05000346/LER-1978-030-03, /03L-0:on 780322,containment Radiation Monitors Re 2004 & Re 2006 Declared Inoperable Numerous Times.Caused by Transformer T-1 Wires Close Proximity to Other Components, Inducing Circuit Board Q-16 Driver Transistor Oscillat

/03L-0:on 780322,containment Radiation Monitors Re 2004 & Re 2006 Declared Inoperable Numerous Times.Caused by Transformer T-1 Wires Close Proximity to Other Components, Inducing Circuit Board Q-16 Driver Transistor Oscillations

ML19326A342
Person / Time
Site:	Davis Besse
Issue date:	04/17/1978
From:	Kovach S TOLEDO EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19326A297	List: 05000346/LER-1978-030, Forwards LER 78-030/03L-0 05000346/LER-1978-030-03, /03L-0:on 780322,containment Radiation Monitors Re 2004 & Re 2006 Declared Inoperable Numerous Times.Caused by Transformer T-1 Wires Close Proximity to Other Components, Inducing Circuit Board Q-16 Driver Transistor Oscillat
References
LER-78-030-03L, LER-78-30-3L, NUDOCS 8002030159
Download: ML19326A342 (6)

LER-1978-030, /03L-0:on 780322,containment Radiation Monitors Re 2004 & Re 2006 Declared Inoperable Numerous Times.Caused by Transformer T-1 Wires Close Proximity to Other Components, Inducing Circuit Board Q-16 Driver Transistor Oscillations

Event date:
Report date:
3461978030R03 - NRC Website

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. LICENSEE EVENT REPORT

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74 75 REPORT oATE 60 63 63 EVENT DATg i

8 60 61 COCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l During 3/22/78 through 3/31/78, the Containment Radiation Monitor RE 2004 or RE 2006 l

Io I2; l o 131 l was declared inoperable numerous times. This placed the unit in Action l

Statement (A.S.) 9 of Tech Spec (T.S.) 3.3.2.1.

Also on 3/27/78, three SFAS Incident I i

I o 1.1 I and placedj l Level 1 Trips occurred which closed the Contain=ent Sa=ple Isolation Valve IoIsl l o 16 l l. the unit in the A. S. of T. S. 3.4.6.1, 3.3.3.6, and 3.6.4.1.

There was no danger to I

During the periods that either]

l o.l 71 l the health and safety of the public or unit personnel.

RE 2004 or RE 2006 were inoperable, three other SFAS Channels were operable. NP-33-78-p5 Io is i I so COMP.

VALVE SYSTEM

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33 34 25 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l i j o j l The cause of these occurrences was faulty instrumentation.

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Transformer T-1 wires were in l board and peak reading voltmeter have been reolaced.

I )ij close proximity to other. components, which induced escillation's to a driver transis-I

,,,, g for both RE 2004 and RE 2006. The detectors for.l g or on Auxiliary Circuit Board Q-16, r

,,,,,,RE 2004 and RE 2006 have been replaced.

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DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION SUPPLEMENTAL INFORMATION FOR LER NP-33-78-35 DATE OF EVENT: March 22 - 31, 1978 FACILITY: ' Davis-Besse Unit,1 IDENTIFICATION OF OCCURRENCE:

Containment Radiation Safety Features Actuation System (SFAS) Channels 1 and 3 Radiation Monitors, RE 2004 and RE 2006, were inoperable.

Conditions Prior to Occurrence: The unit was in Modes 1, 2 or 3 with Power (MWT) ranging from 2126 to 0 and Load (MWE) ranging from 723 to 0.

Description of Occurrence: The containment radiation monitor for SFAS Channels 1 or 3 was inoperable on the dates and times listed in the attached table.

The unit entered Technical Specification 3.3.2.1 (applicable in all modes for con-tainment rad'.ation monitors), Action 9 when either radiation monitor RE 2004 or RE 2006 was inoperable. This Action Statement requires that the inoperable func-h tional unit be placed in the tripped condition within one hour. The Action State-ment requirement was fulfill'ed for each occurrence.

Additionally, on March 27, the unit had three separate SFAS incident level 1 tr.ips which closed'the containment sample isolation valves. Technical Speci-fications 3.4.6.1, 3.3.3.6 and 3.6.4.1 were applicable because containment sample isslation valves were closed:

i

1) Technical Specification 3.4.6.1 requires operability of containment atmos-phere particulate and gaseous monitors in Modes 1,.2, 3 and 4.

