ML17263A247
| ML17263A247 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/21/1993 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| GL-92-01, GL-92-1, NUDOCS 9304270027 | |
| Download: ML17263A247 (3) | |
Text
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ACCESSIGLV NBR:9304270027 DOC.DATE: 93/04/21 NOTARIZED: NO DOCKET ¹ FACXL.'50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester
.G 05000244 AUTH.NAME AUTHOR AFFILIATlON MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3
SUBJECT:
Requests that SECY 93-048 dtd 930225 be revised to indicate that plant reactor vessel currently exceeds 50 ft/lb USE criterion. Actual test data indicates that USE currently exceeds criterion a will exceed limit beyond 21 EFPYs.
DISTRIBUTION CODE:
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TITLE: OR Submittal: General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
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ROCHESTER GAS AND ELECTRIC CORPORATION o
89 EAST AVENUE, ROCHESTER N. Y. 14649-0001 ROBERT C. MECREDY Vice Prerident Cinna Nuclear Production April 21, 1993 TELEPNONE AREACODE 71B 546 2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Washington, D.C.
20555
Subject:
Reactor Vessel Structural Integrity R.E.
Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a):
Letter to A. R. Johnson (NRC) from R.
C. Mecredy (RG&E) dated July 2, 1992 (b):
Letter to Dr. Robert C. Mecredy (RG&E) from A. R. Johnson (NRC) dated March 6, 1992
Dear Mr. Johnson:
SECY 93-048, dated February 25, 1993, indicated that the R.E. Ginna Nuclear Power Plant has reactor vessel welds which have an Upper Shelf Energy (USE) below the 50 ft-lb guidance limit of 10CFR50, App.
G.
This assessment is apparently based on our response to Generic Letter 92-01 (reference a).
In our response, we provided theoretical USE values without taking into account the results of the Ginna reactor vessel surveillance program.
Actual test data from our reactor vessel surveillance program has shown that the USE currently exceeds the 50 ft-lb criterion and is expected to continue to meet or exceed this limit beyond 21 EFPY (beyond at least mid-1997).
The NRC has documented this conclusion in the safety evaluation, dated March 6, 1992, supporting the issuance of Amendment No.
48 to the R.E.
Ginna Nuclear Power Plant license (reference b).
That evaluation states, in part, that "Based on data from surveillance capsule T and on RG 1.99 Rev.
2, the staff has calculated USE at current EFPY (about 15.2) to be 54.2 ft-lb.
The USE at 21 EFPY is calculated to be 52.2 ft-lb, and the End-of-Life (EOL)
USE is expected to be 49.2 ft/lb."
Because SECY-93-048 is being used for more than technical discussions between the Staff and utilities, we request that SECY 93-048 be revised as soon as practicable, to indicate that the Ginna reactor vessel currently exceeds the 50 ft/lb USE criterion.
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We are available to further discuss this with you or to provide additional information.
Very truly yours, REJ4278 Robert C.
Me redy xc: Mr. Allen R. Johnson (Mail Stop 14D1)
Project Directorate I-3 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector