ML20087H774

Advises NRC of Comm Ed Review of Cycle 7 Reload Under Provisions of 10CFR50.59 & Transmits LaSalle Unit 1 Cycle 7 COLR & LaSalle Unit 2 Cycle 7 COLR, Per GL 88-16

ML20087H774
Person / Time
Site:	LaSalle
Issue date:	04/28/1995
From:	Gerner L COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20087H777	List: ML20087H774 ML20087H778 ML20087H781
References
GL-88-16, TAC-M89631, TAC-M89632, NUDOCS 9505040393
Download: ML20087H774 (2)

Text

.

, Ormmonwealth I AINin Company ,

IAalle Generating Mation j o Biol North 21st Road Wrwdles, II. 61.4 6 i M F 1 Tel HI KAPW'61 April 28,1995 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Subject- LaSalle County Nuclear Power Station i Unit 1 Cycle 7 Core Operating Limits Report Mid-Cycle Change Unit 2 Cycle 7 Reload and Core Operating Limits Report NRC Docket Nos. 50-373 and 50-374

Reference:

Letter, W. D. Reckley to D. L. Farrar, *lssuance of Amendments (TAC Nos. M89631 and M89632)", April 13,1995.

LaSalle County Unit 2 is currently preparing for Cycle 7 startup (estimated startup date is May '

5,1995). The purpose of this letter is to advise you of Commonwealth Edison's (Comed) review of the Cycle 7 reload under the provisions of 10CFR50.59 and to transmit the Core Operating Limits Report (COLR) for the upcoming cycle consistent with Generic Letter 88-16. The Unit 1 Cycle 7 Core Operating Umits Report (Attachment A) is also being transmitted since it has been changed mid-cycle to include the ARTS thermal limits approved in the referenced transmittal. In addition, the COLR methodology references previously included in the COLR in anticipation of removal of those references

. . . . ..f. rom Technical. Specification Sectior16.6 A.6.b have beeadeleted.. An amendment,to. remove these -

references from the Technical Specifications is no longer being pursued. A new section is also included which contains a matrix of allowed operating modes and Equipment Out-of-Service combinations. The above mentioned changes have also been made to the Unit 2 Cycle 7 COLR.

The LaSalle County Unit 2 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 accepted; or t

2) reanalysis has been performed to demonstrate that the limiting postulated FSAR events which could be affected by the reload are within allowable limits.

Consistent with past reloads, the reload licensing analyses performed for Cycle 7 utilized NRC-approved methodologies. The fresh fuel to be loaded in Cycle 7 consists of 80 bundles of fuel type GE98-P8CWB320-9GZ3-100M-150-CECO with a bundle average enrichment of 3.20 and 9 Gd Rods, and 96 bundles of fuel type GE9B-P8CWB322-11GZ-100M-150-CECO with a bundle average enrichment of 3.22 and 11 Gd Rods. The cycle-specific power distribution limits for Cycle 7 are presented in the attached Unit 2 COLR.

)

9505040393 950428 PDR ADOCK 05000373 P PDR i 1

i 4 i 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 l requered by 10CFR50.59, which concluded that the reload presents no unreviewed safety questions )

and requires no Technical Specification changes. The 10CFR50.59 evaluation for the Unit 2 reload i and the Unit 1 mid-cycle COLR change have been approved by LaSalle County Senior Station l Management and Onsite Review in accordance with Station procedures. '

Further veiification of the reload core design will be performed during startup testing. The startup tests will be consistent with Technical Specifications and testing recommended in Draft Regulatory Guide Task SC 521-4. As in the past, a summary of the results of key startup tests will be submitted within 90 days following the resumption of commercial operation.

Based on the preceding discussion, Comed has concluded that NRC review and approval of j the reload analyses is not required for resumption of Unit 2 operation with the Cycle 7 core, and NRC review and approval of the additional above described changes is not required for implementation of the revised Unit 1 Cycle 7 COLR.

Very truly yours, E- l Lawrence F. Gemer l Regulatory Assurance Manager '

Attachments:

.. . . . . . . . . . - - - - . . . . - . - - . . - - - - -- - - - - - - - - - - - - - - - - - - - - - - a A. Core Operating Limits Report, LaSalle County Unit 1 Cycle 7 B. Core Operating Limits Report, LaSalle County Unit 2 Cycle 7 l

cc: J. B. Martin - Regional Administrator, Region lli l P. G. Brochman - Senior Resident inspector I W. D. Reckley - Project Manager, NRR L. E. Phillips - Reactor Systems Branch, NRR ,

Office of Nuclear Facility Safety - IDNS '

Central File (w/o) l l

l i

)

l l

i