by Reference (b). As such, the NRC required that RGAE submit a license amendment request (LAR) with a new PTLR by October 2, 1996 using the methodology provided in Reference (b) to allow the NRC time for appropriate review.

Therefore, the purpose of this letter is to provide the required LAR, Revision 2 to the PTLR, and the necessary supporting calculations (i.e., WCAP-14684). Since the P/T limits provided in Revision 2 of the PTLR were developed using the methodology of Reference (b), the LAR will incorporate reference to this methodology into the Administrative Controls section. The LTOP limits are based on the methodology of Reference (c) which is already listed in the Administrative Controls section. As such, these changes will allow RGB to perform future P/T and LTOP evaluations using NRC approved methodology without requiring a potential technical specification change. The change will also complete incorporation of Generic Letter 96-03 into the Ginna Station Technical Specifications since the existing Ginna Station PTLR cannot be revised without a license amendment request (LAR).

9609i80i76 9609i3 05000244 PDR P

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Consistent with Generic Letter 96-03, the proposed revised PTLR contains: (1) reactor vessel material information, (2) LTOP setpoints, and (3) P/T curves. Although the NRC recently approved f

a new pressurized thermal shock (PTS) evaluation for Ginna Station (Ref. (d)), the use o the new fluence values (and additional surveillance capsule chemistry samples) impacts that evaluation as documented in WCAP-14684. In summary, this letter provides the following:

An LARwhich revises Administrative Controls Section 5.6.6 to replace the reference to the May 23, 1996 NRC letter (which is the basis for the existing LTOP and P/T limits) with a new reference containing the NRC's approval of the attached PTLR. In addition, the list of documents containing the approved NRC methodology will be updated to reference WCAP-14040-NP-A for the P/T curves and this letter. The methodology for the LTOP setpoints and enable temperature (Ref. c) remains unchanged. Finally, a typographical error is corrected.

b. Revision 2 of the PTLR which contains the following:

Update of all reactor vessel material information as documented in WCAP-14684.

ii. Revision to the LTOP enable temperature using the methodology submitted as Attachment II to Reference (c) due to the revised P/T curves. The LTOP setpoints remain unchanged as based on the calculation included as Attachment IV to Reference (e).

iii. Update of the P/T curves based on the methodology of Reference (b) as documented in WCAP-14684.

c. WCAP-14684 which provides supporting calculations.

Since the existing PTLR expires on December 31, 1996, RGkE requests NRC consideration of this LARby December 15, 1996 in order to support necessary implementation.

Very truly yours, Robert C. Mecredy MDF$ 870 Attachments

~Rferenc (a) Letter from G.S. Vissing NRC, to R.C. Mecredy, RGB',

Subject:

Issuance ofAmendment No. 64 to Facility Operating License No. DPR-18, RIr. Ginna Niiclear Power Plant (TAC No. M94770), dated May 23, 1996.

(b) WCAP-14040-NP-A, Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves, January 1996.

(c) Letter from R.C. Mecredy, RGB, to A.R. Johnson, NRC,

Subject:

Technical Specification Improvenient Program, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR), dated December 8, 1995.

'd)

Letter from A.R. Johnson, NRC, to R.C. Mecredy, RGB',

Subject:

RIr. Ginna Nuclear Power Plant - Pressurized Thermal Shock I valuation (TAC No. M93827), dated March 22, 1996.

(e) Letter from R.C. Mecredy, RG8'cE, to A.R. Johnson, NRC,

Subject:

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

U.S. Nuclear Regulatory Commission Mr. Guy S. Vissing (Mail Stop 14C7)

PWR Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Mr. Robert Giardina (Mail Stop 011E22)

Technical Specification Branch 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