ML20057E030

Forwards Rev 7 to LAP-1200-16, Core Operating Limits Rept for LaSalle County Station Unit 2,Reload 5 (Cycle 6), for Upcoming Cycle Consistent W/Gl 88-16

ML20057E030
Person / Time
Site:	LaSalle
Issue date:	09/30/1993
From:	Piet P COMMONWEALTH EDISON CO.
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20057E031	List: ML20057E030
References
GL-88-16, NUDOCS 9310070137
Download: ML20057E030 (2)

Text

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' Dr. Thomas E. Murley Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Attn: Document Control Desk l

Subject:

LaSalle County Nuclear Power Station Unit 2 )

Cycle 6 Reload and Core Operating Limits Report i NRC Docket No. 50-374 i

Dear Dr. Murley:

LaSalle County Unit 2 has recently completed its 5th cycle of operation and is currently preparing for Cycle 6 startup (estimated startup date is hovember 21, l 1993). The purpose of this letter is to advise your staff of Commonwealth Edison's review of the Cycle 6 reload under the provisions of 10CFR50.59 and to transmit

, the Core Operating Limits Report (COLR) for the upcoming cycle consistent with Generic Letter 88-16.

I The LaSalle County Unit 2 core, which consists of NRC-approved fuel designs, was designed to oprate within approved fuel design criteria, Technical Specifications and related aases such that:

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

2) 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 6 utilized NRC-approved methodologies. The fresh fuel to be loaded in Cycle 6 consists of 80 bundles of fuel type GE9B-P8CWB313-9GZ-100M-150-CECO with bundle average enrichment of 3.13 and 9 Gd Rods and 152 bundles of fuel type GE9B-P8CWB316-9GZ-100M-150-CECO with bundle average enrichment of 3.16 and 9 Gd Rods. The cycle-specific power distribution limits for Cycle 6 are presented in the attached COLh.

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Dr. Thomas E. Murley September 30,1993

• 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 10CFR50.59, which concluded that the  ;

reload presents no unreviewed safety questions and requires no Technical Specification '

changes. The On-Site and Off-Site Review of the reload 10CFR50.59 evaluation is in '

progress and will be completed prior to the start of Cycle 6 operation.

Finally, further verification of the reload core design will be performed during

! startup testing. The startup tests will be consistent with Technical Specifications and I

testing recommended in Draft Regulatory Guide Task SC 521-4. As in the past, a summary of the results of key startup tests will be submitted within 90 days following the resumption of commercial operation.

Based on the preceding discussion, Commonwealth Edison has concluded that NRC review and approval of the reload analyses is not required for resumption of operation with the Cycle 6 core.

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

Very truly yours, i

-/

l eter L. Piet Nuclear Licensing Administrator j Attachment - Core Operating Limits Report, LaSalle County Unit 2 Cycle 6 cc: J. B. Martin - Regional Administrator, Region III ,

D. L. Hills - Senior Resident Inspector, LaSalle County- '

J. L. Kennedy - Project Manager, NRR L. E. Phillips - Reactor Systems Branch, NRR

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