ML20134A107
| ML20134A107 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 01/21/1997 |
| From: | Lesniak M COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20134A110 | List: |
| References | |
| NUDOCS 9701280179 | |
| Download: ML20134A107 (2) | |
Text
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Commonwealth Edison Company I400 Opus Place
)
Ikswners Grove, 11.60515-5701
)
January 21,1997 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk
Subject:
Supplement to the Application for Amendment to Appendix A, Technical Specifications for Facility Operating Licenses:
Byron Nuclear Power Station, Units 1 and 2 Facility Operating Licenses NPF-37 and NPF-66 NRC Docket Nos. 50-454 and 455 Braidwood Nuclear Power Station, Units 1 and 2 Facility Operating Licenses NPF-72 and NPF-77 NRC Docket Nos. 50-456 and 457 Main Steam Safety Valves Technical Specification Change Request
References:
1.
K.L. Graesser (Comed) to NRC Document Control Desk, " Main Steam Safety Valves Technical Specification Change Request",
dated April 29,1996.
2.
Teleconference between M. Lesniak, et. al., (Comed) and R. Assa (NRC) held on January 7,1997.
In Reference (1) Commonwealth Edison Company (Comed) proposed to amend Appendix A, Technical Specifications, for Facility Operating Licenses NPF-37, NPF-66, NPF-72 and NPF-77 for Byron Nuclear Power Station, Units I and 2 (Byron) and Braidwood Nuclear Power Station, Units 1 and 2 (Braidwood) respectively, pursuant to Title 10, Code of Federal Regulations, Part 50, Section 90 (10 CFR 50.59). Comed proposed to revise Technical Specification Section 3/4.7.1," Turbine Cycle Safety Valves", and the associated Bases.
In Reference (2) Comed agreed to make the following change to the original license amendment request:
Revise Technical Specification Bases 3/4.7.1.1 to clarify that the values calculated from the new equation for the reactor trip setpoint reductions were adjusted lower by 9% power to account for instrument and channel uncertainties.
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8e NRC Document Control Desk January 21,1997 The proposed change in this document is to supersede the corresponding pages in the original license amendment request (Reference 1). There are no changes to the original Attachment C, Evaluation of Significant Hazards Considerations.
To the best of my knowledge and belief, the statements contained in this document are true and correct. In some respect these statements are not based on my personal knowledge, but on information furnished by other Comed employees, contractor employees, and/or consultants. Such information has been reviewed in accordance with company practice, and I believe to be reliable.
Please address any comments to this office.
Sincerely, e
O NW /,
Marcia T. Lesniak Nuclear Licensing Administrator Attachment A: Proposed changes to Appendix A, Technical Specifications for the Byron Nuclear Power Station, Unit I and 2 Attachment B: Proposed changes to Appendix A, Technical Specifications for the Braidwood Nuclear Power Station, Units 1 and 2 i
cc:
A.B. Beach, Regional Administrator, RIII G.F. Dick, Byron Project Manager, NRR R.R. Assa, Braidwood Project Manager, NRR S. Burgess, Senior Resident Inspector, Byron C. Phillips, Senior Resident inspector, Braidwood Office of Nuclear Safety, IDNS k:nla:bybwd mssvsup doc.2