ML20081B648
| ML20081B648 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 03/13/1995 |
| From: | Pontious H COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20081B650 | List: |
| References | |
| NUDOCS 9503160288 | |
| Download: ML20081B648 (2) | |
Text
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Commonwealth fdison Company -
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1400 Opus I%ce ii Downers Grove, IL 60515 March 13,1995 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
SUBJECT:
Byron Nuclear Power Station, Unit 2 Cycle 6 Operating Limits Report NPF-66: NRC Docket No. STN 50-455 Byron Unit 2 has recently completed its 5th cycle of operation and is currently preparing for Cycle 6 stanup (estimated startup date is March 27,1995). The purpose of this letter is to advise you of Commonwealth Edison Company's (Comed's) review of the Cycle 6 reload under the provisions of Title 10, Code of Federal Regulations, Pan 50, Section 59 (10 CFR 50.59) and to transmit the Operating Limits Report (OLR) for the upcoming cycle consistent with Generic Letter 88-16.
The Byron Unit 2 core, which consists of Nuclear Regulatory Commission (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) re-analyses or re-evaluations have been performed to demonstrate that the limiting postulated Updated Final Safety Analysis Report (UFSAR) events which could be affected by the reload are within allowable limits.
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9503160288 950313 i
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L USNRC Document Control Desk March 13,1995 Consistent with past reloads, the reload licensing analyses performed for Cycle 6 j
utilized NRC approved methodologies. The fresh fuel to be loaded in Cycle 6 consists of 88 VANTAGE 5 fuel assemblies. There am 36 Region 8A assemblies with 4.40 t
w/o enrichment and 52 Region 8B assemblies with 4.20 w/o enrichment. The cycle-
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specific power distribution limits for Cycle 6 are presented in the attached OLR.
' 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 10 CFR 50.59, which concluded that the reload presents no unreviewed safety questions and requires no Technical Specification changes. The Byron On-Site Review of the reload 10 CFR 50.59 has been completed.
Finally, further verification of the reload core design will be performed during startup testing. The startup tests will be consistent with Technical Specifications and testing recommended in ANSI /ANS-19.6.1.
Please address any comments or questions regarding this matter to this office.
Very truly yours, L
O I
e II-Id D. Pontious, Jr.
uclear Licensing Administmtor
Attachment:
Byron Unit 2 Cycle 6 Operating Limits Report I
cc:
J. B. Martin, Regional Administratoc - RIII G. F. Dick Jr., Byron Project Manager - NRR
- 11. Peterson, Senior Resident Inspector - Byron Office of Nuclear Facility Safety - IDNS i-l l
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