05000346/LER-1977-019-01, /01T-0:on 771117,auxiliary Feedwater Valves AF 599 & AF 608 Found Closed,Rendering Steam & Feedwater Rupture Control Sys Pressure Switch Inputs Inoperable.Caused by Procedural Deficiency.Tests Revised

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/01T-0:on 771117,auxiliary Feedwater Valves AF 599 & AF 608 Found Closed,Rendering Steam & Feedwater Rupture Control Sys Pressure Switch Inputs Inoperable.Caused by Procedural Deficiency.Tests Revised
ML19329B847
Person / Time
Site: Davis Besse 
Issue date: 11/29/1977
From:
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19329B796 List:
References
LER-77-019-01T, LER-77-19-1T, NUDOCS 8002060857
Download: ML19329B847 (2)


LER-1977-019, /01T-0:on 771117,auxiliary Feedwater Valves AF 599 & AF 608 Found Closed,Rendering Steam & Feedwater Rupture Control Sys Pressure Switch Inputs Inoperable.Caused by Procedural Deficiency.Tests Revised
Event date:
Report date:
3461977019R01 - NRC Website

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11/17/77, pTT} l At 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br /> on l

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g l Control System (SFRCS) Stecc Generator to Feedwater Differential There j This placed the station in violation of Tech Spec 3.3.2.2.

ITTTlI inputs inoperable.

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Yam a diverse steam generator low level input lTJT] l SFRCS would have actuated

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CAUSE DESCRIPTION AND CORRECTIVE 10TIONS Feedwater Valves AF 599 and AF 608 were !

o 17, 1977, Auxiliary j,;OglAt 0935 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.557675e-4 months <br /> on Novem'er 2.2.

A orocedural l opened thus rem)ving the station from violation of Tech Soec 3.3.

li,,j ST 5031.14, which failed to reset the !

,,, g l defic.iency was found in the 3FRCS Monthly Test, 1977J ST 5031.14 was last performed on November 14

[, 3 g l valve logic for AF 599 and AF 608.

The test procedure has been revised.

I This is not a repetitive occurrence.

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DAVIS-3 ESSE UNIT ONE NUCLEAn POWER STATION SUPPLEMENTAL INFORMATION FOR LER NP-32-77-19_

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DATE OF EVENT: November 17, 1977 FACILITY: Davis-Besse Unit 1 Isolation of the Steam and Feedwater Rupture IDENTIFICATION OF OCCURREE g:

Control. System's Steam Generator to Feedwater Differential Pressure Switches.

The plant was in Mode 1, with Power (MWT) = 1129 Conditions Prior to Occurrence:

and Load (MWE) = 390.

At 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br /> on November 17, 1977, Auxiliary Feedwater This iso-Description of Occurrence:

Valves AF 599 and AF 608 t:te discovered closed by Opera This caused (SFRCS) Steam Generator te Feedwater Differential Pressure Switches.

il the pressure differencial witch inputs to the SFRCS to be inoperable, in v o a-i tion of Technical Specification 3.3.2.2 - Table 3.3.11, which placed the stat on under Technical Specificati:n Limiting Condition of Operation 3.0.3.

A procedural deficiency was uncovered s

Designation of Apoarent Cause of Occurrence _:

ST 5031.14. These sections in Sections 6.1 and 6.2 of :he SFRCS Monthly Test, failed to reset the valve logic for Auxiliary Feedwater Valves AF 599 and AF 608 after testing.

Section 6.2 of ST 5031.14, was last performed on November 14, 1977.

There was no danger to the health and safety of the public i

Analysis of Occurrence:

Had a feedwater line ruptured or a loss of feedwater or t5~~statfon personnel.

steam generator low level occurred, the SFRCS would hsve actuated from a redundant input.

17, 1977, Auxiliary Feedwater Valves This removed the station from Technical Specifica-

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At 0935 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.557675e-4 months <br /> on November

Corrective Action

2.2, AF 599 and AF 608 were opened.

tion 3.0.3 and fulfilled the requirements of Technical Specification 3.3.

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Table 3.3.11.

l Sections 6:1 and 6.2, has been revised.

SFRCS Monthly Test, ST 5031.14, l

This is not a repetitive occurrence.

l Failure Data:

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