ML20203D641

Forwards Operating Limits Rept for Braidwood Units 1 & 2, Cycle 7. Operating Limit Rept Revs Being Provided to NRC in Accordance W/Provisions of Section 6.9.1.9 of Plant Tech Specs

ML20203D641
Person / Time
Site:	Braidwood
Issue date:	12/09/1997
From:	Tulon T COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20203D644	List: ML20203D641 ML20203D665 ML20203D753 ML20203D772
References
NUDOCS 9712160250
Download: ML20203D641 (3)

Text

0:nunonw calth Idnon Oimpany liraidmx.! Gencrating Station Route *I, llox Hi liram ille,11. u mr%19 TriHj06 W 2W)l December 9,1997 Oflice of Nuclear Reactor Regulation U. o Nuclear Regulatory Commission Washington, D. C 20555 ATTN: Document Control Desk

SUBJECT:

Braidwood Unit 1 Cycle 7 Operating Limits Repon-Revision i Braidwood Unit 2 Cycle 7 Operating Limits Report-Revisions I and 2 Attached are Braidwood Unit 1 Cycle 7 Operating Limits Report (OLR)-Revision 1, and Braidwood Unit 2 Cycle 7 Operating Limits Repon Revisions 1 and 2. These OLR revisions are being provided to the NRC in accordance with the provisions of Section 6.9.l.9 of the Braidwood Technical Specifications.

Fxy"" in Revision 0 of the BRIC7 and Revisions 0 and 1 of the BR2C7 OLR were identified as being non-conservative in the upper core region due to a discrepancy identified in the OLR development process. Revision I of the BRIC7 OLR and Revision 2 of the BR2C7 OLR corrected the discrepancy and in addition, prosided burnup dependent i<'xy"" limits.

Section 2.5.2, "licat Flux Hot Channel Factor," of the OLRs has been revised as follows.

In Revision 1 of the BRIC7 OLR, burnup dependent Fxy"" limits have been provided. In Revision i of the BR2C7 OLR, the lower core region was divided into two regions, o to 22%, and 22 to 50% core height, for the purposes of defining F,y"" limits. In Revision 2 of the BR2C7 OLR, burnup dependent Fxy"* limits have been provided. These changes have been made utilizing NRC approved methodologies as described in Section 6.9.1.9 of the Braidwood Technical Specifications.

All Fxy surveillances which were performed using the non-conservative Fxy"" values were re-evaluated using the corrected Fxy"" limits. The re-evaluation concluded all prior Unit 1 and Unit 2 Cycle 7 surveillances met all Fxy"" and Fxy' limits as defined in Braidwood Technical Specification 3/4.2.2. () ', i vn 971216025d971209 ,

f ,i A Unkum Cumguny

Document Control Desk Page 2 December 9,1997 If there are any questions regarding this issue, please contact this oflice.

Sincerely, othy J. Tulon ite Vice President Braidwood Nuclear Generating Station Attachments - Braidwood Unit 1 Cycle 7 Operating Limits Report - Revision 1 Braidwood Unit 2 Cycle 7 Operating Limits Report - Revision 1 Braidwood Unit 2 Cycle 7 Operating Limits Report - Revision 2 cc: A. B. Beach, Regional Administrator - Rill G. Dick, Braidwood Project Manager - NRR C. J. Phillips, Senior Resident Inspector - Braidwood Office of Nuclear Safety - IDNS cA..rtc197133mt &c l

i Braidwood Unit 1 Cycle 7 Operating Limits Report Revision 1

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