ML20210H450
| ML20210H450 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 08/08/1997 |
| From: | Hosmer J COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9708140017 | |
| Download: ML20210H450 (3) | |
Text
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Commonwt alth I dmn Compan) 14m Opus Pla( c Downers Grm r. Il Ntil 5 $701 August 8,1997 United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk
Subject:
Byron Nuclear Power Station, Units I and 2 Facility Operating Licenses NPF-37 and NPF-66 NRC Docket Numbers 50-454 and 50-455 Braidwood Nuclear Power Station, Units 1 and 2 Facility Operating Licenses NPF-72 and NPF-77 NRC Docket Numbers: 50-456 and 50-457 Primary Containment and Reactor Coolant System Amendment RAI
Response
Reference;
- 1. J. Ilosmer (Comed) Letter to USNRC, Primary Containment and Reactor Coolant System Amendment, dated January 30,1997.
- 2. NRC P.cquest for AdditionalInformation Regarding Primary Containment and Reactor Coolant System, dated February 10,1997.
- 3. J. Ilosmer (Comed) Letter to USNRC, Response to Request for Additional Information Regarding Primary Cor.tainment and Reactor Coolant System, dated May 23,1997.
4, T. Maiman/K Graesser Letter to USNRC, Request for Information Pursuant to 10 CRF 50.54(f) Regarding Adequacy and Availability of Design Bases Information, dated February 6,1997.
In Reference 1, Comed submitted a License Amendment Request to the NRC to incorporate the effect of the increased reactor coolant system volume resulting from the
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planned replacement of the steam generators at Byron, Unit I and Braidwood, Unit 1. in /
Reference 2, NRC requested additional information regarding the engineering
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methodologies and analyses. To expedite the review Reference 3 contained the response to Questions 1-3. The response to Question 4 is being provided in this submittal.
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. j USNRC Please address any questions or comments to this omce.
Sincerely.
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.- Johr,13. Ilosmer t-Engineering Vice President i-
- Attachment cc:
-A. B. Beach, Regional Administrator - Rlli 1
G, Dick, Byron /Braidwood Project Manager - NRR C. Phillips, Senior Resident inspector Braidwood
- S. Burgess, Senior Resident inspector Byron Omcc of Nuclear Safety -IDNS e
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...s RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING Tile PRIMARY CONTAINMENT AND REACTOR COOLANT SYSTEM VOLUME HYRON/HRAIDWOOD NUCI EAR POWER STATIONS NRC Question 4:
Confirm that any other previous plant modifications that could affect the calculated peak accident pressure have been considered and are reflected in the P. calculation.
Response to Question 4:
As part of any plant modification, the plant design basis is evaluated in accordance with the Comed Design Control Program. For the reasons described in Reference 4, the Byron and Braidwood Stations have concluded that they are configured and operated in a manner that is consistent with their design bases.
As evidenced that the design control process is credible, a validation of all plant modifications since the beginning of plant life was conducted by the corporate engineering group familiar witF Comed's safety analyses. All modifications which potentially affect thc peak containment pressure, P., have been implemented in accordance with this process. Comed has determined that no modifications to date have been made at Byron or Braidwood Stations that would cause an increase to the current P. value (44.4 psig) prior to the proposed revision associated with the steam generator replacement on Byron /Braidwood Units 1.