ML20064N791

Forwards Rev 1 to Secl 90-469, Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation, in Response to NRC RAI Re Util 940321 Request for Emergency TS Amends

ML20064N791
Person / Time
Site:	Byron, Braidwood
Issue date:	03/23/1994
From:	Saccomando D COMMONWEALTH EDISON CO.
To:	Russell W NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20064N793	List: L-90-469, Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation ML20064N791 ML20064N802
References
NUDOCS 9403300131
Download: ML20064N791 (2)

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1400 Opus Place Downers Grove. tilinois 60515 March 23,1994 Mr. William Russell, Director

.i Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk

Subject:

Additional Information Pertaining to Request for EMERGENCY TECHNICAL SPECIFICATION AMENDMENT for Byron and Braidwood Stations Technical Specification Section 3/4.7.1_

NRC Docket Nos. 50-454. 50-455 50-456 and 50-457

Reference:

D. Saccomando Letter to W. Russell dated March 21,1994, transmitting request for Emergency Technical Specification Amendment

Dear Mr. Russell:

As requested by the Nuclear Regulatory Commission's (NRC), Commonwealth Edison Company (CECO) is supplying additional information pertaining to the request for Emergency Technical Specification which was transmitted with the reference letter.

Specifically, the attachment addresses the analysis for Bryon/Braidwood Units 1 and 2 relaxation of main steam safety valves setpoint tolerance to +/- 3%.

If you have any additional comments or questions please contact me at (708) 663-6484.

Sincerely, 4

Sha Denise

. Saccomando Nuclear Licensing Administrator Attachment cc:

R. Assa, Braidwood Project Manager - NRR G. Dick, Byron Project Manager - NRR S. Dupont, Senior Resident inspector - Braidwood -

H. Peterson, Senior Resident inspector - Byron B Clayton. Branch Chief - Region lli Office of Nuclear Facility Safety - IDNS h}Y )

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a Electric Corporation Box 355 Pmsburgn Pennsylvania 15230 0355 CAE-91-209 CCE-91-219 NS-0PLS-0PL-I-91-415 July 22, 1991 Mr. R. Pleniewicz, Station Manager Byron Nuclear Station Commonwealth Edison Company P.O. Box 458 4450 North German Church Road Byron, IL 61010 Commonwealth Edison Company Byron /Braidwood Units 1 and 2 Relaxation of MSSV Setooint Tolerance to +/-3% - Revised SECL

Reference:

(1) Westinghouse letter CAE-90-315/CCE-90-310, dated 10-31-90.

Dear Mr. Pleniewicz:

Enclosed please find Revision 1 to safety evaluation SECL 90-469, previously transmitted via Reference 1.

The revised safety evaluation clarifies the section of the ASME code associated with the main steam safety valves.

If you have any questions, do not hesitate to call.

Very truly yours, t

lWM pN.

B. S. Humphries, Manager

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8. E. Rarig Commonwealth Edison Projects Enclosure Customer Projects Department

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cc:

F. Lentine D. Swartz P. McHale J. Feimster K. Kofron R. Waninski L

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