ML20247J113

Application for Amend to License NPF-49,incorporating Attached Proposed Rev Into Chapter 15 of Unit 3 FSAR

ML20247J113
Person / Time
Site:	Millstone
Issue date:	05/07/1998
From:	Brothers M NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20247J118	List: B17211, Proposed Tech Specs Re Refueling Water Storage Tank Back Leakage ML20247J113
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-3.D.1.1, TASK-TM B17211, IEIN-91-056, IEIN-91-56, NUDOCS 9805210342
Download: ML20247J113 (5)

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Nuclear Energy wiri,too, Nocicar Po-cr staison Northeast Nuclear Energy Company P.O. Box 128

• Waterford, CT 06385-0128 (860) 447-1791 Fax (860) 444-4277 The Northeast Utihties System MAY - 7 1998 Docket No. 50-423 B17211 Re: 10CFR50.90 10CFR50.59 (a)(2)

U.S. Nuclear 3 gulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 3 Proposed License Amendment bquest Refuelina lNater Storaae Tank Back Leakaae (PLAR 3-98-3)

Pursuant to 10CFR50.90, Northeast Nuclear Encrgy Company (NNECO) hereby proposes to amend Operating License NPF-49 by incorporating the attached proposed revision into Chapter 15 of the Millstone Unit No. 3 Final Safety Analysis Report (FSAR).  !

The proposed revision to the Millstone Unit 3 licensing basis will address the addition  ;

of the dose from Refueling Water Storage Tank (RWST) back leakage into the design j basis loss of coolant accident analysis and Chapter 15 of the FSAR.

Description of Proposed Revision j

The original 1985 leakage reduction program instituted at Millstone Unit No. 3 conformed to Technical Specification 6.8.4.a and was accepted by the NRC as l appropriate in meeting the criteria of NUREG 0737 lil.D.1.1.

i NRC Information Notice (IN) 91-56, issued in September 1991, identified the l requirement to include leakage past valves which would not be externally detectable.

l The IN descr; bed potential situations involving radioactive water back-leakage in flow paths, outside of containment, that were not previously recognized as falling under Technical Specification 6.8.4.a criteria. Specifically, it was identified that certain emergency core cool?ng system idolation valves located outside of containment are subject to potential back leakage of highly radioactive containment sump water after 'Mh, isolation. The highly radioactive effluent could then be recirculated into tanks which are vented directly to atmosphere.

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U.S. Nuclerr Repuirtory Commission B17211\Page 2  !

I Based primarily on the credibility of valve failure in the leakage flow paths, an NNECO review of IN 91-56 cv.riudad that the probability was low that the situation described in the IN could occur at Millstone Unit No. 3. Although the report focused on the leakage paths identified in the IN, it did not expand into other areas that could also contain potential leakage paths. During a subsequent design basis review, back leakage frcm the Recirculation Spray System (RSS) to the RWST was identified as one such path.

Since the RWST is ' vented directly to atmosphere, it could contribute to an inadvertent release of radioactivity not previously accounted for in offsite dose evaluations. This condition was determined to be reportable pursuant to 10CFR50.73(a)(2)(i)(B) and, as such, was reported in LER 97-061, as any operation or condition prohibited by the plant's Technical Specifications, in addition, the NRC addressed this issue in inspection Report No. 50-423/97-206, dated March 9,1998.

Markuo of Proocsed Revision A copy of the marked up FSAR page is contained in Attachment 2. The markup reflects the currently issued version of the FSAR.

Backaround. Safety Assessment. Significant Hazards Consideration and Environmental Considerations The Background, Safety Assessment, Significant Hazards Consideration and Environmental Considerations that support this proposed revision are contained in Attachments 3 and 4.

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 10CFR50.91(b), we are providing the State of Connecticut with a .

copy of this proposed amendment to ensure the state's awareness of this request. l Schedule Reauest for NRC Accroval I NNECO requests NRC review and approval of this proposed revision by July 2,1998 and that the ;icense amendment be effective upon issuance with implementation within sixty (60) days.

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U.S. Nuclear Regul tory Commission '

B17211\Page 3 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 N LEAR ENERGY COMPANY j Mb m M. H. Elrothers 1 Vice President - Operations Subscribed and swom to before me this 74k day cf Mrit/ 1998

), e $ .

Date Comm sion Expires: //3/f2 COO cc: H. J. Miller, Region i Administrator W. D. Travers, Ph.D, Director, Special Projects Office J. W. Andersen, NRC Project Manager, Millstone Unit No. 3 A. C. Cerne, Senior Resident inspector, Millstone Unit No. 3 Director Bureau of Air Management Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127 i

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Docket No. 50- 423 I

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Attachment 1 Millstone Nuclear Power Station, Unit No. 3 ,

Proposed License Amendment Request  !

Refueling Water Storage Tank Back Leakage (PLAR 3-98-3)  ;

NNECO's Commitments l

May 1998 l

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U.S. Nuclear Regul: tory Commission B17211%ttachment 1\Page1 Enclosure List of Regulatory Commitments The following table identifies actions committed to by NNECO in this document. Please notify the Manager - Regulatory Compliance at the Millstone Nuclear Power Station Unit No. 3 of any questions regarding this document or any associated regulatory commitments.

Commitment Committed Date or Outage The overall Millstone Unit No. 3 Leaka0e Reduction B17211-01 Program, including the development of the System-To. Prior to RFO6 System Leakage test procedures, will be documented by the next refueling.

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