05000346/LER-1978-028-03, /03L-0:on 780318,channel 1 Steam Generator 1-1 Declared Inoperable.Caused by Water in Level Transmitter SP09B8 Connecting Box Due to Steam Leak.Connection Box Cleaned & Dried.Waterproof Fitting Will Be Installed

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/03L-0:on 780318,channel 1 Steam Generator 1-1 Declared Inoperable.Caused by Water in Level Transmitter SP09B8 Connecting Box Due to Steam Leak.Connection Box Cleaned & Dried.Waterproof Fitting Will Be Installed
ML19326A346
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 04/13/1978
From: Kovach S
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19326A282 List:
References
LER-78-028-03L, LER-78-28-3L, NUDOCS 8002030163
Download: ML19326A346 (3)


LER-1978-028, /03L-0:on 780318,channel 1 Steam Generator 1-1 Declared Inoperable.Caused by Water in Level Transmitter SP09B8 Connecting Box Due to Steam Leak.Connection Box Cleaned & Dried.Waterproof Fitting Will Be Installed
Event date:
Report date:
3461978028R03 - NRC Website

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60 61 OQCK ET *.U*.t3 E R EVENT OESCRIPTION AND PROS A8LE CONSEQUENCES h lo 2; l At 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br /> on March 18, 1978, Steam and Feedwater Rupture Control System (SFRCS)

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Channel 1 Steam Ce *erator (SG) 1-1 level input was declared inoperable. This placed l lo ial l the unit in the Ac: ion Statement 13 of Technical Specification 3.3.2.2, which requireq g o,., ; ;

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all eight SG 1evel inputs to be operable while in Modes 1, 2 or 3.

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47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h A small steam 1

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TOLEDO EDISON COMPANY N

DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION j

SUPPLEMENTAL INFORMATION FOR LER NP-33-78-32 DATE OF EVENT: March 18, 1978 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE:

Steam and Feedwater Rupture Control System (SFRCS)

Channel 1, Steam Generator 1-1 level indication (Level Transmitter LT-SP0938) in-operable.

Conditions Prior to Occurrence: The unit was in Mode 1, with Power (MRT) = 2107,

, and Load (MWE) = 725.

4 Description of Occurrence: On March 18,1978 at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> during the performance of Surveillance Test ST 5099.01, " Miscellaneous Instru=ent Shif t Checks", an opera-tor noticed that level indication for SFRCS Channel 1 Steam Generator (SG) 1-1 level was reading higher than the other channels (but not at its maximum level).

At 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br />, Channel 1 SG l-1 level input was declared inoperable. This occur-rence placed the unit in Action Statement 13 of Technical Specification 3.3.2.2,.

which requires all eight SG 1evel inputs to be operable in Modes 1, 2 or 3.

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The Action Statement specifies that operation may proceed,until performance of the next required channel functional test, provided the inoperable section of the i

channel is placed in the tripped condition within one hour. Channel 1 SG l-1 level input was tripped at 1037 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.945785e-4 months <br />.

Because of high radiation levels inside Containment during power operation, reac-tor power was reduced at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on March 18,1978, from 76% to 25% of full power to allow personnel access to ineestigate and repair the problem.

Reactor power was returned to 75% of full power after LT-SP09B8 was declared operable at

.2220 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.4471e-4 months <br /> on March 18, 1978.

Designation of Apoarent Cause of Occurrence: Maintenance Work Order I&C 255-78 was issued to investigate the cause of this occurrence'.

Instrument and Control personnel found water in the connection box of level transmitter LT-SP0938, and also in the conduit leading to the transmitter. The transmitter and leads were

' cleaned and dried.

A small steam leak in the vicinity is ' believed to have been the source of the water in the conduit. The water traveled through the conduit to the transmitter.

LER #78-028 G

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TOLEDO EDISON COMPANY N

DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION PAGE 2 SUPPLEMENTAL INFORMATION FOR LER NP-33-78-32 Analysis of Occurrence: There was no danger to the health and safety of the public or unit personnel. During the period that Channel 1 SG 1evel-was in-operable, three remaining SFRCS Channels were operable. The inoperable channel was placed in the tripped (safe) condition. The steam generator level signal is not used to detect a steam line break inside the containment vessel.

Corrective Action

Af ter cleaning and drying the connection box for level trans-mitter LT-SP09B8, Surveillance Test ST 5030.14, "SFRCS Monthly Test" and ST 5099.01, " Miscellaneous Instrument Shif t Checks" were performed. LT-SP09B8 was declared operable at 2220 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.4471e-4 months <br /> on March 18, 1978. This re=oved the unit from Action Statement 13 of Technical Specification 3.3.2.2.

To prevent permeation of water into these transmitters, a waterproof fitting will be installed on each steam generator level transmitter which inputs to the SFRCS, per Facility Change Request 77-433. Installation of these fittings will ec=mence Failure Data: There have been no previously reportable occurrences of water leakage as the cause of transmitter inoperability.

LER #78-028 9

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