B17342, Application for Amend to License NPF-49,proposing Rev to TS 4.7.10.e to Eliminate Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred

Application for Amend to License NPF-49,proposing Rev to TS 4.7.10.e to Eliminate Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred

ML20197G975
Person / Time
Site:	Millstone
Issue date:	12/04/1998
From:	Bowling M NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20197G979	List: B17342, Application for Amend to License NPF-49,proposing Rev to TS 4.7.10.e to Eliminate Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred ML20197G983
References
B17342, NUDOCS 9812110093
Download: ML20197G975 (5)

Text

,. g Rope Ferry Rd. (Route 156), Waerford, CT 06385

. Nuclear Energy viiistone N cica, rower sintion Northeast Nuclear Energy Compaoy P.O. Box 128

, , Waterford, CF 06335-0128 (860) 447-1791 Fax (860) 444-4277 The Northeast Utilities System DEC - 41998 Docket No. 50-423 B17342 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 Specification Snubber Functional Test Insoection Interval (TSCR 3-25-98)

. Pursuant to 10CFR50.90, Northeast. Nuclear Energy Company (NNECO) hereby proposes to amend Operating License NPF-49 by incorporating the attached proposed revision into Millstone Unit No. 3 Technical Specification Surveillance 4.7.10.e.

Description of Proposed Revision Technical Specification Surveillance 4.7.10.e requires the functional testing of a representative sample of snubbers at least once each refueling interval. During the recent extended shutdown,. snubber inspections occurred over the interval of the shutdown with the first inspection being performed on September 10,1996, and the last 1 inspection was performed on September 23, 1997. Given the nominal 24-month I; surveillance interval, and considering the 25 percent extension allowed by Technical /

. Specification 4.0.2, and conservatively considering the beginning of the recently completed inspections as the start of the interval, results in a date of March 10,1999, by which the next snubber inspection interval would be required. The next refueling outage, RFO6, is presently scheduled for May 1999 and an additional plant shutdown would be required to complete the inspections, since many of the snubbers are not fg accessible during plant operation. The proposed revision would eliminate the need to cycle the plant and its components through a shutdown-startup cycle by allowing the next snubber surveillance interval to be deferred until the end of RFO6 or September 10,1999, whichever date is earlier. This proposed revision to Technical Specification Surveillance 4.7.10.e was evaluated to be safe and to not involve a 10CFR50.59 Unreviewed Safety Question.

9812110093 981204 PDR F

ADOCK 05000423 6 mdsmxms O

U.S. Nucl: r Regulatory Commission B17342\Pago 2 Markuo of Proposed Revision A copy of the marked up Technical Specification pages is contained in Attachment 1.

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 2.

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

Pending Technical Specification revisions or Technical Specification revisions issued i 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.

Backaround. Safety Assessment. Sianificant 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 their awareness of this request.

Schedule Reauest for NRC Approval NNECO requests expedited NRC review and approval of this proposed revision, and that the license amendment be effective upon issuance.

There are no regulatory commitments contained within this letter.

U.S. Nuclear Regul'_ tory Commis ion B17342\Page 3 If the NRC Staff should have any questions or comments regarding this submittal, l please contact Mr. D. Smith at (860) 437-5840.

Very truly yours, I

NORTHEAST NUCLEAR ENERGY COMPANY f

Martin L. Bowling V

Recovery Officer -Technical Services Swom to d subscribed before me this day of 1998 f),

nsx ow l ota r P'ublic MY COMMISSION EXPlRES JUNE 30,2002 My Commission expires l

l l cc: H. J. Miller, Region i Administrator J. W. Andersen, NRC Project Manager, Millstone Unit No. 3 A. C. Cerne, Senior Resident inspector, Millstone Unit No. 3 l Director Bureau of Air Management l Monitoring and Radiation Division l Department of Environmental Protection l 79 Elm Street l Hartford, CT 06106-5127 l

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l Docket No. 50-423 B17342 t

Attachment 1 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specification Snubber Functional Test inspection Interval (TSCR 3-25-98) i Marked Up Page 1

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l December 1998 4

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. . U.S. Nuclear Regulatory Commission B17342%ttachment 1Page 1 1

MARKUP OF PROPOSED REVISION Refer to the attached markup of the proposed revision to the Technical Specifications. The attached markup reflects the currently issued version of the l

Technical Specifications listed below. Pending Technical Specification revisions j or Technical Specification revisions issued subsequent to this submittal are not l reflected in the enclosed markup.

The following Technical Specification change is included in the attached

, markup.

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. Technical Specification Surveillance 4.7.10.e is reworded to identify that the i surveillance interval is deferred until the end of the next refueling outage or September 10,1999, whichever date is earlier.

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