ML20236J000
| ML20236J000 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/30/1987 |
| From: | Cowles R, Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 87-006-00, 87-6, NUDOCS 8711050089 | |
| Download: ML20236J000 (2) | |
Text
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O NACFee. 330 W 8. NUCLE AJB KEGULATCAY CO8 sin'S$lON AWOvtO ONe NO J150-4104 LICENSEE EVENT REPORT (LER)
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P4VE W Hope Creek Generating Station ois1oio;o131514 1 lOFl 0l 1 High Pressure Coolant Injection (HPCI)l Water LevelSystem Injection During Reactor Scram Due To Low Reactor Vesse tytNY DATS (51 Lan Nunnsen toi mtPOafDAfflH QTHER F ACILITIES INVOLVED ist MONTM OAY YEAA YtAR
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Cowles, Lead Engineer - Technical
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, n..a, e.-n., ma o s, This Special Report is being submitted pursuant to the requirements of Technical Specification 3.5.1 Action g.
to document the circumstances of a High Pressure Coolant Injection system injection to the reactor vessel on 7/30/87. The HPCI injection occurred as a result of low reactor vessel wat'er level excursion (level 2,
-38")
experienced immediately following a reactor scram.
For a description of the
)
refer to LER 87-034.
HPCI injected to the vessel for approximately 20 minutes.
At the onset of the injection, vessel pressure was about 950
- PSI, and vessel temperature about 550 degrees Fahrenheit.
When t t.e injection was terminated, pressure was 925 PSI and temperature 500 degrees Fahrenheit.
As of 7/30/87, Hope Creek had I
experienced 7 HPCI injections to the reactor vessel (120 cycles are allowed by the FSAR).- Because of the early life of the plant, the HPCI injection nozzle usage factor has not been calculated.
The station is in the initial stages of implementing a thermal cycle tracking program.
This program will allow the calculation of component thermal usage factors.
RBC/
p'~ g SORC Mtg.87-157
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8711050089 071030
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PDR ADOCK 050 4
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'O PSEG Public Service Electric and Gu Company P.O. Box L Hancocks Bridge, New Jersey 08038 Hope Creek Operations October 30, 1987 U.
S.
Nuclear Regulatory Commission Document Conttol Desk Washington, DC 20555
Dear Sir:
HOPE CREEK GENERATING STATION DOCKET NO. 50-354 UNIT NO. 1 I
f SPECIAL REPORT 87-006-00 This Special Report is being submitted pursuant to the requirements of Technical Specification 3.5.1 Action g.
Sincerely, he (a be S.
LaBruna General Manager -
Hope Creek Operations RBC/
Attachment SORC Mtg.87-157 C Distribution I
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The Energy People 95 2173,' I W 5 67
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