ML20211B333

Forwards Proprietary Calculation Rev 0 to ESI150, Allowable Heat Intensity in Cable Trays, in Response to RAI Re Ampacity Derating Analyses.Affidavit & Request for Withholding Info,Encl.Calculation Withheld

ML20211B333
Person / Time
Site:	Byron, Braidwood
Issue date:	09/19/1997
From:	Hosmer J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20046D808	List: ML20211B333 ML20211B349
References
NUDOCS 9709250166
Download: ML20211B333 (3)

Text

I Commonw ohh 14 hum company i 100 Opm ihre Downer [Grme, IT. 9)515 5'01 September 19,1997 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk

Subject:

Response to the NRC Request for Additionallnformation Regarding Ampacity Derating Analyses Byron Nuclear Power Station, Units 1 and 2 Facility Operating Licenses, NPF-37 and NPF-66 NRC Docket Nos. 50-454 and 50-455 Braidwood Nuclear Power Station, Units 1 and 2 Facility Operating Licenses, NPF-72 and NPF-77 NRC Docket Nos. 50-456 and 50-457

Reference:

1) D. Saccomando to USNRC letter dated March 21,1996.

2) R. A. Capra to D. L. Farrar letter dated une 12,1996.

3) J. Hosmer to USNRC letter dated July 12,1996.

4) G. Dick, Jr. to I. Johnson letter dated July 9,1997.

Reference 1, provided the Commonwealth Edison Company (Comed) response regarding the ampacity derating analyses previously performed for Byron and Braidwood. Reference 2, was the NRC RAI that requested a description of the detailed plan and schedule of the actions to resolve the stated ampacity derating issues. In reference 3 that detailed plan and schedule was provided for Byron and Braidwood.

Reference 4, is the NRC RAI that requests further information. Attachment 1 of this letter provides the Comed response to that request.

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U.S. Nuclear Regulatory Commission O- September 19,1997 In reference 4, the NRC staff states that calculation BYR96-082 / BRW-96-194, Revision 0 introduced a new methodology and addressed ampacity analyses for single cable trays in "special" barrier configuration, multiple horizontal trays in a single fire barrier enclosure, single vertical cable tray risers and multiple cable tray risers in a singic fire barrier enclosure. Comed would like to clarify that calculation BYR96-082 /

BRW 96-194, Revision 0 did not introduce a new methodology, but rather applied the existing methodology in more detail and modeled more specifically for the plant configurations, listed.

Further, Comed wants to ensure that the NRC staff has the appropriate information, needed to complete the review of the ampacity derating information provided for Byron and Braidwood. Therefore, should there be any additional questions, Comed is available to meet and strongly encourages a meeting with the NRC staff, as necessary, to address any questions and to bring this matter to closure. Such a meeting may provide the best means of presenting and explaining the Comed approach.

Please note that calculation ES1150-1 contains information proprietary to Sargent &

Lundy (S&L) and is supported by an affidavit signed by S&L, the owner of the information. The affidavit sets forth the basis on which the informatiert 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 Commonwealth Edison, be withheld from public disclosure in accordance with 10 CFR 2.790 of the Commission's regulations.

Correspondence with respect to the proprietary aspects of the items should be addressed to K. Kostal, Executive Vice President, Sargent and Lundy,55 East Monroe St., Chicago, IL 60603-5780.

To the best of my knowledge and belief, the statements contained in this document are true and correct.

If there are any further questions conceming this matter, please contact our Nuclear Licensing office.

Sinurely,

, n0 wn John B. Hosmer Engineering Vice President k nla 19 bwd rai ac2

U.S. Nuclear Regulatory Commission -3 September 19,1997 Subscribed and sworn to fore e ..

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Attachments:

1) Response to RAI

2) Application for withholding Proprietary Information

3) Calculation #ES1150-1, Rev. O.

cc: Byron Project Manager NRR Braidwood Project Manager-NRR Senior Resident inspector Byron Senior Resident inspector Braidwood Regional Administrator- Rill Office of Nuclear Facility Safety-IDNS l

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