B16758, Application for Amend to License NPF-49,modifying List of Valves That Can Be Opened in Modes 1 Through 4,removing Footnote on Type a Testing & Rewording TS & Bases to Provide Clarity & Consistency.Withdrawal Requested of 970630 LAR

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Application for Amend to License NPF-49,modifying List of Valves That Can Be Opened in Modes 1 Through 4,removing Footnote on Type a Testing & Rewording TS & Bases to Provide Clarity & Consistency.Withdrawal Requested of 970630 LAR
ML20211M899
Person / Time
Site: Millstone Dominion icon.png
Issue date: 10/07/1997
From: Brothers M
NORTHEAST NUCLEAR ENERGY CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20211M901 List:
References
B16758, NUDOCS 9710150173
Download: ML20211M899 (5)


Text

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%e Nortimt Utibtle. Sptein OCT ~ T 997 i-Docket No. 50-423 B16758 Re: 10CFR50.90 1

U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station Unit No. 3 Proposed Revision to. Technical Specification Containment Systems (PTSCR 3-34-97)

Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO), in a letter dated June 30,1997, proposed to amend Operating License NPF-49 by incorporating revisions (PTSCR 3-15-97) into the Millstone Unit No. 3 Technical Specifications 4.6.1.1, 3/4.6.1.2 and 3/4.6.1.3 and Bases Sections 3/4.6.1.1, 3/4.6.1.2 and 3/4.6.1.3.

NNECO has decided to modify that submittal by removing the request to add a footnote 1 * *"

- to Technical -Specification 4.6.1.1.a and modify footnote ** to Technical Specification 4.6.1.1.s and correcting the safety assessment description of the valves being removed from footnote ** as being inside the containment. Therefore, NNECO requests that our proposed revision to amond Operating License NPF-49, dated June 30,1997, be withdrawn and replaced by this proposed revision to the Millstone Unit No.

3 Technical Specifications 4.6.1.1, 3/4.6.1.2 and 3/4.6.1.3 and Bases Sections 3/4.6.1.1, 3/4.6.1.2 and 3/4.6.1.3.

Description of Proposed Revision Technical Specifications 4.6.1.1, 3/4.6.1.2 and 3/4.6,1.3 require the testing of the (Jo/

containment to verify leakage limits at a_ specified test pressure. The proposed changes will modify _ the list of valves that can be opened in modes 1 througi 4, remove a footnote on Type A testing, and reword the Technical Specifications ano Bases to provide clarity and consistency.

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4 U.S. Nuclear Regul: tory Commission B16758\Page 2 hiarkuo of Proposed Revisio_n A copy of the marked up Technical Specification pages is contained in Attachment 2.

The markup reflects the currently issued version of the Technical Specifications.

Pending Technical Specification revisions or Technical Specification revisions issued subsequent to this submittal are not reflected in the enclosed markup.

Retvoe of Proposed Revision A copy of the retyped Technical Specification pages are contained in Attachment 3.

The retyped pages reflect the currently issued version of the Technical Specifications.

Pending Technical Specification revisions or Technical Specification revisiono issued subsequent to this submittal are not reflected in the enclosed retype. The enclosed retype should be checked for continuity with Technical Specifications prior to issuance, f DEkground. Safety Assessment. Sianificant Hazards Consideration and l Environmental Considerations The Background, Safety Assessment, Significant Hazards Contideration and Environmental Considerations that support this proposed revision are contained in Attachments 4 and 5.

Plant Operations Review Committee and Nuclear Safety Assessment Board Review

.The Plant Operations Review Committee and the Nuclear Safety Assessment Board have reviewed this proposed amendment request and concur with the contained determinations.

State Notification in accordance with y(b), we are providing the State of Connecticut with a copy of this proposed amendment to ensure their awareness of this request.

Schedule Reauest for NRC Acoroval NNECO requests NRC review and approval of this proposed revision by November 21, 1997 and that the license amendment be effective upon issuance with implementation within sixty (60) days.

9

4 U.S. Nucl:ar R:gul: tor / Commission B16758\Page 3 The submittal of this proposed revision provides closure for the Licensee Event Reports 97-013-00 and 97-006-01 license amendment request commitments, if the NRC Staff should have any questions or comments regarding this submittal, please contact Mr. D. Smith at (860) 437-5840.

Very truly yours, NORTHEAST CLEAR ENERGY COMPANY l11$ ~

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M. H. Brothers \

Vice President - Millstone Unit No. 3 l Subscribed and sworn to before me this 7 day of A;4ebar .1997

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Date Commission Expires: iko 30 A00 t cc: H. J. Miller, Region I Administrator W.D. Travers,phD, Director, Special Projects Office J. W. Andersen, NRC Project Manager, Millstone Unit No. 3 A. C. Cerne, Senior Resident inspector, Millstone Unit No. 3 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 2

4 Docket No. 50-423 E11Zhl l

l Attachment 1 Millstone Nuclear Power Station Unit No. 3 Proposed Revision to Technical Specification Containment Systems (PTSCR 3-34-97)

NNECO's Commitments i October 1997

  • O.S. Nuclear Regul: tory Commission B16758%ttachment 1\Page1 Enclosure List of Regulatory Commitments The following table identifies those actions committed to by NNECO in this document.

I Please notify the Manager - Regulatory Compliance at the Millstone Nuclear Power l Station Unit No. 3 of any questions regarding this document or any associated regulatory commitments.

Commitment Committed Date or Outage NONE N/A e