ML20154R653

Supplemental Application for Amend to License NPF-11, Changing Tech Specs Re Thermal Hydraulic Stability Requirements for Cycle 2 Reload Licensing Package

ML20154R653
Person / Time
Site:	LaSalle
Issue date:	03/21/1986
From:	Allen C COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20154R655	List: ML20154R653 ML20154R658
References
1438K, NUDOCS 8603310125
Download: ML20154R653 (3)

Text

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v Commonwe:lth Edison

'O ) One First National Plaza. Chicago. Illinois O Address Reply to: Post Office Box 767 Chicago. Illinois 60690 March 21, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Conunission Washington, DC 20535 i

Subject:

LaSalle County Station Unit 1

Supplemental Information to Proposed Amendment Technical Specification for Facility Operating License NPF-ll - Reload Licensing-i Package for Cycle 2 NRC Docket No. 50-373 i

Reference (a): H. L. Massin letter to H. R. Denton dated October 22, 1985.

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Dear Mr. Denton:

Pursuant to 10 CFR 50.90, Commonwealth Edison proposes to amend Appendix A. Technical Specification, to Facility Operating License NPF-11. '

These changes are being submitted for your staff's review and approval and are as discussed in several telecons with your staff' reviewers.

i Attachment A provides background and discussion. The proposed i changes are enclosed in Attachment B. The attached change has received both On-Site and Off-Site review and approval. We have reviewed this amendment request and find that no significant hazards consideration exists. Our review is documented in Attachment C.

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Conunonwealth Edison is notifying the State of Illinois of our request for this amendment by transmitting a copy of this letter and attachments to the designated State Official.

Please direct any questions you may have concerning this matter to i this office.

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H. R. Denton March 21, 1986 One signed original and fifteen (15) copies of this transmittal and its attachments are provided for your use.

Very truly yours, tb C. M. Allen Nuclear Licensing Administrator im Attachments A: Background and Discussion B: Technical Specification Change to NPF-ll C: Evaluation of No Significant Hazards Consideration-cc: Region III Inspector.- LSCS Dr. A. Bournia - NRR M. C. Parker - State of Ill 1438K

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ATTACIORENT A l

l LASALLE COUNTY STATION UNIT 1

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l TECHNICAL SPECIFICATION SUPPLEMENTAL CHANGE REQUEST l

l BACKGROUND: Recent discussion with the Nuclear Regulatory Conunission (NRC) on LaSalle's Unit 1 Cycle 2 Reload Licensing Submittal have i clarified NRC concerns in the area of thermal hydraulic stability. To address these concerns LaSalle is amending the stability Technical Specification previously submitted.

Specifically, the proposed Technical Specification on thermal hydraulic stability (3/4.4.1.5) is being withdrawn, and

stability requirements have been incorporated into the reactor recirculation Technical Specification (3/4.4.1.1). LaSalle Unit 1 Cycle 2 will have stability requirements during single loop operation only.

The thermal hydraulic requirements which are being added to l Technical Specification 3/4.4.1.1 limits single loop operation in a designated restricted region (greater than 80% rod line and less than 39% core flow) of the power-to-flow map. Also required is the monitoring of APRM and LPRM noise levels when operating in a designated surveillance region (greater than 80%

rod line and less than 45% core flow) of the power-to-flow map.

i j No stability monitoring is required in two loop operation

because that cycle specific decay ratio of 0.6 is lower than j the NRC limit of 0.8. GE has confirmed this value at~

Conunonwealth Edison's request. GE attributes the decay ratio i

value to a low (less negative) void coefficient which is due to i the low initial enrichment and low fuel exposure values.

l Included in Attachment B are the pages changed from the original submittal.

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