The action i

Statement requires that the plant be in " Hot Standby"(Mode 3) within the next six hours.

2) Technical Specification 3.3.3.6 requires operability of containment vessel post-accident radiation instrumentation and containment vessel hydrogen instrumentation in Modes 1, 2, and 3.

The Action Statement requires that the inoperable' channel (s) be returned to operable status within 30 days or be in " Hot Shutdown" (Mode 4) within the next-12 hours.

3). Technical Specification 3.6.4.1 requires the cperability of two inde-pendent containment hydrogen analyzers in Modes 1 and 2.

The Action State =ent, which details action for one hydrogen analyzer being inopera-ble, was exceeded; the unit was placed in Li=iting Condition for Opera-f tion 3.0.3.

A LER #78-030

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( JDAVIS-BESSE UNIT ONE NUC*. EAR POWER STATION SUPPLEMENTAL INFORMATION FOR LER NP-33-78-35 PACE 2 e

Limiting Condition for Operation 3.0.3 specifies that if the Action Statement requirements cannot be satisfied, the unit shall be placed in Hot Standby (Mode 3) within one hour, and in Cold Shutdown (Mode 5) within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

The unit was removed from the Action Statements of these Technical Specifications as shown on the attached table by resetting the affected channels and opening the containment isolation sample valve,s.

On March 28, 1978 at 1635 hours0.0189 days <br />0.454 hours <br />0.0027 weeks <br />6.221175e-4 months <br />, SFAS Channel 3 was found to be not in the tri; ped condition.

The unit exceeded Action Statement 9 (a) of Technical Speci-fica.-ion 3.3.2.1 and entered Limiting Condition for Operation 3.0.3.

This occur-rence was reported in a separate Licensee Event Report, NP-33-78-39.

Designation of Accarent Cause of Occurrence:

The cause of each of these occur-rences vas faulty instrumentation. On March 28, 1978, Victoreen field service representatives found a leakage area on a low range amplifier board (Part Number 847-1-20) for RE 2004.

They also found.that the peak reading voltmeter on the auxiliary board (Part Nu=ber 847-1-25) for RE 2006 was de.fective.

\\I Both Victoteen and I&C personnel have determined the cause of the RE 2006 trip on March 26, 1978, and the RE 2004 trip on March 27, 1978.

Transformer T-1 wires were in close prcximity to other components, which induced oscillations to a driver transistor or auxiliary circuit board Q-16 (for both RE 2004 and RE 2006).

Analysis of Oca.urrence:

There was no danger to the health and safety of the public or to unit personnel. During the periods that either RE 2004 or RE 2006 was inoperable, three other SFAS Channels were operable. The SFAS Incident Level 1 trips occurred per system design. Three other SFAS containment radia-tion monitors were operable during the SFAS Level 1 Trips.

Corrective Action

On Ibrch 28, 1978, Victoreen replaced the low range amplifier board for RE 2004. The auxiliary board for RI 2006 on which the transformer was mounted, was also replaced on the same date.

Instrument and Control personnel properly reconnected the power supply ground return.which was i= properly connected and could have contributed to the failure.,

RE 2004 and RE 2006 were proven operable through perfor=ance of' Surveillance Test ST 5031.01, "SFAS Monthly Test" and were declared operable at the ti=es.and dates indicated on the attached r.able.

The unit was removed fror the-Action Statements of the Technical Specifications as shown on the table.

v LER #75-030

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!OLEDO EDISON COMPANY DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION PAGE 3

- SUPPLEMENTAL INFORMATION FOR LER NP-3_3-78-35 On October 24,1977 (Licensee Event Report NP-33-77-87), RIS 2004, Failure Data:

2005, 2006 and 2007 were reported to have had electrical isolatien problems be-tween grounds. On October 28,1977 (Licensee Event Report NP-33-77-86) RIS 2007 was inoperable due to a defective low amplifier board. On November 7,1977 (Licensee Event Report NP-33-77-89) RI 2007 was inoperable due to a defective low range amplifier board. An Incident 1 Level SFAS Trip was reported on the same date (Licensee Event Report NP-33-77-91) due to " spiking" on RI 2006 while RI 2007 was inoperable. On November 29, 1977 (Licensee Event Report NP-33-77-97)

RI 2006 was inoperable and the entire detector was replaced.

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