ML20140H135
| ML20140H135 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 05/01/1997 |
| From: | Stanley H COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20140H139 | List: |
| References | |
| GL-88-16, NUDOCS 9705120348 | |
| Download: ML20140H135 (2) | |
Text
_-
- W Ginunonwealth (Alison Gempany
- f Ilran!wom! Generating Stauon
,, Route *l,Ibx 8 6 Ilraces ille,1L 60107%i9 Tel H154W2Ho t May 1,1997 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001
Subject:
Braidwood Generating Station Unit 1 Cycle 7 Reload and Unit 2 Cycle 6 and Unit 1 Cycle 7 Operating Limits Reports Braidwood Unit I has recently completed its sixth cycle of operation and is currently preparing for Cycle 7 startup (estimated startup date is May 21,1997). Braidwood Unit 2 Cycle 6 is currently in operation. This letter's purpose is to advise ynn of Comed's review of both the_ Unit 1 Cycle 7 reload and the Unit 2 Cycle 6 operating cycle under the l
provisions of 10CFR50.59, and to transmit the Operating Limits Repons for these two cycles consistent with Generic Letter 88-16 and Section 6.9.1.9 of the Braidwood Technical Specifications. This letter transmits the Operating Limits Reports in etTect following receipt of Amendment 80 to the Braidwood Technical Specifications, approving expansion of the Operating Limits Report.
s 1
The Braidwood Unit I Cycle 7 and Unit 2 Cycle 6 cores, which consist of NRC approved fuel designs, were designed to operate within approved fuel design criteria, Technical Specifications, and related bases such that:
1
- 1) the core operating characteristics will be equivalent to or less limiting than those previously reviewed and accepted; or
- 2) re-analysis or re-evaluations have been performed to demonstrate that the limiting postulated UFSAR events that could be afTected by the reload are 4
within allowable limits.
f i
Consistent with past reloads, the reload licensing analyses performed for Unit 1 Cycle 7 i
and Unit 2 Cycle 6 utilized NRC-approved methodologies. The fresh fuel to be loaded
) i l
j into Unit 1 Cycle 7 coasists of 56 VANTAGE 5 fuel assemblies. There are 16 Region 9A JA assemblies with 4.80 w/o enrichment and 40 Region 9B assemblies with 4.60 w/o I
enrichment. Unit 2 Cycle 6 is an operating cycle. Analyses performed to suppon the attached power distribution limits utilized NRC-approved methodologies, and accomplished no changea to fuel loading. The cycle-specific power distribution limits for j
Unit 1 Cycle 7 and Unit 2 Cycle 6 are presented in the attached OLRs.
9705120340 970501 PDR ADOCK 05000456 llllIl!I Ilillilltll
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,, Document Control Desk Page 2 Comed has performed a detailed review of the relevant reload licensing documents, the associated bases, and applicable references. Based on that review, a safety evaluation was prepared for the Unit 1 Cycle 7 reload, as required by 10CFR50.59, which concluded that the reload presents no unreviewed safety questions, and requires no Technical Specification changes. The Braidwood review of the reload 10CFR50.59 has been j
completed. Also based on that review, Comed determined that the preparation of the Unit 2 Cycle 6 Operating Limits Report involved no changes from procedures previously reviewed as required by 10CFR50.59, and required no further review.
Finally, further verification of the Unit 1 Cycle 7 reload core design will be performed during startup testing.
The startup tests will be in accordance with Technical l
Specifications, and consistent with testing recommended in ANSI 19.6.1.
If there are any questions regarding this issue, please contact this oflice.
Sincerely,
}
i
~ f. Gen (Sta ley Site Vice President Braidwood Generating Station Attachments - Operating Limits Report, Braidwood Unit 1 Cycle 7 and Operating Limits Report, Braidwood Unit 2 Cycle 6 4
cc:
A. B. Beach, Regional Administrator - RIII J
G. Dick, Braidwood Project Manager - NRR C. J. Phillips, Senior Resident Inspector - Braidwood Oflice of Nuclear Safety - IDNS I
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