05000346/LER-1978-066-99, /99X-1:on 780429,during Operation at 20% Power, RCS Pressure Dropped to Approx 1620 Psig & Safety Features Actuation Sys Channels 1 & 3 Tripped on RCS Low Pressure, Initiating Incident Levels 1 & 2

/99X-1:on 780429,during Operation at 20% Power, RCS Pressure Dropped to Approx 1620 Psig & Safety Features Actuation Sys Channels 1 & 3 Tripped on RCS Low Pressure, Initiating Incident Levels 1 & 2

ML19289D334
Person / Time
Site:	Davis Besse
Issue date:	07/28/1978
From:	Batch S TOLEDO EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19289D331	List: 05000346/LER-1978-066-99, /99X-1:on 780429,during Operation at 20% Power, RCS Pressure Dropped to Approx 1620 Psig & Safety Features Actuation Sys Channels 1 & 3 Tripped on RCS Low Pressure, Initiating Incident Levels 1 & 2 05000346/LER-1978-083-03, /03L-1 on 780720:containment vessel-to-annulus Differential Pressure Exceeded Tech Spec Limit by 1 Inch. Purge of Containment Bldg Commenced.Caused by Inadequate Monitoring of Pressure Increase by Shift Check 05000346/LER-1978-107-03, /03L-1 on 781031:during Diesel Generator Monthly Test,Room Temp Rose to 110 F & Outside Air Damper Would Not Open.Caused by Damper Linkage Being Out of Adjustment & Bound in Guide ML19289D330
References
LER-78-066-99X, LER-78-66-99X, NUDOCS 7903050342
Download: ML19289D334 (1)

LER-1978-066, /99X-1:on 780429,during Operation at 20% Power, RCS Pressure Dropped to Approx 1620 Psig & Safety Features Actuation Sys Channels 1 & 3 Tripped on RCS Low Pressure, Initiating Incident Levels 1 & 2

Event date:
Report date:
3461978066R99 - NRC Website

text

U. S. NUCLE AR RE RC Fo"" 366 (7 7M LICENSEE EVENT REPORT CONT AOL BLOCK: l l

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8 l During a transient on 4/29/78 while the unit was in the process of shutting down o 2 System l

10131 I maintenance outage and was operating at 20% reactor power, Reactor Coolant j

I o la 1 L(RCS) pressure dropped to approximately 1620 psig and Safety Features Ac This initiated j

I (SFAS) Channels 1 and 3 tripped at 0553 hours0.0064 days <br />0.154 hours <br />9.143518e-4 weeks <br />2.104165e-4 months <br /> on RCS low pressure.

o s of the public 1

incident levels 1 and 2.

There was no danger to the health and safety 1o is 1 I No actual loss of coolant accident occurred.

Equipment actuated l

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1 (NP-30-78-01)

I as designed to inject water into the RCS.

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VALVE COMPONENT CODE SUBCODE SUBCOOE SYSTE*1

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40 41 CAUSE DESCRIPTION AND CCRRECTIVE ACTIONS h Systen j l The cause of this high pressure iniection actuation was a low Reactor Coolant i o [i li l l pressure trip resulting from the opening of feedwater valves. The enusa of the food-of the feedwater system while i

l water valves opening was due both to the sensitivity 7

f rom flow control to level control of steam generator level ]

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7 8 9 DISCOVERY DESCRIPTION l

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