ML20198G811
| ML20198G811 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 01/07/1998 |
| From: | Johnson I COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9801130123 | |
| Download: ML20198G811 (2) | |
Text
Commonwealth Edimn Company
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1400 Opus Place Downers Grove, IL 60315 5'01 January 7,1997 United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk
Subject:
Byron Nuclear Power Station, Units 1 and 2 Facility Operating Licenses NPF 37 and NPF-66 NRC D2cket Numbers: 50-454 and 50-455 Braidwood Nuclear Power Station, Units 1 and 2 Facility Operating Licenses NPF-72 and NPF-77 NRC Docket Nurthert 50-456 and 50-457 Clarification to the Primary ContairuNnt and Reactor Coolant System Amendment Regarding Equipment Qualification (EQ)
References:
1.
J. liosmer (Comed) Letter to USNRC, Primary Containment and Reactor Coolant System Amendment, dated January 30,1997 2.
USNRC Request for Additional Information Regardine Primary Containment and Reactor Coolant System, dated Mas.ii 20,1997 3.
J. liosmer (Comed) Letter to USNRC, Primary Conthinment and Reactor Coolant System RAI Response, dated May 23,1997 4.
J.1losmer (Comed) Letter to USNRC, Primary Containment and Reactor Coolant Sys+em RAI Response to Question #4, dated August 8,1997 5.
J. Ilosmer (Comed) Letter to USNRC, Primary Containment and Reactor Coolant System Update to RAI Response, dated November 11,1997 6.
J. Hosmer (Comed) Letter to USNRC, Supplement to Technical 2ouvvj Specification Amendment Pertaining to Primary Containment and l
y Reactor Coolant System Volume, dated December 9,1997 l
s 7.
M Lesniak (Comed) and G. Dick (NRC) telecons of l
December 19,1997, and January 5,1998
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USNRC ' January 7,' 1998 In Reference 1; Comed submitted a LSense Amendment Request to the NRC to incorporate the effect of the increased reactor coolant system volume resulting from the planned replacement of the steam generators at Byron,' Unit 1 and Braidwood, Unit 1. In Reference 2, NRC requested additional information regarding the engineering methodologies and analyses, References 3-5 contained the responses to that request.
Reference 6 provided a supplement to the original technical specification amendment request! This letter provides further clarification to the telecons in Reference 7.
The revised temperature profile for the Large Break Loss of Coolant Accident (LB LOCA) with the replacement steam generators is bounded by the EQ envelope currently used to qualify equipment at the Byron and Braidwood Stations.
Please address any questions or comments to this office.
Sincerely, m
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' 1,f 4(L Irene M. Jo: son I,icensing Operations Director cc:
Regional Administrator - RIII-Byron /Braidwood Project Manager - NRR L
Senior Resident inspector - Braidwood Senior Resident Inspector - Byron Office of Nuclear Safety - IDNS K:\\N1,d\\BYRDWDSORIVAEQ. DOC.
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