B15482, Application for Amend to License NPF-49,revising TS 4.0.5a, SRs for ISI & Testing Program & Bases Section 3/4.4.10, Structural Integrity, Consistent w/NUREG-1431 & NUREG-1482

Application for Amend to License NPF-49,revising TS 4.0.5a, SRs for ISI & Testing Program & Bases Section 3/4.4.10, Structural Integrity, Consistent w/NUREG-1431 & NUREG-1482

ML20097D447
Person / Time
Site:	Millstone
Issue date:	02/05/1996
From:	Dacimo F NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20097D453	List: B15482, Application for Amend to License NPF-49,revising TS 4.0.5a, SRs for ISI & Testing Program & Bases Section 3/4.4.10, Structural Integrity, Consistent w/NUREG-1431 & NUREG-1482 ML20097D457
References
RTR-NUREG-1431, RTR-NUREG-1482 B15482, NUDOCS 9602120394
Download: ML20097D447 (3)

Text

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% Hartford, CT 06141-0270 i g (203) 665-5000 l February 5, 1996 Docket No. 50-423 B15482 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 Inmarvica Inspection and Tastina Proaram Northeast Nuclear Energy Company (NNECO) hereby proposes to amend Facility Operating License No. NPF-49 by incorporating the changes identified in the attachments into the Millstone Unit No. 3 Technical Specifications.

summary j NNECO proposes to revise the Millstone Unit No. 3 Technical  !

Specifications by deleting the phrase "(g), except where specific written relief has been granted by the Commission pursuant to i 10 CFR Part 50, Section 50.55a(g) (6) (i)" from Section 4.0.5a and Bases Section 3/4.4.10. This proposed change is consistent with NUREG-1431, " Standard Technical Specifications - Westinghouse Plants," and NUREG-1$82, " Guidelines for Inservice Testing at Nuclear Power Plants." Moreover, this proposed change is similar to a license amendment recently approved by the NRC on the Wolf Creek Nuclear Operating Corporation docket (Docket No. 50-482) . m The changes to Bases Sections 3/4.7.7 and 3/4.7.8 add design basis infor: nation and provide clarification of system design and operation- to facilitate interpretation of the technical specification action statements. These action statements cover plant operation when one or both trains of control room envelope pressurization are inoperable. These proposed changes only affect the Bases Section, therefore, they were reviewed in accordance with the provisions of 10CFR50.59 and approved by the Millstone Unit No. 3 Plant Operations Review Committee. The changes to Bases (1) Wolf Creek Generating Station - Amendment No. 90 to Facility Operating License No. NPF-42 (TAC NO. M93002), dated October 4, 1995.

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1 U.S. Nuclear Regulatory Commission I j B15482/Page 2 l

! February 5, 1996  ;

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l Sections 3/4.7.7 and 3/4.7.8 are being submitted to the NRC for

! information only.

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

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. Attachment 1 forwards the marked-up technical specification 3

pages.

! . Attachment 2 forwards the retyped technical specifications and 4

reflects the currently issued version of the technical

, specifications.

! . Attachment 3 describes the proposed technical specification

! changes.

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i . Attachment 4 provides a safety assessment for the changes.

NNECO has reviewed the proposed technical specification changes 1 in accordance with 10CFR50.92 and has determined that the changes do not involve a significant hazards consideration. )

The basis for this determination is discussed in Attachment 4.

j Environmental Considerations j i l

, NNECO has reviewed the proposed license amendment against the j j criteria of 10CFR51.22 for environmental considerations. The i proposed changes do not increase the types and amounts of affluents i

, that may be released offsite, nor significantly increase individual or cumulative occupational radiation exposures. Based on the i

foregoing, NNECO concludes that the proposed changes meet the l criteria delineated in 10CFR51.22(c)(9) for a categorical exclusion l from the requirements for an environmental impact statement.

State of Connecticut j In accordance with 10CFR51.91(b), the State of Connecticut is being provided with a copy of this license amends mt request.

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! Nuclear Safety Assessment Board The Nuclear Safety Assessment Board has reviewed the proposed changes and concurs with the above determinations.

f Schedule Required for NRC Approval 1

Regarding our proposed schedule for this amendment, we request ,

issuance at your earliest convenience, with the amendment effective  !

I as of the date of issuance and to be implemented within 60 days.

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t s U.S. Nuclear Regulatory Commission 5 B15482/Page 3 February 5, 1996 )

Should you have any questions, please contact Mr. R. G. Joshi at (860) 440-2080.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY s/f Ai F. R. Dacimo Vice President ( l I

cc: T. T. Martin, Region I Administrator V. L. Rooney, NRC Project Manager, Millstone Unit No. 3 l A. C. Cerne, Senior Project Manager, Millstone Unit No. 3 l

l Mr. Kevin T. A. McCarthy, Director Bureau of Air Management Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127 Subscribed and sworn to before me this b day of b , 1996

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/L Date Commission Expires:

SHERRY ). GHERMAN N O TA R Y I* G U LIC M Y CC :l.l~~. u. ..s.. m. .. 31,1933 o l I

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