ML20069N865
| ML20069N865 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/16/1994 |
| From: | Lockwood J COMMONWEALTH EDISON CO. |
| To: | Russell W NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20069N868 | List: |
| References | |
| NUDOCS 9406230237 | |
| Download: ML20069N865 (2) | |
Text
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Commonw:cith Edison LaSalle County Nuclear Station 2001 N. 21st. Rd.
Marseilles, Illinois 61341 June 16,1994 Telephone 815/357-6761 Mr. William T. Russell, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Attn: Document Control Desk
Subject:
LaSalle County Nuclear Power Station Unit 1 Cycle 7 Reload and Core Operating Limits Report Unit 2 Cycle 6 Core Operating Limits Report Mid-Cycle Change NRC Docket Nos. 50-373 and 50-374
Dear Mr. Russell,
LaSalle County Unit 1 is currently preparing for Cycle 7 startup (estimated startup date is June 19,1994). The purpose of this letter is to advise you of Commonwealth Edison's (Comed) review of the Cycle 7 reload under the provisions of 10CFR50.59 and to transmit the Unit 1 Core Operating Limits Report (COLR) for the upcoming cycle consistent with Generic Letter 88-16. The Unit 2 Cycle 6 Core Operating Limits Report is also included since LaSalle Unit 1 and 2 Core Operating Limits Reports contain the references from Technical Specification Section 6.6.A.6.b. This is in preparation for a license amendment submittal which would l
remove those references from the Technical Specifications for all of Comed's BWR units.
The LaSalle County Unit 1 core, which consists of NRC-approved fuel designs, was designed to operate within approved fuel design criteria, Technical Specifications and related bases 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.
l Consistent with past reloads, the reload licensing analyses performed for Cycle 7 utilized NRC-approved methodologies. The fresh fuel to be loaded in Cycle 7 consists of 104 bundles of fuel type GE9B-P8CWB320-9GZ-100M-150-CECO j
with a bundle average enrichment of 3.20 and 9 Gd Rods and 104 bundles of fuel type GE98-P8CWB322-11GZ-100M-150-CECO with a bundle average enrichment of 3.22 and 11 Gd Rods. The cycle-specific power distribution limits for Cycle 7 i
9406230237 940616 l
PDR ADOCK 05000373 P
PDR g
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i are presented in the attached Unit 1 COLR.
Comed 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 10CFR50.59 evaluation for the Unit 1 reload and the Unit 2 COLR have been approved by LaSalle County Senior Station Management and Onsite Review in accordance with Station procedures.
Further verification of the Unit 1 Cycle 7 reload core design will be performed during startup testing. The startup tests will be consistent with Technical Specifications. A summary of the results of key startup tests will be j
submitted within 90 days following the resumption of commercial operation.
Based on the preceding discussion, Comed has concluded that NRC review and approval of the reload analyses is not required for resumption of Unit 1 operation with the Cycle 7 core.
If there are any questions regarding this matter, please do not hesitate to contact this office.
Very truly yours, f
Joh E. Lockwood Regulatory Assurance Supervisor Attachments:
- 1) Core Operating Limits Report, LaSalle County Unit 1 Cycle 7
- 2) Core Operating Limits Report, LaSalle County Unit 2 Cycle 6 cc:
J. B. Martin - Regional Administrator, Region lli D. L. Hills - Senior Resident Inspector, LaSalle County A. T. Gody, Jr. - Project Manager, NRR L. E. Phillips - Reactor Systems Branch, NRR