ML20069P569

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Forwards Nonproprietary WCAP-14047 & Proprietary WCAP-14046, Braidwood Unit 1 Technical Support for Cycle 5 SG Interim Plugging Criteria, in Response to Request for Addl Info Re Util 940425 Emergency TS Amend to Section 3/4.4.5
ML20069P569
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 06/10/1994
From: Saccomando D
COMMONWEALTH EDISON CO.
To: Russell W
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML19304C288 List:
References
NUDOCS 9406240252
Download: ML20069P569 (2)


Text

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CN Commonwohlth Edison June 10,1994

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Downers Grove. Illinois 60515 Mr. William Russell Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk

Subject:

Braidwood Station Unit 1 Additional Information Regarding Technical Specification Amendment for Section 3/4.4.5 NRC Docket No. 50-456

References:

1)

D. M. Saccomando letter to W. Russell transmitting Emergency Technical Specification dated April 25,1994 l

2)

R. Assa letter to D. Farrar transmitting Safety Evaluation for Unit 1 Steam Generator IPC '

Dear Mr. Russell:

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Reference 1 letter transmitted Commonwealth Edison Company's (CECO) request for an Eraergency Technical Specification amendment to Section 3/4.4.5. This amendment request was subsequently granted and transmitted in Reference 2. In that April 25th letter, CECO submitted NSD-TAP-3069, "Braidwood 1: Tec_ nical i

Support for Cycle 5 S/G Interim Plugging Criteria, Pre-WCAP Release," dated April 21,1994, and committed to forwarding to the Nuclear Regulatory Commission (NRC) the finalized version of that Pre-WCAP. Attached you will find WCAP-14046, a summary in part of the updates to the Pre-WCAP is as follows:

a section was added summarizing acceptability of the use of the TRANFLO code including consideration of prior NRC clarification and editorial changes to outlier data evaluation modification to Steam Line Break leak rate methodology description of the rotating pancake coil sampling plan for intersections with dents or residual signals was added l

clarification made to Braidwood-1 IPC description to resolve review comments I

9406240252 940610 DR ADOCK 05000456 PDR I

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m Mr. Russell June 10,1994 It is CECO's understanding that review of WCAP-14046, will disposition outstanding technical issues related to IPC for Braidwood Unit 1, in particular resolution of the leakage portion. If the Staff has any additional questions, we request that they be expeditiously communicated to CECO.

Enclosed please find one copy of WCAP-14046 (proprietary) and one copy of WCAP-14046 (non-proprietary). Also enclosed are a Westinghouse authorization letter, CAW-94-635, accompanying affidavit, Proprietary Information Notice and Copyright Notice.

As WCAP-14046 contains information proprietary to Westinghouse Electric Corporation, it is supported by an 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 Section 2.790 of the Commission's regulations.

Correspondence with respect to the proprietary aspects of the items listed above or the supporting Westinghouse Affidavit should reference CAW-94-635 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.

Please address any comments or questions regarding this matter to this office.

Sincerely,

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- w aJe Denise M. Saccomando Nuclear Licensing Administrator Attachments cc:

R.R. Assa, Braidwood Project Manager-NRR S. G. Dupont, Senior Resident Inspector-Braidwood J. B. Martin, Regional Administrator-Region III Office of Nuclear Facility Safety k:nla\\bwd\\sgsupl\\2