05000423/LER-1996-007-02, Forwards LER 96-007-02 Which Supplements Rept Submitted on 960502,per 10CFR50.73(a)(2)(ii)(B),10CFR50.73(a)(2)(v)(B&D), 10CFR50.73(a)(2)(vii)(B&D).Commitments in Response to Event, Encl

Forwards LER 96-007-02 Which Supplements Rept Submitted on 960502,per 10CFR50.73(a)(2)(ii)(B),10CFR50.73(a)(2)(v)(B&D), 10CFR50.73(a)(2)(vii)(B&D).Commitments in Response to Event, Encl

ML20132G013
Person / Time
Site:	Millstone
Issue date:	12/13/1996
From:	Brothers M NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20132G017	List: 05000423/LER-1996-007, :on 960403,containment Recirculation Spray, Quench Spray & Safety Injection Sys Were Outside Design Basis Due to Design Errors.Design Reviews of Rss,Qss,Si & Other Sys Will Be Performed 05000423/LER-1996-007-02, Forwards LER 96-007-02 Which Supplements Rept Submitted on 960502,per 10CFR50.73(a)(2)(ii)(B),10CFR50.73(a)(2)(v)(B&D), 10CFR50.73(a)(2)(vii)(B&D).Commitments in Response to Event, Encl
References
B15967, NUDOCS 9612260156
Download: ML20132G013 (4)

LER-1996-007, Forwards LER 96-007-02 Which Supplements Rept Submitted on 960502,per 10CFR50.73(a)(2)(ii)(B),10CFR50.73(a)(2)(v)(B&D), 10CFR50.73(a)(2)(vii)(B&D).Commitments in Response to Event, Encl

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii)(B), Common Cause Inoperability 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)
4231996007R02 - NRC Website

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["}F NuclearEnergy Northeast hope Fury Rd. (Rouw 1W, Wetafwd, Cm385 Malstone Nucleu Pown Station Northeast Nuclear Energy Company P.O. Box 128 Taterford, CT 06385-0128 (203) 447-1791 Fax (203) 444-4277 he Northeast Utilities System December 13,1996 Docket No. 50-Cs, B15967 Re: 10CFR50.73(a)(2)(ii)(B) 10CFR50.73(a)(2)(v)(B) 10CFR50.73(a)(2)(v)(D)

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10CFR50.73(a)(2)(vii)(B) 10CFR50.73(a)(2)(vii)(D)

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U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 l

Millstone Nuclear Power Station Unit 3

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Licensee Event Report 96-007-02 Submitted Pursuant to 10CFR50.73(a)(2)(ii)(B),10CFR50.73(a)(2)(v)(B&D) j and 10CFR50.73(a)(2)(vii)(B&D)

This letter forwards Licensee Event Report 96 007-02, supplementing the report that was submitted on. May 2,1996. This LER is submitted pursuant to 10CFR 50.73(a)(2)(ii)(B),10CFR50.73(a)(2)(v)(B&D) and 10CFR50.73(a)(2)(vil)(B&D).

NNECO's commitments in response to this event are contained within to this letter.

Should you have any questions regarding this submittal, please contact Mr.

James M. Peschel at (860) 437-5840.

i Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

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M. Hgrothers Unit Director, Millst ne U No.3 J

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U.S. Nucl;ar Regulatory Commission B15967Page 2 i

Attachment: 1)

NNECO's commitments in response to LER 96-007-02 2)

LER 96-007-02 i

cc-H. J.

Miller, Region i Administrator A. C. Corne, Senior Resident inspector, Millstone Unit No. 3 V. L. Rooney, NRC Project Manager, Millstone Unit No. 3 W. D. Travers, Dr., Director, Special Projects i

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l Docket No. 50-423 B15967 Millstone Nuclear Power Station, Unit No. 3 NNECO's Commitments in Response To (LER 96-007-02)

December 13,1996

Enclosure List of Regulatory Commitments The following table identifies.those actions committed to by NNECO in this document. Any other actions discussed in the submittal represent intended or planned actions by NNECO.

They are described to the NRC for the NRC's irformation and are not regulatory commitments.

Please notify the Manager -

4 Nuclear Licensing at the Millstone Nuclear Power Station Unit No. 3 of any questions regarding this document or any associated regulatory commitments.

Number

Commitment

Due Date 4

B15847 The design reviews of the RSS, QSS, and SI prior to declaring

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piping systems will be completed and the the systems design modifications required to restore the operable for other systems to design basis requirements will be than mode 5 and 6.

completed.

B15847-02 A review of those systems which would be prior to entry into exposed to a Post-LOCA or Post HELB Mode 4 environment and which are required to mitigate the consequences of a design basis accident will be performed to determine whether or not they are susceptible to the same types of design deficiencies, and to ensure the systems comply with the design basis requirements.

Number

Commitment

Due Date i

B15967-01 The plant's Stress Data Package (SDPs)s prior to entry into will be reviewed, and corrected Mode 4 B15967-02 The updated SDPs will be added to the prior to entry into controlled documents list following Mode 4 completion of the reviews.

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