ML20212G711

Advises of Review of Unit 2 Cycle 7 Reload Under Provisions of 10CFR50.59 & Transmits Operating Limits Rept for Unit 2 Cycle 7 Consistent W/Gl 88-16 & Section 6.9.1.9 of TS

ML20212G711
Person / Time
Site:	Braidwood
Issue date:	10/31/1997
From:	Tulon T COMMONWEALTH EDISON CO.
To:	NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20212G715	List: ML20212G711 ML20212G716
References
GL-88-16, NUDOCS 9711070062
Download: ML20212G711 (2)

Text

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( TriHi04W 2801 October 31,1997 Oflice of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D C 20555 ATTN: Document Control Desk

SUBJECT:

Braidwood Station Unit 2 Cycle 7 Reload and Operating Limits Report Braidwood Unit 2 has recently completed its sixth cycle of operation and is currently preparing for Cycle 7 startup (estimated startup date is November 2,1997). This letteri purpose is to advise you of Comed's review of the Unit 2 Cycle 7 reload uader the provisions of 10CFR50.59, and to transmit the Operating Limits Reports (OLR) for Unit 2 Cycle 7 colisistent with Generic Letter 88-16 and Section 6.9.1.9 of the Braidwood Technical Specifications.

The Braidwood Unit 2 Cycle 7 core, which consists of NRC approved fuel designs, was designed to operate within approved fuel design criteria, Technical Sp:cifications, and related bases such that:

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 affected by the reload are within allowable limits.

Consistent with past reloads, the reload licensing analyses performed for Unit 2 Cycle 7 utilized NRC-approved methodologies. The fresh fuel to be loaded into Unit 2 Cycle 7 consists of 81 VANTAGE + fuel assemblies. There are 40 Region 9A assemblies with 4.60 w/o enrichment and 41 Region 9B assemblies with 4.40 w/o j enrichment. The cycle-specific power distribution limits for Unit 2 Cycle 7 are presented in the attacheu OLR. j 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 2 Cycle 7 reload, as required by 10CFR50.59, which concluded that the reload prescrits no unreviewed safety questions, and requires 9711070062 971031~

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Document Control Desk 10/31/97 Page 2 no Technical Specification changes. The Braidwood resiew of the reload 10CFR50.59 has been completed.

In addition, Comed has resiewed the information related to the potential for Westinghouse fuel to exceed its oxidation limit and has concluded along with Westinghouse that reactor core operation does not result in an immediate safety concern. The startup of Unit 2 following refueling will proceed based on the guidance provided in NRC Generic Letter No. 91-18, Revision 1, dated October 8,1997.

Finally, further verification of the Unit 2 Cycle 7 reload core design will be performed during startup testing. The startup tests will be in accordance with Technical Specifications, and consistent with testing recommended in ANSI 19.6.1.

If there are any questions regarding this issue, please contact this office.--

Sincerely,

/

thy J. Tulon ~

ite Vice President

,Braidwood Nuclear Generating Station Attachment - Operating Limits Report, Braidwood Unit 2 Cycle 7 cc: A. B. Beach, Regional Administrator - RIII G. Dick, Braidwood Project Manager - NRR C. J.' Phillips, Senior Resident Inspector - Braidwood Office of Nuclear Safety -IDNS

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