ML19319B770

RO NP-33-77-45:on 770806,auxiliary Feedwater Pump Turbine 1-2 Failed on Actuation.Caused by Const Personnel Bumping Valve MS107 Disconnect Switch Out of Position.Switch Repositioned.Personnel Instructed to Use Care When Passing

ML19319B770
Person / Time
Site:	Davis Besse
Issue date:	08/31/1977
From:	Chesko R, Lingenfelter J TOLEDO EDISON CO.
To:
Shared Package
ML19319B674	List: ML19319B673 ML19319B770
References
NUDOCS 8001270240
Download: ML19319B770 (2)

Text

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• TOLEDO EDISON COMPANY

) DAVIS-BESSE UNIT ONE UUCLEAR POWER STATION ,

SUPPLEMENTAL Il: FORMATION FOR LER NP-33-77-45 .

DATE OF EVENT: August 6, 1977 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF O'CCURRENCE: Auxiliary Feedwater Pump Turbine (AFPT) 1-2 did net start a Steam Feedwater Rupture Control System (SFRCS) actuation.

Conditions Prior to Occurrence: The plant was in Mode 3, with Power (MWT) = 0 and Load (MWE) = 0.

Description of Occurrence: On August 6, 1977 at 0329 hours0.00381 days <br />0.0914 hours <br />5.439815e-4 weeks <br />1.251845e-4 months <br />, while performing a section of IP 600.11, " Auxiliary Feedwater and Once Thru Steam Generator Control Systems", AFPT 1-2 did not start on an SFRCS loss of feedwater signal.

Both Steam Generators did isolate as required, but AFPT l-2 did not start, placing the Station in Action Statement of Technical Specification 3.7.1.2.

Investigation of the occurrence found that the disconnect switch for Valve MS107, AFPT 1-2 Main Steam Supply, had been bumped slightly out of tne " Remote"

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position. The disconnect switch was repositioned in the " Remote" position

[( returning AFPT 1-2 to operability at 0333 hours0.00385 days <br />0.0925 hours <br />5.505952e-4 weeks <br />1.267065e-4 months <br /> on August 6, 1977.

Designation of Apparent Cause of Occurrence: The disconnect switch for MS107 is on a panel in a narrow corridor. Ihis area is a high traffic area during construction, but will have limited traffic during normal operations. It is suspected that an unknown person bumped the discennect switch slightly out of the " Remote" position taking control of MS107 away.

Analysis of Occurrence: Since the Reactor had not reached initial criticality, and there was no decay heat in the Reactor core, there was no threat to the health and safety of the public or to Station staff.

Corrective Action: The disconnect switch was repositioned and personnel were instructed to use care while passing through close quarters in ene plant and to be observant of switch positions being in "Re=ote". A Facility Change Request FCR 77-234 has been issued to install a cover over these panels to prevent recurrence.

s Failure Data: No previous Auxiliary Feed Pump inoperabilities were caused by disconnect switches being repositioned. One previous inoperability of a Contain-s_ e

) ment Isolation Valve was partially caused by a disconnect switch being in " LOCAL",

NP-33-77-38.

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