ML20202E160
| ML20202E160 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 01/30/1998 |
| From: | Graesser K COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20202E165 | List: |
| References | |
| BYRON-98-0027, BYRON-98-27, GL-88-16, NUDOCS 9802180086 | |
| Download: ML20202E160 (2) | |
Text
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. npon Generating Wtion 4 4% honh (errmon ( hu ';h flowl h) ton. !! 010109%4 ltlNI% 3 89411 Comed January 30,1998 LTR: IlYRON 98-0027 File:
1.02.1052.194 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555
Subject:
Hyron Unit I Cycle 9 Operating Limits Report Dyron Nucicar Power Station NRCEncLcWmnber: 50-4L4 Hyron Unit I has recently completed its 8th cycle of operation ar,d is currently preparing for Cycle 9 startup (estimated stanup date is February 20,1998). The purpose of this letter is to advise you of Commonwealth Edison's (Comed's) review of the Cycle 9 reload under provisions of 10CFR50.59 and to transmit the Operating Limits Report (OLR) for the upcoming cycle consistent with Generic Letter 88 16 and the Byron Technical Specifications.
The BYIC9 co e, which consists of NRC-approved fuel designs, was designed to operate within approved fuel design criteria, Technical Specifications und related bases such that:
1) core operating characteristics will he equivalent to or less limiting than those previously reviewed and accepted; or 2) re analyses or re-craluations have been performed to demons' rate that the limiting postulated UFSAR events which could be afTected by the reload are within allowable limits.
1 Consistent with past reloads, the reload licensing analyses performed for Cycle 9 utilized NRC-approved methodologies. During the Cycle 8/9 refueling,77 new VANTAGE 5 fuel assemblics were inserted into the core. The Byron Unit I core contains a full core of Westinghouse 17 x 17 VANTAGE 5 assemblics (77 new,76 once burned, and 40 twice-bumed assemblics). The cycle-specific power distribution limits for operation of Cycle 9 are presented in the r.'tached OLR resision.
Comed has performed a detailed review of the revised 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 Speci5 cation changt. The Byron On site Review of the 10CFR50.59 Safety Evaluation has been completed in accordance with station procedures.
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e January 30,1998
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BYXON 98 0027.
TPage"2 U. S. Nuclear 16gulatory Com S. sion Finally, further verification of the reload core design will be performed during startup testing. - The standard tests will be consistent with Technical Specifications and testing recommended in ANS 19.6.1.
.E If there are any questions regarding this submittal, please contact Marcia Lesniak, Byron Nuclear Licensing Administrator, at (630) 6634,84.
Sincerely, K. L. draesser Site Vice President
- Byron Nuclear Power Station KLG/ML/rp Attachment -
cc:
~ Byron Project Manager - NRR.-
' Regional Admir%% Rill Senior Residein !nsper;t < - Byron Office of Nucicar Et:.aty Satsty - IDNS -
. (p-\\98byttrs\\980027. doc)
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