ML20141M448
| ML20141M448 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 08/25/1992 |
| From: | Simpkin T COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19303F044 | List: |
| References | |
| NUDOCS 9208280207 | |
| Download: ML20141M448 (2) | |
Text
Commonwezith Edison
=
1400 Opus Place Downers Grove, Illinois 00515 August 25,1992 Dr. Thomas E. Murley Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk
Subject:
Byron /Braidwood Stations Flaw Evaluation Methodology for RHR Heat Exchanger Nozzle to Shell Wolds NBCLDocketRoJ0d5L50d55J0-45SJMEZ
Reference:
November 13,1991 T. Simpkin ltr. to Dr. T. Murley November 21,1991 R. Pulsifer lir. to T. Kovach
Dear Dr. Murley:
Reference (a) transmitted a fracturo mechanics ovaluation used to disposition weld indications in the Braidwood Unit 2 Rerldual Heat Removal (RH) heat exchangers. With reference (b), the methodology Wr.s approved for use on the RH heat exchanger nozzles for both the Byron and Braidwood Stations, Units 1 and 2.
The subject heat exchangers and associated piping are ASME Class 2 components. The currently accepted methodology uses the ASME Class 1 acceptance criteria oecause no acceptance criteria for dispositioning flaws in Class 2 components is currently contained in Section XI of the ASME Code.
The purpose of this letter is to submit for NRC review and approval a methodology to disposition flaws in Class 2 componems. The revised acceptance criteria has been developed utilizing the original design criteria for the RH heat exchangers and preserves the design margin in the presence of a flaw.
Enclosed are:
1.
1 copy of WCAP 13454," Fracture Mechanics Evaluation, Byron and Braldwood Units 1 and 2, Residual Heat Exchan Outlet Nozzles" dated August 1992 (Proprietary)ger Tube Side Inlet an 2,
1 copy of WCAP-13455,
- Fracture Mechanics Evalution, Byron and Braidwood Units 1 and 2, Residual Heat Exchanger Tube Side Inlet and i
Outlet Nozzles" dated August 1992 (Non Proprietary).
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ZNLD/1324/1
Dr. T.E. Murley August 24,1992 Also enclosed are a Westinghouse authorization letter, CAW 92 344, accompanying affidavit, Proprietary Information Notice, and Copyright Notice.
As item 1 contains information proprietar to Westinghouse Electric Corporation,it is supported by an affidavit slyned b Westinghouse, the owner of the inforrnation. The affidavit sets forth the bas s on w ich the nformation may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations.
Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.790 of the Commission's regulations.
Correspondence with respect to the proprietary aspects of the items listed above or the supporting Westinghouse Affiday t should reference CAW 92 344 and should be addressed to Nicholas J. Liparuto, Manager of Nuclear Safety and Regulatory Activities, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pennslyvania 15230 0355.
The next scheduled inspections where this methodology may be needed are in September,1992 for Braidwood Unit 1, and in the Spring of 1993 for Byron Unit 1.
Please direct any questions you may have concerning this matter to this Sincerely, Ql<Mw f/h 2W 4
T.W. Simpkin Nuclear Licensing Administrator cc:
S. DuPont - Braidwood (WC AP 13455)
W. Kropp Byron WCAP 13455)& 13455)
R. Pulsifer - NRR WCAP 13454 B. Clayton - Rlli ( CAP 13455)
J. Jacobsen - Alli (WCAP 13455) l l
l ZNLD/1324/2 i
.