ML20097D757

Forwards Rev 3 to Byron Unit 1 Cycle 7 Operating Limits Rept, Per GL 88-16

ML20097D757
Person / Time
Site:	Byron
Issue date:	02/09/1996
From:	Lesniak M COMMONWEALTH EDISON CO.
To:	NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20097D760	List: ML20097D757 ML20097D772
References
GL-88-16, NUDOCS 9602130165
Download: ML20097D757 (2)

Text

( nmmonwealth I dison Conyun)

, 1100 (1 pus Place

,, Dow ncrs Gros c. II. 60515 1

l February 9,1996 l

Office of Nuclear Reactor Regulation '

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 ATTN: Document Control Desk

SUBJECT:

Byron Nuclear Power Station Unit 1 Cycle 7 Reanalyses and Operating Umits Report NRC Docket No. 50-454 Byron Unit 1 has recently completed startup following the Cycle 7 Mid-Cycle Steam ,

Generator inspection. Reanalyses to implement up to a 2 F Tove increase and to '

address the steam generator tube plugging (SGTP) have been performed. The purpose of this letter is to advise you of Comed's review of the Cycle 7 reonalyses under the provisions of 10CFR50.59 and to transmit the revised core Operating Umits Report (OLR) for the remainder of Cycle 7 consistent with Generic Letter 88-16.

The BYlC7 core loading pattern has not changed. All BYlC7 design characteristics remain valid, with the analyzed increase in Tave. The BY1C7 reonalyses supports a maximum average SGTP level of 24% and a peak level of 30% in up to three steam generators. The Byron Unit I core, which 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 and acceptec; or

2) re-analyses or re-evaluations have been performed to demonstrate that the limiting postulated UFSAR events which could be offected by the reload are within allowable limits.

The reload licensing reanalyses which were performed for the remainder of Cycle 7 utilized NRC-opproved methodologies. The cycle-specific power distribution limits for '

l remaining operation of Cycle 7 are presented in the attached core OLR revision.

Comed has performed a detailed review of the revised 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 reonalyses present no unreviewed safety questions and require no Technical Specification changes. The Byron On-Site review of the 10CFR50.59 safety evaluation has been completed.

Finally, since there Is no change in the core design or the assumed key design parameters, except for the Increased Vessel Tove from 582 F to s 584oF, the standard i reload startup physics tests, as recommended in ANSI /ANS 19.6.1, are not required for  !

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r the BY1C7 redesign. However, testing has been completed which demonstrated that i the SGTP has not impacted the assumed minimum design flow through appropriate colorimetric tests, if there are any questions regarding this matter, please contact this office.

Very truly yours, hlN6bh 441 Marcia Lesniak Nuclear Ucensing Administrator Attachment - Operating Umits Report, Byron Unit 1 Cycle 7, Revision 3 cc:

H. Miller, Regional Administrator - Rlll G. Dick, Byron Project Manager - NRR H. Peterson, Senior Resident Inspector - Byron Office of Nuclear Facility Safety - lDNS l