05000277/LER-1980-029, Forwards LER 80-029/01T-0

Forwards LER 80-029/01T-0

ML20002B124
Person / Time
Site:	Peach Bottom
Issue date:	11/26/1980
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20002B125	List: 05000277/LER-1980-029, Forwards LER 80-029/01T-0 05000277/LER-1980-029-01, /01T-0:on 801113,reactor Core Isolation Cooling Sys Declared Inoperable.Caused by Turbine Trip Valve Switch Being Out of Adjustment.Switch Readjusted & Tested
References
801121, NUDOCS 8012090464
Download: ML20002B124 (2)

LER-1980-029, Forwards LER 80-029/01T-0

Event date:
Report date:
2771980029R00 - NRC Website

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[) P.O. BOX 8699 n w:. co- ,3;;.; PHILADELPHI A. PA.19101 [' Of. saisi e4i 4ooo c ~ o ,y November 26, 1980 Mr. Boyce H. Grier, Director Region I Office of Inspection & Enforcement US Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

Dear Mr. Grier:

SUBJECT: Licensee Event Report Narrative Description The following occurrence was reported to Mr. Cowgill, Region I, Office of Inspection and Enforcement on November 13, 1980

Reference:

Docket No. 50-277 Report No.: IZR 2-80-29/1T Report'Date: November 26, 1980 Occurrence.Date: November 13, 1980 Facility: Peach Botton Atomic Power Station RD 1, Delta, Pennsylvania Technical Specification _ _ Reference: Technical Specification 3.5.D.1 states in part that "The RCIC Subsystem shall be operable whenever there is irradiated fuel in the reactor vessel...except as specified in 3.5.D.2..." Technical Specification 3.5.D.2 states in part that "From and after the date that the RCICs is made or found to'be inoperable for any reason, continued reactor operation is permissable only during the succeeding seven days provided that during such seven days the HPCI system is operable." Description of the Event: . With the unit operating at full power, the Unit 2 RCIC system was declared inoperable due to an apparent inability to trip the turbine.. Investigation of the problem revealad that turbine trip and. valve operation was proper but that no annunciator or valve closed b IO12000Y/ek

O y Paga 2 condition was' received in the control room. This was caused by the closed limit switch'on.the turbine trip valve being out of adjustment. During-the period of investigation the RCIC turbine could not have initiated automatically but could have been manually operated, if necessary. Probable' Consecuences of the Occurrence: During the period of investigation, RCIC could have been s operated manually if necessary; however, automatic initiation was not operable. All other ECCS systems were operable and required surveillance testing was completed.

Cause of the Event

Misadjustment of valve limit switch.

Corrective Action

Following readjustment of the trip valv: Ifmit switch the turbine was tested and satiefactory operation of the trip indication was obtained. Very truly yours, 4 i i /b M.J.f l h (0 W / Coo y

- Supeirintendent pration~ Division - Nuclear Attachment cc: Director, NRC Office of Inspection & Enforcement Mr. Norman M. Haller, NRC - Office of Management & Program Analysis

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