ML20197H652
| ML20197H652 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/13/1986 |
| From: | Salvesen R Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| NUDOCS 8605190227 | |
| Download: ML20197H652 (1) | |
Text
O PSEG Public Service Electric and Gas Company P. O. Box A Hancocks Bridge, New Jersey 08038 Hope Creek Generating Station May 13, 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 OF 04/13/86 On April 13,
- 1986, the HCGS Senior Nuclear Shift Supervisor contacted the NRC Operations Center to report an Engineered Safety System (ESP) Actuation.
The four-hour non emergency event report was made pursuant to 10CFR72(b) (2) (ii).
The event precipitating the notification was the automatic closure of the Reactor Water Cleanup System Supply Outboard Containment Isola-tion Valve (BG-HV-F004).
This valve provides both a containment and system isolation function and the isolation signalc associated with these functions are provided in section 3/4.3.2, ISOLATION ACTUATION INSTRUMENTATION, of the HCGS Technical Specifications.
Upon investigation into the event, it was determined that the subjecc valve had closed not on an ESF signal as. outlined in the HCGS Technical Specifications, but rather on a RWCU Deminerali-zer Inlet Temperature High-High signal.
This isolation function is provided to protect the resin in the ENCU demineralizers.
Since the closure of the valve was not due to an ESP
- signal, the event does not represent an ESF actuation as described in 10CFR58.72(b)(2)(ii) or 10CFR50.73(a)(2)(iv).
Thus a Licensee Event Report will not be submitted for this event.
Sincerely,
}.)(u & h M S S h ~
R.
S. Salvesen General Manager Hope Creek Operations SORC Mtg.86-107 C. Distribution
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