05000267/LER-1982-028, Forwards LER 82-028/03L-0.Detailed Event Analysis Encl

Forwards LER 82-028/03L-0.Detailed Event Analysis Encl

ML20062H357
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/06/1982
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20062H361	List: 05000267/LER-1982-028, Forwards LER 82-028/03L-0.Detailed Event Analysis Encl 05000267/LER-1982-028-03, /03L-0:on 820707,excessive Water Leakage Through PV-21244 Necessitated Isolation of Emergency Feedwater Supply Header.Caused by Water Cut in Valve Seat & Plug. Valve Ring Seat,Plug Assembly,Body & Seat Gaskets Replaced
References
P-82300, NUDOCS 8208160025
Download: ML20062H357 (5)

LER-1982-028, Forwards LER 82-028/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2671982028R00 - NRC Website

text

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r pubile service company of Ceacado 16805 Road 19 i t, Platteville, Colorado 80651-9298 August 6, 1982 Fort St. Vrain p

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- 823 Mr. John T. Collins, Regional Administrator l

Region IV

.J Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011

Reference:

Facility Operating License No. DPR-34 Docket No. 50-267

Dear Mr. Collins:

Enclosed please find a copy of Reportable Occurrence Report No. 50-267/82-028, Final, submitted per the requirements of Technical Specification AC 7.5.2(b)2.

Also, please find enclosed one copy of the Licensee Event Report for I

Reportable Occurrence Report No. 50-267/82-028.

Very truly yours, h Wwnb Don Warembourg t

Manager, Nuclear reduction DW/cls Enclosure cc:

Director, MIPC rY F208160025 820806 PDR ADOCK 05000267 S

PDR

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?IPCRTA3LE OCC"RFINE M S TFIB'l* ION Numbe r of Copie s Dep a r t men t o f E n e r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Le t te r)

San Francisco Operations Of fice Attn: California Patent Group 1333 3 roadway Oakland, Califo rnia 94612 De p a r t me n t o f E n e r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Letter)

Mr. Glen A. Newby, Chie f HTR Branch Division of Nuclear ?vver Developrent Suil S tation B-10 7 W as n in gt on, D.C.

205a5

epartment o f E n e r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Letter)

Attn: Project Man ager 110 West A St ree t, Saite '60 S an Die go, Califo rnia 72101 "r.

John T. Collins, Re gion al Adminis t rato r --- ---- ---- ------ -

Original of P Letter)

Regien IV Nuclear Regulatory Cocrission 611 Fyan Plaza Drive S ui t e 1000 Arlin gton, Texas 76011 Mr. Ge o r g e K uz y c z - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Letter)

Nuclear Re gulatory Core.t s s t an 7)20 Norf olk Avenue Se the s da, Ma rylan d 20034 Director------------------------------------

1 (P Le t te r)

Office of Manage ent Informatica and Progran Con trol huc le a r Re gula t o ry Cocnis s i on Wasnin gten D.C.

20555 Re c o r ds Ce n t e r - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Letter)

'as titute of Nuclear P ower Ope rations 1820 Water Place Atlanta, Ce a r gia X339 Mr. Richard Phelrs, FS V, CA, Site Rep re s en t ative. - - - - -- ---------

1 (P Letter)

Gene ral Atccic Campany le S64 Weld County Road 19 1/2 P lat te vi lle, Colorado S0651 1 (P Letter)

NRC Resident Site In s pe c to r

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REPORT DATE:

August 6, 1982 REPORTABLE OCCURRENCE 82-028 ISSUE O OCCURRENCE DATE:

July 7, 1982 Page 1 of 3 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651-9298 REPORT NO. 50-267/82-028/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

During power operation, the emertency feedwater supply header to the Loop 2 helium circulators was isolated. This constitutes a degraded mode allowed by LCO 4.2.2.a and is reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

EVENT

DESCRIPTION

On July 7, 1982, at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br />, with the reactor operating at approximately 70% power and 215 MWe, excessive leakage _through PV-21244 necessitated isolation of the emergency feedwater to the Loop 2 helium circulator water turbine drives.

Fort St.

Vrain Technical Specification LCO 4.2.2.a specifies that a supply of emergency feedwater be available to drive the circulator water turbine drives, allowing however, for isolation of the emergency feedwater supply for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> without the helium circulators being considered inoperable.

The valve, PV-21244, was repaired and calibrated, and the emergency feedwater supply header was restored to normal operation at 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br /> on July 7, 1982, within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period allowed by LCO 4.2.2.a.

If necessary, the affected helium circulators 'could have been operated on the water turbine drive at reduced speed, utilizing the water supply from the emergency condensate or firewater systems.

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CAUSE

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DESCRIPTION

l The internal leakage was found to have been caused by a water cut into the valve seat and plug attributed to normal wear.

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- f REPORTABLE OCCURRENCE 82-028 ISSUE 0 Page 2 of 3 CORRECTIVE ACTION:

The valve ring seat, valve plug assembly, body and seat gaskets were replaced, and the. valve stem was renewed.

The valve was then calibrated, and the emergency feedwater supply header restored to normal operation.

No further corrective action is anticioated or required.'

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i REPORTABLE OCCURRENCE 82-028 ISSUE 0 Page 3 of 2 Prepared By:

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Robert A. Dickerson Technical Services Technician Reviewed By:

[Idc[A JL[Is Charles Fuller

- Technical Services Engineering Supervisor l

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Reviewed By:

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l Edwin @:7 iti 1P '

Station Manager YL vM Approved By:

e Don Warembourg

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Manager, Nuclear Production l

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