ML20202F820
| ML20202F820 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 12/03/1997 |
| From: | Hosmer J COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20202F824 | List: |
| References | |
| NUDOCS 9712090236 | |
| Download: ML20202F820 (3) | |
Text
Commonweahh I dann Company 1 m) Opus I'lxc 5
Downers Grove,11,6051% 5701 December 3,1997 United States Nuclear Regulatory Commission ATTN. Document Control Desk Washington, D.C. 20555 -
Subject:
SupplementalInformation Pertaining to Byron & Braidwood's Reactor Vessel Integrated Surveillance Program Byron Nuclear Power Station Braidwood Nuclear Power Stations NRC Docket Numbers: 50-454. 50-455. 50-456 and 50-457
References:
1.J. Hosmer letter to NRC dated May 6,1997, transmitting Byron &
Braidwood Reactor Vessel Integrated Surveillance Program,10 CFR 50
}
Appendix H Section III.C.
2.1 Hosmer letter to the NRC dated November 18,1997, transmitting Supplement to the Technical Specification Amendment Request Reference I transmitted the Commonwealth Edison Company's (Comed's) request to integrate the weld metal surveillance program of Byron Unit I and Unit 2, and Braidwood Unit 1 and Unit 2. WCAP-14824, Revision 1," Byron Unit 1 Heat Up and Cool Down Limit Curves for Nonnal Operations and Surveillance Weld Metal Integration for Byron &
Braidwood" was included in that correspondence. Subsequent to that submittal, Comed and the Staff have had several conversations regarding this WCAP. Accordingly, Comed has revised WCAP-14824 to address these comments. Revision 2 contains:
All newly available data based on the June 30,1997, FTI letter INS-97-2526 (referenced in NDIT BYR97-346, Rev. 0). This data has been incorporated into the weld metal best-estimate chemistry values. The new data had no adverse impact.
Irradiation environment analysis. This analysis has been expanded using the October 14,1996, Zion submittal Item 11 as a guide.
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U.S. Nuclear Regulatory Commission December 3,1997 Additional information on presence and location of neutron pads, their impact e
on neutron transport calculation methodology, and dosimetry location.
Clarification and additionaljustification of the Comed commitment to revise fluence estimates using ENDF/B-VI neutron cross-section libraries at the next scheduled capsule withdrawal.
Detailed explanation of the Comed approach to Regulatory Guide 1.99, Revision 2 margin term and ratio procedure.
Corrected approach to surveillance data credibility evaluation with detailed explanation.
Attached is WCAP-14824, Rev. 2 and its associated errata (Westinghou3e Letter CAE-97 220/ CCE-97-304) for your review. Additionally, Reference 2 transmitted a supplement to amend the Technical Specifications regarding the Reactor Coolant System i
Pressure and Temperature Limits, which references the attached WCAP. Please note that the attached errata should be included when reviewing this WCAP. Comed would appreciate your prompt review of the attached WCAP to avoid delays in the restart of l
Byron Unit I for the current Steam Generator replacement outage.
Please address any comments to this oflice.
Sincerely, rb0lhw John B. Hosmer Engineering Vice President cc:
Byron /Braidwood Project Manager - NRR Senior Resident Inspector - Byron Senior Resident Inspector - Braidwood Regional Administrator - Rill Office of Nuclear Safety - IDNS K:WLD BYRDWDSoRPFTLRHB2Ax
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DearMr. Adans:
The
, arifloodons ofWCAP-14824, Rev. 2 mi provided per danussions wkh Mr. Toni d
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. on 5 on c, derd smesam under the woes" should med, sumidwood I X was '
at the and ofcycle 4 and Braidwood 2 espoule X was wkhdrawn aser the end arevde 4.
On page C-5 an Appendbt C,lasi parasraph; the thled seneseos abould ned Table A-2 not.
Pleans insert this lauer into your @ ofWCAP-14:24 Rev. 2 (
transmined per letter CAE 97-218CCE-97-302 to Messrs. Adams, and SpryofConf#.
Ifyou or need Mth information, pisue comance ene or Mr. Tom J ' or 5m an(412)37 vayaulyyoun, WESTDICHOUEEMECTRIC MOf C%Ah.
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