ML20087H719

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Interim Deficiency Rept Re Anchor Darling HPCS Sys Valve Vibration Loosening anti-rotational Set Screws.Initially Reported on 840127 & Reported by GE Per Part 21. Investigation in Progress.Final Rept by 840723
ML20087H719
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 02/27/1984
From: Mangan C
NIAGARA MOHAWK POWER CORP.
To: Starostecki R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
REF-PT21-84 8113, NUDOCS 8403210136
Download: ML20087H719 (2)


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N M atM N6AGARA MOHAWK POWER CORPORATION /300 ERIE BOULEVARD WEST. SYRACUSE. N.Y.13202/ TELEPHONE (315) 4741511 February 27, 1984 (8113)

Mr. R. W. Starostecki, Director U.S. Nuclear Regulatory Commiss,n Region I

- Division of Project and Resident Programs 631 Park Avenue King of Prussia, PA 19406 Re: Nine Mile Point Unit 2 Docket No. 50-410

Dear.Mr. Starostecki:

Enclosed is an interim repcrt in accordance with 10CFR50.55(c) for the problem concerning Anchor-Darling valves. This problem was reported via

'telecon to W. -Lazerus of your staff ori January 27, 1984.

Very truly yours, aM C.V.Mangs Vice President Nuclear Engineering & Licensing CVM/MWS:ja Enclosure xc: Director of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 8403210136 840227 PDR ADOCK 05000410 S

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NIAGARA M0 HAWK POWER CORPORATION NINE MILE POINT - UNIT 2 DOCKET N0. 50-410-Interim Report for a Problem

- Concerning Anchor-Darling Valves (55(e) 03) j

. Description of the' Problem a

The problem pertains.to the Anchor-Darling globe valves used in the lhigh-pressure core spray system.:- The problem is attributed to the loosening of the antirotational set screws, due to the vibration in these valves.

General' Electric (GE) has informed Niagara Mohawk that it has reported.this problem to the Nuclear Regulatory Commission under 10CFR21.

The problen was also addressed by the Nuclear Regulatory Commission in I.E. Information Notice No.- 83-70.1 On Nine Mile Point Unit 2, three valves with mark Numbers 2CSH8M0V110,111 and 112 are affected.

Analysis of Safety Implications General Electric believes that these. valves may fail to operate as a result of tthis condition. On Nine Mile: Point Unit 2, these valves are provided for flow

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r testing of the HPCS.

The failure of valves 2CSH*MOVil0.and 112 to close after a testing operation would provide an open flow path from.the discharge of the HPCS pump to the-condensate storage tank.

In addition, with. valves

' 2CSH8MOV110,111 and 112 open. the effectiveness of the HPCS system to respond

. following a LOCA would be reduced, since HPCS -injection water would preferentially. flow to.the lower pressure condensate storage tank and/or-l suppression. pool rather than the reactor vessel.

Therefore, if this problem remained uncorrected, it could have adversely affected the safety of operation o-of the plant.. As a result, the criteria for reportability under 10CFR50.55(e)

'have.been met.

' Corrective Action i

The corrective action is still being investigated and a final report will be submitted by: July, 23 1984.

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