ML20214F604

Elucidated Ro:On 861022,HPCI Valve Failed to Open During Manual Operation.Undersized Motor Overloads Would Not Have Prevented Sys Operation.Ler Will Not Be Submitted Since Event Not Reportable Per 10CFR50.73

ML20214F604
Person / Time
Site:	Hope Creek
Issue date:	11/21/1986
From:	Salvesen R Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
NUDOCS 8611250365
Download: ML20214F604 (2)

Text

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O PSEG Pubhc Service Electnc and Gas Company P.O. Box L Hancocks Bndge, New Jersey 08038 Hope Creek Operations November 21, 1986 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

HOPE CREEK GENERATING STATION DOCKET NO. 50-354 UNIT NO. 1 CLARIFICATION OF FOUR-HOUR NON EMERGENCY EVENT REPORT OP 10/22/86 On October 22, 1986, the Hope Creek Generating Station Senior Nuclear Shift Supervisor (SNSS) made a four-hour nonemergency report regarding the failure of a High Pressure Coolant Injection (HCPI) valve to open during manual operation of the system. At the time of the event, the unit was operating at 75%

power and the HPCI system was undergoing startup testing. The SNSS interpretted the failure of the HPCI injection valve as a event or condition which alone could prevent the fulfillment of a safety function and thus made the appropriate notifications pursuant to 10CFR50.72 (b) (iii) .

Investigation into the failure revealed that the valve motor overloads were undersized causing the devices to trip prematurely. The root cause of the occurrence was attributed to ~

a design error in the sizing of the overloads and PSE&G has as a result instituted a program to verify the proper sizing of these devices in other motor-operated valves in the plant.

While the undersized motor overloads prevented the -valve from opening during the startup test, these same over1 cads would have had no effect on the operation of the systen under accident conditions or in response to a manual initiation signal. The motor overloads provide an equipment protection function used' during testing. The overload device, however, is bypassed under accident conditions (i.e., high drywell pressure, Level 2, or manual initiation signal) or by maintaining the OPEN/CLOSE pushbuttons depressed. Thus, the undersized motor overloads would not have prevented the operation of the system or the fulfillment of a safety function.

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To the US NRC 11/21/86 Based on the above described system design, plant management considers the action taken by the SNSS to be a conservative measure but not one required by 10CFR50.72. Similarly, the event does not meet the reporting requirements of 19CFR59.73 and as such, a Licensee Event Report will not be submitted for this occurrence.

Sincerely,

. S. Salvesen General Manager Hope Creek Operations WJM:tlb 1.999 C. Distribution l . _ . .--. _. _ _ . .-- . .. . _ - _ . - . .. , _ - .