ML20108D856
| ML20108D856 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 04/30/1996 |
| From: | Kaup K COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20108D859 | List: |
| References | |
| GL-88-16, NUDOCS 9605090086 | |
| Download: ML20108D856 (2) | |
Text
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Commonwealth Ediwn Company 9
firaidwood Generating Station Ruute ol, llox H l 4
liraceville, lL 60 io% I 9 TelHI% HH-2801 April 30,1996 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001
Subject:
Cycle 6 Operating Limits Report Braidwood Nuclear Power Station, Unit 2 Facility Operating License Number NPF-77 NRC Docket No. 50-457 Ladies and Gentlemen:
Commonwealth Edison Company's (Comed's) Braidwood Nuclear Power Station Unit 2 (Unit 2) has recently completed its 5th cycle of operation and is currently preparing for Cycle 6 startup. The estimated Cycle 6 startup date is May 7,1996. The purpose of this letter is to advise the United States Nuclear Regulatory Commission (USNRC) of Comed's review of the Cycle 6 reload under the provisions of Title 10, Code of Federal Regulations, Part 50 Section 59 (10CFR50.59) and to transmit the Operating Limits Report (OLR) for the i
upcoming cycle consistent with Generic Letter 88-16, " Removal of Cycle-Specific Parameter Limits from Technical Specifications," dated October 4,1988.
The Braidwood Unit 2 core consi::ts of USNRC approved fuel designs, and 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 l
postulated Updated Final Safety Analysis Report (UFSAR) events which could be l
affected by the reload are within allowable limits.
Consistent with past reloads, the reload licensing analyses performed for Cycle 6 used l
USNRC-approved methodologies. The fresh fuel to be loaded in Cycle 6 consists of 84 l
VANTAGE 5 fuel assemblies. There are 68 Region 8A assemblies with 4.60 weight percent uranium-235 (w/o U-235) enrichment and 16 Region 8B assemblies with 4.40 w/o U-235 enrichment. The cycle-specific power distribution limits for Cycle 6 are presented in the attached OLR.
Comed has performed a detailed review of the relevant reload licensing docut-ts, 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 9605090086 960430 PDR ADOCK 05000457 N-P1 i P
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questions and requires no Technical Specification changes. The Braidwood On-Site Review of the reload 10CFR50.59 has been completed.
4 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 American National Standards Institute /American Nuclear Society (ANSI /ANS)-19.6.1-1985,
" Reload Startup Physics Tests for Pressurized Water Reactors."
Please direct any questions or comments regarding this matter to Mr. Douglas S. Huston, Braidwood Nuclear Station Licensing Supervisor at (815)458-2801 extension 2511.
Karl L. Kaup Site Vice President Braidwood Generating Station KLK/DSH/tts
Attachment:
Operating Limits Report, Braidwood Unit 2 Cycle 6 cc:
R. Assa, Braidwood Project Manager - NRR H. Miller, Regional Administrator - RIII C. Phillips, Senior Resident Inspector - Braidwood Office of Nuclear Facility Safety - IDNS etisvykoivamps90018 doc