ML20073D096
| ML20073D096 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 04/23/1991 |
| From: | Schuster T COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| TAC-79082, TAC-79083, TAC-79084, TAC-79085, NUDOCS 9104260164 | |
| Download: ML20073D096 (2) | |
Text
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April 23,1991 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn: Document Control Desk
Subject:
Byron Station Units 1 and 2 Draldwood Station Units 1 and 2 Information regarding an Application for Amendment to Facility Operating Licenses NPF 37/66 & NPF 72/77 Appendix A, Technical Specifications TAC # 79082/79083 and 79084/79085 NRCDocketNosm50 45#455_ nod 50-456L457
Reference:
a) October 26,1990 letter from T. Schuster to Dr. T. Murley containing an application for Amendment to the Byron /Braidwood Facility Operating Licenses
Dear Dr. Murley:
In Reference (a), pursuant to 10 CFR 50.90, Commonwealth Edison Company (CECO) proposed to amend Appendix A, Technical Specifications of Facility Operating Licenses NPF-37/66 and NPF.72/77 for Byron /Braldwood Stations. The proposed amendment /evises a portion of Technical Specificat!on Tables 2.21 and 3.3 4, Reactor Trip System Instrumentation Trip Setpoints and Engineered Safety Features Actuation System instrumentation Trip Setpoints respectively, to reduce the setpoint for Low-Low Steam Generator Level Reactor Trip and Auxiliary Feedwater Initiation from 40.8% to 34.8% level for the Unit 1 Model D-4 Steam Generators. This setpoint reduction utilized existing excess margin present in the original 40.8% setpoint.
J' By this letter CECO requests that reviews and processing of the referenced application for amendment be delayed until a Setpoint Study being conducted by CECO is completed in June 1991. The scope of the study involves all setpoints provided by Westinghouse for the Byron /Braidwood Stations Technical Specifications including Steam Generator Level setpoints specified for Reactor Trip and Auxiliary Feedwater initiation. The Setpoint Study is a comprehensive review of the design assumptions made by Westinghouse comparing current plant specific data to the original Westinghouse assumptions. The study may result in changes to margin values, therefore, CECO believes the review delay to be a prudent action although the impact of the study on the Steam Generator Level setpoints is unknown at this time.
Commonwealth Edison is notifying the State of Illinois of this information relative to an application for amendment by transmitting a copy of this letter to the designated State Official.
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D,r. Thom s E. Murl;y 2-April 23,1991 To the best of my knowledge and belief the statements contained horein are true and correct. In some respects, these statements are not based on my personal knowledge but upon information received from other Commonwealth Edison and contractor employe_es. Such information has been reviewed in accordance with Company practice and I believe it to be reliable.
Please direct any questions you may have concerning this matter to this office.
Respectfully, T.K. Schuster Nuclear Licensing Administrator cc: W. Kropp Byron S. Dupont - Braidwood A. Hsia - NRR R. Pulsifer - NRR W. Shafer Rlli Office of Nuclear Facility Safety - lDNS State of-County of f
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