05000346/LER-1980-083-03, /03L-0:on 801116,feedwater Swing Caused Steam Generator 1-1 Level to Exceed Tech Spec Limits.Caused by Bad Relay in Integrated Control Sys.Relay 86/MBV-B Replaced. Relay 33X Changed on 801206

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/03L-0:on 801116,feedwater Swing Caused Steam Generator 1-1 Level to Exceed Tech Spec Limits.Caused by Bad Relay in Integrated Control Sys.Relay 86/MBV-B Replaced. Relay 33X Changed on 801206
ML19345E021
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 12/15/1980
From: Whitesell B
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19345E020 List:
References
LER-80-083-03L, LER-80-83-3L, NUDOCS 8012220451
Download: ML19345E021 (2)
v • d • e


LER-1980-083, /03L-0:on 801116,feedwater Swing Caused Steam Generator 1-1 Level to Exceed Tech Spec Limits.Caused by Bad Relay in Integrated Control Sys.Relay 86/MBV-B Replaced. Relay 33X Changed on 801206
Event date:
Report date:
3461980083R03 - NRC Website
v • d • e

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f,1 COMET *,v.T E R EVENT Cf SCRIPTION AND PHOO ABLE CON 5ECUENCES h l o 121 l (NP-33-80-101) on NovenScr IL 1980, at 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br />, the Station experienced a feed-l swiny which caused the steam generator 1-1 level to exceed the 348 inches upperj l_ a t a ] l water latall ifm_it of Technical Specification 3.4.5.

The operator took manual control of feed-J There was no dangerj

!ij I water and restored the level to within linits within 15 minutes.

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FIT 1 l The cause was a bad relay in the Integrated controt System which nave a false indica g [g l tion that the No. 1 main feedvater block valve had closed. Integrated Control Systeag in feed flow to Stean Generator 1-1 uhich causedj

,,j [ responded by calling for an increase (1

Under Shintenance Work Order (>NO) IC-0562-80 relay 86/MBV-U was the overfeed.

[g l ji; jj replaced. Relay 33X was changed on December 6, 1980 l

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DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-107 1

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DATE OF EVENT: November 16, 1980 EACILITY: Davis-Besse Unit 1 Overfeeding of Steam Generator 1-1 caused by a loss of IDENTIFICATION OF OCCURRENCE:

main feed flow signal to the Integrated Control System (ICS) 4 The unit was in Mode 1, with Power (MRT) = 2051 and 1

Conditions Prior to Occurrence:

Load (Gross MWE) = 680.

4 i

On November 16, 1980 at 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> while operating at Description of Occurrence:

approximately 74 percent power the operators noted a rapid indicated decrease in f

increase in Steam Generator 1-1 feed flow to Steam Generator 1-1 with a concurrent j

level to greater than technical specification Section 3.4.5 limit of 348 inches.

l This section required that with one or more steam generators inoperabic due to'the water level being outside the limits, be in at least hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and The operators took manual control of

- in cold shutdown within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

feedwater and lowered level to within the technical specification limit within approxi-Steam Generator 1-1 level had increased to approximately 400 mately 3 5 minutes.

inches or the full range indicator (225 inches below upper tubesheet).

On November 16, 1980, at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br />, Designation of Apparent Cause of Occurrence:

Instrument and Control personnel determined that ICS relay 86/MBV-B was de-energized which gave a false indication to the ICS that the No.1 main feedwater block valve to the This caused the ICS to monitor a feed flow signal equivalent I

had closed.

startup feed flow. The ICS responded by calling for an increase in feed flow to This caused the overfceding of_ Steam Generator 1-1.

correct the apparent imbalance.

l Before a final determination of the ca'use could be made, relay 86/MBV-B re-energized and feed flow indication returned to normal.

There was no danger to the health and safety of the public Analysis of Occurrence:

Once the operator took manual control of feedwater flow,.

or to station personnel.

l Steam Generator 1-1 level was returned to within technical specification limits in l

The highest feedwater level observed was approximately 400' inches above 15 minutes.

the inner face of the lower tubesheet which was still approximately 225' inches from-

- the inner face of the upper tubesheet.

4

Corrective Action

Temporary corrective action was completed at 1303 hours0.0151 days <br />0.362 hours <br />0.00215 weeks <br />4.957915e-4 months <br /> the same l

day under Work Request IC-056-19-80 which consisted of placing a jumper across contact MVB-B of relay 33X to maintain relay 86/MBV-B energized. On November-22, 1980,. plant l

- conditions permitted a permanent correction under Maintenance Work Order IC-0562-80 l

l which repla'ced relay 86/MBV-B in the ICS.

Relay 33X was also changed on December 6,-

1980 under Maintenance Work Order.80-1035-28.

t Previous occurrences of steam generator levels going high were reported Failure Data:

in Licensee, Event Reports NP-33-77-30, NP-33-77-72 and NP-33-78-36'(78-033).

l LER #80-083 m

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