ML20063C811
| ML20063C811 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/02/1994 |
| From: | Marsh W SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-01, GL-92-1, NUDOCS 9402070188 | |
| Download: ML20063C811 (2) | |
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7 Southem Califomia Edison Company 23 PARKER S1 REE'T IHVINE. CALFORNIA 92718 February 2,1994 wAuEnc m Man MANAGEM UF HUf 4 E' AR HE QUE.A TOMy AF y Ain$
(714) 4tbe.4403 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
Subject:
Docket Nos. 50-361 and 50-362 Revision to Supplemental Response to Generic Letter 92-01, Revision 1, " Reactor Vessel Structural Integrity, 10 CFR 50.54(f)" San Onofre Nuclear Generating Station Units 2 and 3
References:
1.
R. M. Rosenblum to V. S. Nuclear Regulatory Commission Document Control Desk, Response to Generic Letter 92-01, Revision 1, " Reactor Vessel Structural Integrity,10 CFR 50.54(f)" San Onofre Nuclear Generating Station, Units 2 and 3, July 6, 1992 2.
Walter C. Marsh to U. S. Nuclear Regulatory Commission Document Control Desk, Docket Nos. 50-361 and 50-362 Supplemental Response to Generic Letter 92-01, Revision 1,
" Reactor Vessel Structural Integrity,10 CFR 50.54(f)" San Onofre Nuclear Generating Station Units 2 and 3, January 29, 1993 On March 6, 1992, the NRC issued Generic Letter 92-01, Revision 1, to obtain j
information needed to assess compliance with the requirements and commitments regarding reactor vessel integrity. References 1 and 2 provided our initial
-I and supplemental responses to Generic Letter 92-01. The supplemental response 1
indicated that we needed to obtain additional information to confirm certain heat numbers and assumptions contained in our response. At that time we-anticipated that this follow-up activity would be submitted to the NRC.by February 2,1994.
j The final information was transmitted to Edison from ABB/CE by letter dated-January 4,1994. Although we anticipated that the ABB/CE data would' validate
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the assumptions made in our supplemental response, the data contained
- previously unidentified heat numbers. We now believe that'a complete revision to our Generic Letter 92-01 response is needed to incorporate the new data.
While this new data will allow a more accurate evaluation of the Units 2 and 3 reactor vessel structural integrity, we do not expect that it will change any of the analysis results contained in Reference 2.
The revised response will be submitted by June 27, 1994.
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If you have questions or require further information, please let me know.
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Sincerely,.
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K. E. Perkins, Jr., Acting Regional Administrator, NRC Region V J. A. Sloan, NRC Senior Resident Inspector, San Onofre Units 2 & 3 M. B. Fields, NRC Project Manager, San Onofre Units 2 and 3 i
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