ML20093G921
| ML20093G921 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 10/13/1995 |
| From: | Saccomando D COMMONWEALTH EDISON CO. |
| To: | NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19317C017 | List: |
| References | |
| NUDOCS 9510190286 | |
| Download: ML20093G921 (2) | |
Text
__
Commonwealth Ihn Company 1400 Opm Place Dow ocrs Grme, llM)$15 October 13,1995 dffice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 i
Attn: Document Control Desk
Subject:
Addendum to WCAP-14273 " Technical Support for Alternate Plugging Criteria with Tube Expansion at Tube Support Plate Intersections for Braidwood-1 and Byron-1 Model D4 Steam Generators" Pertaining to Commonwealth Edison's Request to increase in the Interim Plugging Criteria for Byron Unit 1 and Braidwood Unit 1 Steam Generators NRC Docket Numbers:50-454 and 50-456
References:
1 D. Saccomando letter to the Nuclear Regulatory Commission dated February 7,1995, transmitting Final WCAP-14273 to Support Commonwealth Edison Company Request for a 3 Volt Interim Plugging Criteria for Byron Unit 1 and Braidwood Unit 1 Steam Generators 2.
D. Saccomando letter to the Nuclear Regulatory Commission dated October 3, 1995, transmitting Additional Information Regarding the Increase in the Interim Plugging Criteria for Byron Unit I and Braidwood Unit 1 In Reference I the Commonwealth Edison Comp ly (Comed) submitted WCAP-14273, " Technical Support for Alternate Plugging Criteria with Tube Expansion at Tube Support Plate Intersections for Braidwood -1 and Byron-1 Model D4 Steam Generators" to support the Technical Specification Amendment request for use of a 3 volt interim plugging criteria for Byron Unit I and Braidwood Unit 1 steam generators. The tube support plate analysis contained in that WCAP was based upon the use of TRANFLO as the hydrodynamic load model. Since that submittal, as discussed in Reference 2, Comed has become aware that RELAP5 is the more universally accepted model for the evaluation of the hydrodynamic load produced in a steam generator during a main steam line break event. As a result of this, Comed is submitting an addendum to the original WCAP, which reflect the tube support plate analysis using "RELAP5/ MOD 3 Version 1.1" loads. Attachment A contains the proprietary version to the WCAP addendum and Attachment B contains the non-proprietary version.
Please note that the addendum to WCAP-14273 contains inform? ion proprietary to Westinghouse Electric Corporation and is supported by the attached affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information 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 2.790 of the Commission's regulation.
Correspondence with respect to the proprietary aspects of the items listed above or supporting Westinghouse affidavit should reference CAW-95-892 and should be addressed to N.J. Liparulo, Manager of Nuclear Safety & Regulatory Activities, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355.
i 190069 9510190286 951013 g4 0
PDR ADOCK 05000454 Ch unum Comp.my s\\ Lq, t
' NRC Document Control Desk October 13,1995 If you have any questions concerning this correspondence, please contact this office.
Sincerely,
^
& / -wJu es Denise M. Saccoman(do-Senior Nuclear Licensing Administrator Attachment cc:
D. Lynch, Senior Project Manager-NRR R. Assa, Braidwood Project Manager-NRR G. Dick, Byron Project Manager-NRR S. Ray, Senior Resident Inspector-Braidwood H. Peterson, Senior Resident Inspector-Byron H. Miller, Regional Administrator-RIII i
Office of Nuclear Safety-IDNS i
l l
K:nist,irmare
"