ML20080U085

Advises of Util Review of Cycle 5A Core Design Per 10CFR50.59 & Transmits Operating Limits Rept for Upcoming Cycle Consistent W/Gl 88-16

ML20080U085
Person / Time
Site:	Braidwood
Issue date:	03/09/1995
From:	Saccomando D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20080U092	List: ML20080U085 ML20080U511
References
GL-88-16, NUDOCS 9503140223
Download: ML20080U085 (2)

Text

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t M- A rd N 7ca iuoD Opus Place eew nn s en

,j Downers Grove, Illiros 60515

L March 9,1995 Office of Nuclear Reactor Regulation is , U. S. Nuclear Regulatory Commission ;

• L Washington, D. C.' 20555

- ATTNi Document Control Desk

SUBJECT:

Braidwood Nuclear' Power Station Unit 1 Cycle SA Design and Operating Limits Report-NRC Docket No.50-456 e Braidwood Unit 2 has recently completed midcycle 5 outage and is currently -

L preparing for Cycle 5A startup (estimated startup date is March 12,1995). Cycle 5A'is the name given to Braidwood Unit 1 Cycle 5 (BR1C5) after the mid-cycle P< outage to inspect steam generators. The Cycle 5A designation was given and a L redesign is required because of the vessel average temperature increase of 4 *F.

(580 'F to 584 'F).~ The purpose of this letter is to' advise you of Comed's review of the Cycle SA core design under the provisions of 10CFR50.59 and to transmit the g Operating Limits Report (OLR) for the upcoming cycle consistent with Generic Letter

l. 88-16.

[ The Braidwood Unit 1 core, which consists of NRC approved fuel designs', was l designed to operate within approved fuel design criteria, Technical Specifications L and related bases such that:

1) core operating characteristics will be equivalent to or less limiting than-those previously reviewed and accepted;'or.

l

[ 2) re-analyses or re-evaluations have been performed to demonstrate that -

l_ the limiting postulated UFSAR events which could be affected by the core ,

3 design are within allowable limits.

Consistent with past core designs, the reload licensing analyses performed for Cycle 5A utilized NRC-approved methodologies. The cycle-specific power L distribution limits for Cycle SA are presented in the attached OLR.

l L. Comed has performed a detailed review of the relevant 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, j' including the maximum anticipated steam generator plugging levels presents no unreviewed safety questions and requires no Technical Specification changes. The Braidwood On-Site review of the reload 10CFR50.59 has been completed.

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NRC Document Control March 9,1995 Finally, further verification of the core design will be performed through limited scope physics tests. Since this is not a refueling outage, the requiremente for the start up physics test in ANSI /ANS 19.6.1 is not considered a requirement. ,

! If there are any questions regarding this matter, please contact this office.

S perely,

/ J Denise M.

ccomando Nuclear Licensing Administrator

• Attachment - Operating Limits Report, Braidwood Unit 1 Cycle SA cc: R. Assa, Braidwood Project Manager - NRR J. Martin, Regional Administrator - Rlli S. DuPont, Senior Resident inspector - Braidwood Office of Nuclear Facility Safety - IDNS t

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