05000336/LER-1997-011, Forwards LER 97-011-00,documenting Event Occurred at Unit 2 on 970402.Commitments Made within Ltr Listed

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Forwards LER 97-011-00,documenting Event Occurred at Unit 2 on 970402.Commitments Made within Ltr Listed
ML20138J685
Person / Time
Site: Millstone Dominion icon.png
Issue date: 05/02/1997
From: Price J
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20138J688 List:
References
B16372, NUDOCS 9705080296
Download: ML20138J685 (2)


LER-1997-011, Forwards LER 97-011-00,documenting Event Occurred at Unit 2 on 970402.Commitments Made within Ltr Listed
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(ii)

10 CFR 50.73(a)(2)(v), Loss of Safety Function

10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
3361997011R00 - NRC Website

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g' Nuclear Energy siaision, Nocirar Po.er station Northeast Nuclear E,nergy Cornpany P.O. Hos 128 Waterford, Cr 063850128 (860) 447-1791 Faz (860) 444-4277 The Northeast Utilities Systern May 2,1997 Docket No. 50-336 B16372 Re: 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(v) 10 CFR 50.73(a)(2)(vii)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 This letter forwards Licensee Event Report (LER) 97-011-00, documenting an event that occurred at Millstone Nuclear Power Station, Unit No. 2 on April 2,1997. This LER is being submitted pursuant to 10 CFR 50.73(a)(2)(ii),10 CFR 50.73(a)(2)(v) and 10 CFR 50.73(a)(2)(vii).

The following are NNECO's commitments made within this letter.

l B16372-01:

Appropriate procedures shall be revised prior to entry into Mode 4 from the current outage to ensure that proper valve control parameters (benchset, air regulator, and stroke length) are specified and verified l

after any maintenance activities are performed that could affect dual l

function valve closing forces.

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l 9705080296 970502 PDR ADOCK 05000336 8

PDR 9 9 9 t, v.,

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t U. S. Nucicer Regulatory Commission l

B16372/Page 2 i

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B16372-02:

The affected valves will be adjusted to ensure they properly close against containment design pressure and NOSP, and they will be tested i

to ensure Appendix J, Type C leakage rate testing criteria are met.

j These activities will be performed prior to entry into Mode 4 from the current outage.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY l

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N J.A.P cif" Direct Millstone Unit No. 2 i

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Attachment: LER 97-011-00

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cc:

W. D. Travers, Director of Special Projects l

H. J. Miller, Region i Administrator i

D. P. Beaulieu, Senior Resident inspector, Millstone Unit No. 2 D. G. Mcdonald, Jr., NRC Senior Project Manager, Millstone Unit No. 2 1

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