ML20237D120

Notifies NRC That Listed Actions Are Completed for Byron & Braidwood Stations Re Amends 84 & 76

ML20237D120
Person / Time
Site:	Byron, Braidwood
Issue date:	08/21/1998
From:	Graesser K COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYRON-98-0240, BYRON-98-240, NUDOCS 9808250077
Download: ML20237D120 (2)

Text

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Commonwealth I:diwn Company flyron Generating Station 4 450 Noah German Churt b Road liyron, 11.61010-9791 j

Td 815-2%5 411 August 21,1998 Letter:

BYRON 98-0240 File:

2.01.0301 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C. 20555-0001

Subject:

Byron Nuclear Power Station Units 1 and 2 Facility Operating Licenses NPF-37 and NPF-66 NRC Docket Nos. 50-454 and 50-455 Braidwood Nuclear Power Station Units 1 and 2 Facility Operating Licenses NPF-72 and NPF-77 NRC Docket Nos. 50-456 and 50457 Notification of Completed Actions for Amendments 84 and 76

References:

1) Letter from G.F. Dick, Jr. (NRC) to D.L. Farrar (Comed),

" Issuance of Amendments (TAC Nos. M90529, M90530, M90531, and M90532)," dated June 26,1996.

2) Letter from B.A. Boger (NRC) to R.A. Newton (Westinghouse Owners Group), " Review of Westinghouse Electric Corporation Topical Report WCAP-13632, Revision 2, ' Elimination of Pressure Sensor Response Time Testing Requirements,' dated August 1995 -

Westinghouse Owners Group Program MUHP-3040, Revision 1,"

dated September 5,1995.

' In Reference 1, the U.S. Nuclear Regulatory Commission issued Amendment 84 to Facility Operating Licenses NPF-37 and NPF-66 for Byron Station Units 1 and 2, and Amendment 76 to Facility Operating Licenses NPF-72 and NPF-77 for Braidwood Station Units 1 and 2. The letter reiterated that Commonwealth Edison Company l

(Comed) committed to take certain actions when eliminating pressure and differential pressure sensor response time testing requirements. These actions are consistent with f

those in the staff's conditional approval of WCAP-13632-P-A, " Elimination of Pressure Sensor Response Time Testing Requirements," Revision 2 (Reference 2). The NRC 4 <]( :

requested that Comed notify the NRC Staff when those actions are complete.

4 4 50077 980821 i

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[i BYRON 98-0240 August 21,1998 Page 2 i

With this letter, Comed is notifying the NRC Staff that these actions are complete for Byron and Braidwood Stations.

Please address any comments or questions regarding this matter to this office.

Sincerely, j/

(

K. L. Graesser Site Vice Preside.nt Byron Nuclear Power Station 3

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)

Regional Administrator-RegionIII cc:

Senior Resident Inspector - Byron Senior Resident Inspector - Braidwood Office of Nuclear Facility Safety - IDNS l

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