ML20093G113

From kanterella
Jump to navigation Jump to search
Final Part 21 Rept Re Anchor Darling Valves in HPCS Sys. Initially Reported on 840127.Corrective Action Consists of Staking Antirotational Screws.Action Completion Expected by 841231
ML20093G113
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 06/29/1984
From: Lempges T
NIAGARA MOHAWK POWER CORP.
To: Starostecki R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
REF-PT21-84-369-000 (NMP2L-97), NMP2L-0097, NMP2L-97, PT21-84-369, PT21-84-369-000, NUDOCS 8407230326
Download: ML20093G113 (2)


Text

-

s.

M Y NIAGARA RUMOHAWK NIAGARA MOHAWK POWER CORPORATION /300 ERIE BOULEVARD WEST. SYRACUSE. N Y.13202/ TELEPHONE (315) 474-1511 June 29,1984 (NMP2L 0097)

Mr. R. W. Starostecki, Director U.S. Nuclear Regulatory Commission 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 a final report in accordance with 10CFR50.55(e) for the problem concerning Anchor-Darling valves (55(e)-84-03). This problem was reported via telecon to Mr. W. Lazerus of your staff on January 27, 1984. An interim report was submitted to the NRC via our letter dated February 27, 1984.

Very truly yours, DYD T.'E. Lempges Vice President Nuclear Generation TEL/TL:Ja Enclosure xc: Director of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 R. A. Gram, Resident Inspector Project File 8407230326 840629 gDRADOCK05000 1\\

t r 2' 1

NIAGARA M0 HAWK POWER CORPORATION NINE MILE POINT UNIT 2 00CKET N0. 50-410 Final Report for a Problem Concerning Anchor-Darling Valves (55(e)-84-03)

Description of the Problem The problem pertains to the Anchor-Darling globe valves used in the high-pressure core spray system.

The problem is attributed to the loosening of the antirotational set screws due to vibration in the valves.

General Electric has informed Niagara Mohawk Power Corporation that it has reported this problem to the Nuclear Regulatory Commission under 10CFR21.

The problem also was addressed by the Nuclear Regulatory Commission in I.E. Information Notice No. 83-70.

Three valves with Mark Nos. 2CSHH0V110,111 and 112 are affected.

Analysis of Safty Implications General Electric has stated tnat tnese valves may fail to operate as a result of this condition.

These valves are provided for flow testing of the high pressure core spray systems The loosening of the antirotational set screws and subsequent failure of valves 2CSHH0V110 and 112 to close after a testing operation would provide an open flow path from tne discharge of the high pressure core spray system pump to the condensate storage tank.

In addition, with valves 2CSH H0V110, 111 and 112 open, the effectiveness of the high pressure core spray system to respond following a loss of coolant accident would be reduced since high pressure core spray system injection water would preferentially flow to the lower pressure condensate storage tank and/or suppression pool rather than the reactor vessel.

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

Corrective Action 4

Tne corrective action will be to stake the antirotational screws.

This action is expected to be complete by December 31, 1984.

1::i :.

t

- tc

.. - _ - -. -