05000278/LER-1980-028, Forwards LER 80-028/01T-0

Forwards LER 80-028/01T-0

ML19340D582
Person / Time
Site:	Peach Bottom
Issue date:	12/17/1980
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19340D583	List: 05000278/LER-1980-028, Forwards LER 80-028/01T-0 05000278/LER-1980-028-01, /01T-0:on 801203,HPCI Steam Supply Valve, MO-3-23-14,failed to Fully Close.Caused by HPCI Sys Being Inoperable for Valve Insp.Valve Reassembled & Tested
References
NUDOCS 8012310320
Download: ML19340D582 (2)

LER-1980-028, Forwards LER 80-028/01T-0

Event date:
Report date:
2781980028R00 - NRC Website

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PHILADELPHIA ELECTRIC COMPANY i

2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101

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December 17, 1980 Mr. Boyce H. Grier, Director Office of Insp?ction and Enforcement Region I US Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

SUBJECT:

LICENSEE EVENT REPORT NARRATIVE DESCRIPTION s

Dear Mr. Grier:

The following occurrence was reported to Mr. Cowgill, Region I, Office of Inspection and Enforcement on December 4, 1980.

Reference:

Docket No. 50-278 Report No.:

. 8 0- 28 /1 T Report Date:

uecember 17, 1980 Occurrence Date:

December 3, 1980 Facility:

Peach Bottom Atomic Power Station RD #1, Delta, PA 17314 Technical Specification Reference:

Technical Specification 3.5.C.1 states that "tha HPCT subsystem shall be operable whenever there is irradiated fuel in the reactor vessel, reactor pressure is greater than 105 psig, and prior to reactor star *.up frcm a Cold Co ndit ion, except as specified in 3 5.C.2 and F.5.C.3 below."

Description of the Event:

03 3

During testing on December 1, 1980, the HPCI steam supply valve MO-3-23-14 did not fully close as described in LER 3 /

i 27/17.

Later attempts to stroke the valve were successful.

On December 3, 1980, after satisfactory testing of remaining ECCS systems and the RCIC system, the HPCI system was taken out of service and declared Anoperable to work on the valve.

The valve

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operator and valve were disassembled, inspected, and reassembled by December 5, 1980.

No conditions were found which could have 1< '

caused the valve to operate improperly.

Due to minor scratches, i '

the valve stem and stem packing were replaced.

The valve was satisfactorily tested and the HPCI system returned to service on December 6, 1980.

Probable Consequences of the Occurrence:

During the period HPCI was inoperable, all ECCS systems and the RCIC system were either known to be op(*able or were tested to verify operability.

Additionally, operation of this valve is not required for containment isolation.

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Cause of the Event

I This event was caused by the HPCI system being inoperable for i

j the valve inspection.

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Corrective Action

After the valve failed to fully close during testing, it was j

disassembled, inspected, reassembled, and successfully tested as described above.

Very truly yours.

D

[

M. J. Cooney Superintendent Generation Division - Nuclear Attachment ec: Director, NRC - Office of Inspection and En fore c= en t Mr. tJorman M. Haller, NRC - Office of Management &

Program Analysis 0

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