ML20087H790
| ML20087H790 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/01/1995 |
| From: | Benes G COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20046D708 | List: |
| References | |
| NUDOCS 9505040418 | |
| Download: ML20087H790 (2) | |
Text
913011152260;* 2/ 3 SENT BY:COM D
- 5-1-95 ; 16:23 ;
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utnocweaue.ia mmin I sis 0 Onr. lhec imwnm on, c. :t u,si s May 1,1995 U.R Nuclear Regulatnry Commission Attn: Document Control Dock Washington, D.C. 20555
SUBJECT:
LaSalle County Nuclear Power Station Unit 2 Correction to Amendment to Facility Operating License NPF.D Emergency Safety / Relief Valve Opening Setpoint Tolcrance Change NHC Docket No. 50-374
REFERENCE:
G. Benes letter to USNRC dated March 31,1995 The Reference letter proposed an emergency amendment to change the Safety Ralief Valve (SRV) anfety function lift setting tolerances. Attachment G to th c Reference letter contains a Sargent and Lundy analysis for SRV Discharge Pi hg l
umi Main Steam Piping Loads Due to SRV Setpoint Tolerance Relaxation. On M bottom of page 2 to the Sargent and Lundy Analysis is a footnote indicating tho doeurnent contains information which is confidential and proprietary to Sargent and Lundy. Discussions with Sargent and Lundy have determined that this footnote chould not have been placed within the document. Sargent and Lundy has reconfirmed that there is no information which is cosidential and proprietary to Sargent and Lundy existing within the Sargent and Lundy Analysis. In summary, the Sargent and Lundy Analysis contained in Attachment G of the Reference letter is nonproprietary and does not ne'ed to be withheld from public disclosure pursnint in 10 CFR 2.700.~
To the best ef my !.tmwledge and belief, the statements contained above are true and correct. In some respect these statements are not based on my personal knowledge, but obtained information furnished by other Commonwoalth Edison employees, contractor employees, and consultants. Such information has been reviewed in accordance with company practice, and I believe it to be reliable.
We regret any inconvenience this error may have caused. Please direct any quectiona you may havo concerning this mattor to this ofEce.
Sincerely, Y
Oaq G. Benen Nuclear Licensing Administrau>r 950504o41s 950331 PDR ADOCK 05000374 p
PDR s:.n.. u....p in
M 4
r ATTACHMENT G SARGENT AND LUNDY ANALYSIS FOR SRV DISCHARGE PIPING AND MAIN STEAM PIPING LOADS DUE TO SRV SETPOINT TOLERANCE RELAXATION l
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