B15293, Application for Amend to License NPF-49.Amend Would Support 24-month Fuel Cycle Surveillance Extension for Unit 3

Application for Amend to License NPF-49.Amend Would Support 24-month Fuel Cycle Surveillance Extension for Unit 3

ML20086M108
Person / Time
Site:	Millstone
Issue date:	07/18/1995
From:	Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20086M112	List: B15293, Application for Amend to License NPF-49.Amend Would Support 24-month Fuel Cycle Surveillance Extension for Unit 3 ML20086M115
References
B15293, NUDOCS 9507240131
Download: ML20086M108 (5)

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P.O. Box 270 Hartford, Cr 06141-0270 (203) 665-5000 July 18, 1995 Docket No. 50-423 B15293 Re:- 10CFR50.90 .

U.S. Nuclear Regulatory Commission

. Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No.:3 Proposed Revision to Technical Specifications 24-Month Fuel Cycle - Reactor Coolant System Surveillance Extensions Introduction Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) to amend its Operating License,~ NPF-49, by hereby proposes incorporating the attached proposed changes into .the Millstone Unit No. 3 Technical Specifications.

Discussion The amendment request included in_-this letter repr8Fents a defined group'of submittals necessary to support the 24-month fuel. cycle We expect to.

su'rveillance extensions for Millstone Unit No. 3.

submit license amendment requests-at regular' intervals, with the last request to be submitted in late July.1995.

This submittal is considered a cost beneficial licensing action by NNECO. Implementation of a 24-month fuel cycle ~ would save in excess of the $100,000 guideline identified by the NRC Staff with no reduction in public health and safety.

This ~ submittal modifies the frequency of several surveillance requirements of the Millstone Unit No. 3 Technical Specifications.

Thesti surveillance requirements pertain; to _ the reactor coolant system.

In support of' this license amendment- request, the following information is provided:

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l U.S. Nuclear Regulatory Commission B15293/Page 2 July 18, 1995 1

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Attachment 1 and Attachment 2 forward the marked-up and retyped technical specification pages, and reflect the currently issued version of the technical specifications.

Attachment 3 describes the proposed technical specification changes.

Attachment 4 provides a safety assessment for the changes.

NNECO has reviewed the proposed technical specification changes in accordance with 10CFR50.92 and has determined that the changes do not involve a significant hazards consideration (SHC). The basis for this determination is discussed in Attachment 4.

Moreover, the Commission has provided guidance concerning the application of standards in 10CFR50.92 by providing certain examples (March 6, 1986, 51 FR 7751) of amendments that are considered not likely to involve an SHC. The proposed changes described in Attachment 3 are not enveloped by a specific example.

However, it has been demonstrated (i.e., Attachment 4) that the proposed changes do not involve an SHC. Therefore, the proposed changes do not negatively impact the public health or safety.

Environmental Consideration NNECO has reviewed the proposed license amendment against the criteria of 10CFR51.22 for environmental considerations. The proposed changes do not involve an SHC, do not significantly increase the types and amounts of effluents that may be released off site, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, NNECO concludes that the proposed changes meet the criteria delineated in 10CFR51. 22 (c) (9) for a categorical exclusion from the requirement of an environmental impact statement.

Nuclear Safety Assessment Board Review The Nuclear Safety Assessment Board has reviewed this proposed amendment request and concurs with the above determination.

State Notification In accordance with 10CFR50.91(b) , we are providing the State of Connecticut with a copy of this proposed amendment request to  !

ensure their awareness of this request.  !

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L U.S. Nuclear Regulatory Commission B15293/Page 3 July 18, 1995 schedule Reauired for NRC Accroval As stated earlier, the remaining amendment requests will be j submitted at regular intervals, with the last request to be submitted in late July 1995. On June 7,1995, Millstone Unit No. 3 l t

began operating on a 24-month fuel cycle instead of the previous i 18-month fuel cycle. It is our objective to obtain NRC approval of l all the amendment requests related to the 24-month fuel cycle by 1 September 1996. NNECO requests that the license amendment be effective upon issuance with implementation within 90 days.

If the NRC Staff should have any questions or comments regarding this submittal, please contact Mr. R. G. Joshi at (203) 440-2080.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY 4 L J. F. dpekh O Executive Vice President cc: T. T. Martin, Region I Administrator V. L. Rooney, NRC Project Manager, Millstone Unit No. 3 P. D. Swetland, Senior Resident Inspector, Millstone Unit Nos. 1, 2, and 3 Mr. Kevin T.A. McCarthy, Director Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street P.O. Box 5066 Hartford, CT 06102-5066 I

Subscribed and sworn to before me l this /8 day of Og;[1] , 1995 )

ei n) Qn kmdA1 Date Commission Expires: 8!3/

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Docket No. 50-423 B15293 Attachment 1 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications 24-Month Fuel Cycle Reactor Coolant System Surveillance Extension Marked-Up Pages 1

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1 July 1995

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U.S. Nuclear Regulatory Commission B15293/ Attachment 1/Page 1 July 18, 1995 y l

Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical specifications 24-Month Fuel Cycle Reactor Coolant System Page Number and Section Title Amendment Number 3.4.4 Relief Valve 3/4 4-12*, 4-13, Amendment No. 88 3.4.6.1 Leakage Detection Systems - 3/4 4-21, Amendment No.100 3.4.6.2 Operational Leakage 3/4 4-22*, 4-23, Amendment No. 100 3.4.9.3 Overpressure Protection System 3/4 4-38*, 4-39, 4-39, Amendment No. 100 3.4.11 Reactor Coolant System Vents 3/4 4-43*, Amendment No. 100 3/4 4-43a, Amendment No. 88 CNo changes are required. These pages are provided for information only.

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