ML17262A481

Provides Clarification of Heatup/Cooldown Curves Re Ltop Setpoint Mods

ML17262A481
Person / Time
Site:	Ginna
Issue date:	05/14/1991
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9105210244
Download: ML17262A481 (3)

Text

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM~" 0 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR: 9105210244 DOC.DATE: 91/05/14 NOTARIZED:

NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas 6 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.

Project Directorate I-3

SUBJECT:

Informs of LTOP Setpoint Modification re modify heat/cooldown curves.DISTRIBUTION CODE: A053D COPIES RECEIVED:LTR 2 ENCL 8 SIZE: TITLE: OR Submittal:*

Updated FSAR (50.71)and Amendments NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

DOCKET g 05000244 05000244 R D RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: AEOD/DOA/~

~WF 01 EXTERNAL IHS NSIC COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD1-3 PD NRR/DST 8E2 RGNl NRC PDR SAIC LINERER COPIES LTTR ENCL D D D NOTE TO ALL"RIDS" RECIPIENTS:

D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISIS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 11)ENCL p s w)f ZZZZZ IIIIIII'i<<III IZZuiZZ ROCHESTER GAS AND ELECTRIC CORPORATION sts ltd~Oel Ja 8P'89 EAST AVENUE, ROCHESTER N.K 14649-0001 ROBERT C MECREDY Vice Prerldent Clnna Nudear Production May 14, 1991 TELEPHONE AREA COBE 71B 546 2700 U.S.Nuclear Regulatory Commission Document Control Desk'ttn: Allen R.Johnson Project Directorate I-3 Washington, D.C.20555

Subject:

Heatup/Cooldown Curves and Associated LTOP Setpoint Modification R.E.Ginna Nuclear Power Plant Docket No.50-244

Dear Mr.Johnson:

During the NRC review of RGGE's February 15, 1991 proposed license amendment to modify heatup/cooldown curves and the associated LTOP setpoint to meet Regulatory Guide 1.99, Revision 2 methodology, a question was raised concerning reactor vessel weld material identification.

In Table 5.3-5 of the Ginna Station UFSAR, weld control number SA-847 is identified.

as having a nickel content: of 0.39 weight percent, and.a copper content of 0.20 weight percent-.These values are nominal weld material values.For licensing-purposes, the chemical composition used is.a.more conservative 0.54 weight percent nickel, and 0.25 weight percent copper.These latter values will be reflected in the next UFSAR update, December.1991.It should be noted that the weld control number SA-847 is identified as Seam WR-19 in some RG&E and Westinghouse documents.

These two designations identify the same weld.Very truly yours, I<Nial I HOQ'OO QO~-4$, 0AO ctO IN'A wet N lO'K wQ (hQ Q Robert C.Mecredy GJW/165 xc: Mr.Allen R.Johnson (Mail Stop 14D1)Project Directorate I-3 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I King of Prussia, PA 19406/arrl frrn+7~z, pinna Senior Resident Inspector@f959//p 1%I Y)~0