ML20094K927

Forwards Core Operating Limits Rept for LaSalle County Station,Unit 2,Reload 4 (Cycle 5), for Upcoming Cycle, Consistent W/Generic Ltr 88-16

ML20094K927
Person / Time
Site:	LaSalle
Issue date:	03/18/1992
From:	Piet P COMMONWEALTH EDISON CO.
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20094K931	List: ML20094K927 ML20094K933
References
GL-88-16, NUDOCS 9203230314
Download: ML20094K927 (2)

Text

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March 18, 1992 i Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn: Document Control Dest l

Subject:

LaSalle County Station Unit 2 Cycle 5 Reload and Core Operating Limits Report NRC_DotteLNo...50-374

References:

(a) P.L. Piet (Ceco) letter to (USNRC),

dated September 6, 1991; "LaSalle County Nuclear Power Station Unit 2 Fuel Channel Evaluation for LaSalle Unit 2 Cycle 5, i NRC Docket No. 50-374" '

(b) B.L. Siegel (USNRC) letter to T.J. Kovach (CECO) dated January 21, 1992; " Evaluation of Response to NRC Bulletin 90-02 for LaSalle County Station, Unit 2" (TAC No M82038)

Gentlemen:

LaSalle Unit 2, which has recently completed its fourth cycle of operation, 15 currently preparing for Cycle 5 startup (estimated startup dote is March 27, 1992). The purpose of this letter is to advise you of Commonwealth Edison's reviaw of the Cycle 5 reload urider the provisions of 10 CFR 50.59, and to transmit the Core Operating Limits Report (COLR) for '

the upcoming cycle consistent with Generic Letter 88-16.

The LaSalle Unit 2 core, which consists of NRC approved fuel designs, was designed to operate within approved fuel design criteria, Technical Specifications and related bases such that:

- core operating characteristics will be equivalent to or less limiting than those previously reviewed and accepted; or t

- reanalysis has been performed to demonstrate that the limiting postulated FSAR events which could be affected by the reload are within allowable limits.

Consistent with past reloads, the reload licensing analyses ,

performed-for Cycle 5 utilized NRC approved methodologies. The cycle-specific power distribution limits for Cycle 5 are presented in the '

attached COLR.

92032 o d 31a /)(T DR ADOCK 05000374 #[

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U.S. Nuclear Regulatory Commission March 18, 1992 Limited appilcation in the L2C5 core of previously reused channels has been evaluated in Reference (a) and approved by your staff in Reference '

(b). This evaluation demonstrated no impact on fuel design or safety

. limits.

Commonwealth Edison has performed a detailed review of the <

relevant reload-licensing documents, the associated bases, and references. ,

Based on that review, a safety evaluation was prepared as required by 10 '

CFR 50.59 and approved by CECO's On-Site and Off-Site Review functions.

CECO has concluded that the reload presents no unreviewed safety questions. ,

and that no revisions to the current Technical Specifications are required '

as a result'of the reload. j Final'-9, further verification of the reload core design will be perforined durlieu startup testing. The startup tests will be consistent with Technical Specifications and testing recommended in Draft Regulatory Guide Task SC 521-4. As in the past, a sunmary of the results of Ley startup tests will be: submitted within-90 days following the resumption of .

commercial operation.

Based on the previous discussion Ceco has concluded that NRC review and appioval of the reload analyses is not required for resumption  :

of operation with t'; Cycle 5 core.

If there are any further questions regarding this matter, please contact this office.

Very truly yours,

/[ '

Y eter L. Piet Nuclear Licensing Administ tor Attachment - Core Operating Limits Report for LaSalle County Unit 2 Cycle 5 cc: -A.-B. Davis _- Regional Administrator, Rlll B. Siegel - NRR, Project Manager-D. E. Hills - Senior Resident-Inspector-LSCS I i INLu/862/7s

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