ML20236J000

Special Rept 87-006-00:on 870730,HPCI Sys Injection Reactor Scram Occurred.Caused by Low Reactor Vessel Water Level Excursion.Plant in Initial Stages of Implementing Thermal Cycle Tracking Program

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)

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NACFee. 330 W 8. NUCLE AJB KEGULATCAY CO8 sin'S$lON AWOvtO ONe NO J150-4104

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LICENSEE EVENT REPORT (LER)

PACILITV NAAff Of DOCKET NUnettR 12) P4VE W Hope Creek Generating Station ois1oio;o131514 1 lOFl 0l 1 High Reactor Pressure ScramCoolant Due To Injection Low Reactor (HPCI)l VesseWater LevelSystem Injection During tytNY DATS (51 Lan Nunnsen toi mtPOafDAfflH QTHER F ACILITIES INVOLVED ist MONTM OAY YEAA YtAR ' 8,0 'Ak

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w o.wn n., nansnim nanino 87-006-00 LICEN$tE CONTACT POR TMit LtR {121 NAME TELEPHONE NUM8tR R.B. Cowles, Lead Engineer - Technical ^"'^ coo' i

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I f I I I i 1 I I I I I i 1 l 111 1 1 I i l I 1 I I f SUPPLEMENTAL REPOAf EXPECTtD H43 MONTH DAY vfAA SV8 Mis $ ION YtB 114 vor. co puote IX9fC?t0 SUDM13SiON CA tti NO l l l Am n ACr <L a n 1m u . mm. ., n, , 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 scram, )

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. l RBC/ p'~ g SORC Mtg.87-157

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8711050089 071030

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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 SPECIAL REPORT 87-006-00 f

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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