ML17262A481
| 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
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0 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR: 9105210244 DOC. DATE: 91/05/14 NOTARIZED: NO DOCKET g FACIL: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 JOHNSON,A.R. Project Directorate I-3 R
SUBJECT:
Informs of LTOP Setpoint Modification re modify heat/cooldown curves.
D DISTRIBUTION CODE: A053D Submittal:*
COPIES RECEIVED:LTR 2 ENCL 8 SIZE:
TITLE: OR Updated FSAR (50.71) and Amendments 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 PD1-3 LA PD1-3 PD D JOHNSON,A D
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NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISIS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ) ENCL
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III IZZuiZZ ROCHESTER GAS AND ELECTRIC CORPORATION 8P 89 EAST AVENUE, ROCHESTER N.K 14649-0001 ROBERT C MECREDY TELEPHONE Vice Prerldent AREA COBE 71B 546 2700 Clnna Nudear Production May 14, 1991 U.S. Nuclear Regulatory Commission Document Control Allen R. Johnson Desk'ttn:
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 identified be noted that the weld control number as Seam WR-19 in some RG&E and Westinghouse SA-847 documents.
is These two designations identify the same weld.
Very truly yours, I Robert C. Mecredy
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0AO xc: Mr. Allen R. Johnson (Mail Stop 14D1)
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