ML20084C222

Application for Amends to Licenses NPF-11 & NPF-18, Clarifying Described Equipment out-of-svc Options

ML20084C222
Person / Time
Site:	LaSalle
Issue date:	05/23/1995
From:	Benes G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20084C223	List: ML20084C222 ML20084C249
References
NUDOCS 9505310457
Download: ML20084C222 (2)

Text

.e Commonwealth filison Company I

• I.aSalle Generating Station

. 2601 North 21st Road Marseilles, 11.6134i-9757 I

TelH143576*61 May 23,1995 1

U.S. Nuclear Regulatory Commission I Attn: Document Control Desk j Washington, D.C. 20555 j l

SUBJECT:

Technical Specification Bases change for  !

LaSalle County Nuclear Power Station Units 1 and 2 NRC Docket Nos. 50-373 and 50-374 l

1 Pursuant to 10 CFR 50.59, Commonwealth Edison (Comed) has changed the  ;

Minimum Critical Power Ratio (MCPR) section in the LaSalle Station Technical Specification Bases Section 3/4.2.3 of Facility Operating Licenses NPF-11 and NPF-18.

1 The Bases Section is being changed to clarify the described Equipment Out-of-Service  !

(EOOS) options. These Bases changes do not involve changes to the Technical  !

Specification Limiting Conditions for Operations or Surveillance Requirements, l l

The current description of LaSalle Equipment Out-of Service (EOOS) options in Technical Specification Bases Section 3/4.2.3 (Minimum Critical Power Ratio) is consistent with the initial LaSalle EOOS analysis performed by General Electric, but does not adequately address subsequently analyzed EOOS conditions. The revised Bases section -

eliminates the detailed discussion of EOOS options and instead references the Core Operating Limits Report, which provides detailed directions for applying MCPR penalties to EOOS conditions and contains references for the current EOOS analyses. This will l eliminate future needs to revise the MCPR Bases as new EOOS analyses are reviewed per I 10 CFR 50.59. New EOOS analyses will continue to be referenced in the Core Operating l Limits Report, which is transmitted consistent with Generic Letter 88-16. '

Comed has performed a Safety Evaluation pursuant to 10 CFR 50.59, and determined that an Unreviewed Safety Question does not exist. These Bases changes l have been reviewed and approved by Comed On-Site and Off-Site review in accordance I with Comed procedures. Copies of the marked up and approved Bases pages are attached.

Please direct any questions you may have concerning this matter to this office.

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Sincerely,  ;

h hh64W Gary G. Benes l Nuclear Licensing Administrator

1. 9505310457 950523 PDR ADOCK 05000373 P PDR A i'nh om company

Attachments  !

I cc: J. B. Martin - Regional Administrator, Region III P. G. Brochman - Senior Resident Inspector, LaSalle County  ;

W. D. Reckley - Project Manager, NRR l Office of Nuclear Facility Safety - IDNS l 1

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