ML20113E362

Forwards Rev 0 to Byron Unit 1 Cycle 8 Operating Limit Rept, Per GL 88-16

ML20113E362
Person / Time
Site:	Byron
Issue date:	06/24/1996
From:	Graesser K COMMONWEALTH EDISON CO.
To:	NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20113E365	List: ML20113E362 ML20113E367
References
BYRON-96-0184, BYRON-96-184, GL-88-16, NUDOCS 9607050274
Download: ML20113E362 (2)

Text

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l Commonw calt h I:dison Company ilyron Generating Station '

,, 1450 North German Churth Road 1 li) ron, IL 61010-9794 Tel 814234-5141 i

June 24,1996 l

LTR: BYRON-96-0184 File: 1.02.1052.184 Oflice of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Wr.shington, D. C. 20555 ATTN: Document Control Desk

SUBJECT:

Byron Unit 1 Cycle 8 Operating Limits Report Byron Nuclear Power Station NRC Docket Number: 50-454 Byron Unit I has recently completed its 7th cycle of operation and is currently preparing for Cycle 8 startup {

(estimated startup date is June 26,1996). The purpose of this letter is to advise you of Commonwealth Edison's (Comed's) review of the Cycle 8 reload under provisions of 10CFR50.59 and to transmit the Operating Limits Report (OLR) for the upcoming cycle consistent with Generic Letter 88-16.

The BYIC8 core, which consists of NRC-approved fuel designs, was designed to opera'e 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 review-d and accepted; or

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

Consistent with past reloads, the reload licensing analyses performed for Cycle 8 utilized NRC-approved methodologies. During the Cycle 7/8 refueling, seventy-six (76) new VANTAGE 5 fuel assemblies were inserted into the core. The Byron Unit 1 core contains a full core of Westinghouse 17 x 17 VANTAGE 5 assemblies (76 new,92 once-burned, and 25 twice-burned assemblies). The cycle-specific power distribution limits for operation ,

of Cycle 8 are presented in the attached OLR revision. l 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 reload presents no unreviewed safety questions and requires no Technical Specification change. The Byron On-site Review of the 10CFR50.59 Safety Evaluation has been completed in accordance with station procedures.

Finally, further verification of the reload core design will be performed during startup testing. The standard tests will be consistent with Technical Specifications and testing recommended in ANS 19.6.1.

9607050274 960624 PDR ADOCK 05000454 P PDR

.? O A l'nkom Company 4 4

F If there are any questions regarding titis submittal, please contact Mike Rothenbuehler, Unit i Nuclear Engineer, at (815) 234-5442 ext. 2283, Sincerely, .

, '2BM K. L. Graesser Site Vice President Byron Nuclear Station Attachment cc: G. F. Dick, Byron Project Manager - NRR lt J. Miller, Regional Adrainistrator - Rill H. Peterson, Senior Resident inspector - Byron Office of Nuclear Facility Safety - IDNS l

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