ML20217K103
| ML20217K103 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 10/08/1997 |
| From: | Hosmer J COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-08, GL-92-8, NUDOCS 9710230214 | |
| Download: ML20217K103 (2) | |
Text
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CommonutAh himn Qinyuny 1400 Opus Plu e e
Dawnen Gnne, n W15 Pol October 8,1997 U. S. Nuclear Regulatory Commission Washington Dd 20555-0001 Attention:
Document Control Desk Fubject:
Submittal of Plant Changest Thermo-Lag Resolution Byron Nuclear Power Station Units 1 and 2 NRC Docket Numbers 50454. 50-455 Braidwood Nuclear Power Station Units 1 and 2 NRC Doghet Numbers 50-456. 50-457
Reference:
Letter from J. B, llosmer to NRC Document Control Desk," Status of Actions to Address Generic Letter 92-08 Thermo Lag Fire Barriers", dated January 17,1997.
The purpose of this letter is to re schedule Byron and Braidwood Station's submittal of the final plant changes resolving Thermo-Lag (Generic Letter 92 08) concerns at both stations. The referenced letter informed the NRC that all plant changes necessary to resolve the Generic Letter 92 08 concerns have been installed on all units at Byron and Braidwood and reliance on Thermo Lag fire barrier material is no longer required. The plant changes in effect as of June,1996 at both stations were submitted to the NRC in Fire Protection Report Amendment #17 in December,1996. The referenced letter stated that the plant changes in effect after June,1996 would be submitted in Amendment #18 to the Fire Protection Report in December,1997. Byron and Braldwocd Stations now plan to submit Amendment #18 in Dece nber,1998, as explained below.
Discussions with the Byron and Braidwood Project Manager on September 4 and 25, 1997, indicated that the re schedule would not impact NRR's review of this issue, provided the plant changes discussed in the reference letter are in place. All the changes discussed in the referenced letter have been completed at both stations.
The plant changes in effect after June,1996, are marked on pending Fire Protection Report pages. Safety evaluations per 10CFR50.59 have been perfoimed and demonstrate that no unreviewed safety questions are involved. These pending Fire Protection Report pages are available for use by plant personal for any fire protection program evaluations and are available for NRC review at the Byron and Braidwood sites. The plant changes I
in effect after June,1996 w
+ be forwarded to the NRC as Amendment #18 until a
'(
December,1998 because s
.atial revisions to the same Fire Protection Report pages are being prepared due to an ongoing re-constitution of the Byron /Braidwood Safe Shutdown Analysis. The scope of this evaluation has expanded but is expected to be completed in 1997, thereby allowing a comprehensive inclusion of both sets of changes at 9710230214 971008 PDR ADOCK 05000454 l llllllllk,ll,ll[l[ll P
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Pagg 2 U.S NRC October 8,1997 the same time. The postponement of the submittal of the Thermo-Lag resolution plant changes will climinate two closely spaced revisions to the same pages. Amer:Iments to the Fire Protection Report are typically submitted to the NRC with the normal UFSAR updates. The next required update to the Byron /Braidwood UFSAR is December,1998.
Submittiag Amendment #18 to the Fire Protection Report in December,1998 maintains the normalinterval.
Sincerely, 4Ak'%
f John B. Hosmer Vice President ec:
Regional Administrator-Rill Byron /Braidwood Project Manager NRR Senior Resident inspector Byron Senior Resident inspector Braidwood Office of Nuclear Safety IDNS k:nla byrbwd/thermlag. doc