ML20247B712
| ML20247B712 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 05/01/1998 |
| From: | Kofron K COMMONWEALTH EDISON CO. |
| To: | NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20247B717 | List: |
| References | |
| BYRON-98-0140, BYRON-98-140, G-88-16, NUDOCS 9805080215 | |
| Download: ML20247B712 (2) | |
Text
a Commonwealth 1:dhon Comp.m) 15)ron Gcncrating Station
-6 isn North German Chun h Road
!!) ron. IL 61n 10979 i Tel H15464i il day 1,lh98 l
LTR:
BYRON-984)l40 File:
1.02.1052.2.8 Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission i
Washington, D. C. 205554)01 1
ATTN: Document Control Desk
SUBJECT:
Byron Unit 2 Cycle 8 Operating Limits Report Byron Nuchar Power Station Unit 2 Facility Operating License NPF-66 NRC Docket Number: 50-455 Byron Unit 2 has recently completed its 7th cycle of operation and is currently preparing for Cycle 8 startup (estimated startup dr.e is May 17, 1998). The purpose of this letter is to advise you of Commonwealth Edison's (Comed's) resiew of the Cycle 8 reload under provisions of 10CFR50.59 and to transmit the Operating Limits Report (OLR) for the upcoming cycle consistent with Generic Letter 88-16.
The Byron Unit 2 Cycle 8 core, w hich 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 md accepted; or 2) re-analyses or re-evaluations have been performed to demonstrate that the limiting postulated UFSAR events u hich could be affected by the reload are within allowable limits.
Consivent with past reloads, the reload licensing analyses perfcaned for Cycle 8 utilized NRC-approved methodologies. The fresh fuel to be loaded in Cycle 8 consists of 89 VANTAGE 5 fuel assemblies. There are 44 Region 10A assemblies with 4.8 w/o enrichment,13 Region 10B assemblics with 4.4 w/o enrichment, and 32 Region 10C assemblies with 4.0 w/o enrichment. The cycle-specific power distribution limits for Cycle 8 arc
/
presented in the attached OLR.
i 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 unresiewed safety questions and requires no Technical Specification change. The 7';
Byron On-site Review of the relcad 10CFR50.59 Safety Evaluation has been completed in accordance with station i
procedures.
Finally, further verification of the reload core design will be performed during startup testing. These tests will be consistent with Technical Specifications and will also meet the intent of the testing recommended in ANS 19.6.1-1997.
9905090215 990501 PDR ADOCK 05000455 p
PDR (p W8t yttrs\\980140. doc)
A l'nicom Company
i BYRON-98-0140 41ay1,1998 Page 2 If there are any questions regarding this submittal, please contact Marcia Lesniak, Licensing Administrator, at (630)663-6484.
Sincerely, Y
K. L. Kofron Station Manager Byron Nuclear Station ALK/LZ/rp Attachment cc:
By ron Project Manager - NRR Regional Administrator-Rill Senior Resident inspector - Byron Office of Nuclear Facility Safety - IDNS l
l r
(pA98byltrs\\980140. doc)
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