ML19289D334

LER 78-066/99X-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

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: ML19289D330 ML19289D334 ML19289D335 ML19289D337
References
LER-78-066-99X, LER-78-66-99X, NUDOCS 7903050342
Download: ML19289D334 (1)

Text

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26 LICENSE T YPE J0 $1 CAT Sd CON'T PEPC 12 l9 17 (8 Ql0l7REPORT l2 l8DATEl7 l8 80l@

lol l 7 8 3 s l L }@l 0] 510 ] - l 0 l 3 \ 4161@l0 t,0 61 DOC A L T N U'.'D E R (x$ 03 14 DATE EVENT 74 75 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l During a transient on 4/29/78 while the unit was in the process of shutting down 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 o s 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.

of the public 1 incident levels 1 and 2. There was no danger to the health and safety 1o is 1 I Equipment actuated l l o l 7 ] l or unit personnel. No actual loss of coolant accident occurred.

1 (NP-30-78-01) o e I as designed to inject water into the RCS.

COYP. VALVE SYSTE*1 CAUSE CAUSE SUBCODE SUBCOOE SUSCODE COMPONENT CODE CODE CODE 1

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HOURS 22 YA N A TO O PLA T ET izlzlzlz!g lxlglJ4x ig g g g g l70 10 li 2 Y l S Bly lgl42N jg h M 3 40 41 l43zlg 44 47 JJ CAUSE DESCRIPTION AND CCRRECTIVE ACTIONS h Systen j i o l The cause of this high pressure iniection actuation was a low Reactor Coolant

[i li l l pressure trip resulting from the opening of feedwater valves. The enusa of the food-of the feedwater system while i

, 7 l water valves opening was due both to the sensitivity f rom flow control to level control of steam generator level ]

g,,3, l repetitively transferring l

, 4 l and improper operator response to the transient. 80 7 8 9 DISCOVERY DESCRIPTION oTHER STATUS 15 O RY S

• POWER l i 5 [Dj@ l0 l2 l0 l@l NA l [ Aj@l NA ACTIVITY CONTENT LOCATION OF RELE ASE RELEASED OF RELE ASE AMOUNT OF ACTivlTY l l l NA 60 7

1 6 8 9 LzJ O 'z l91 t1NA 44 45 PERSON .iUR E S NUY8ER TYPE DESCRIPTION l S

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' ,ERSONNE L iN;u'JiES Nuvet R DESCmPTiON@ l 80 li Ia l 101010 l@l 12NA 11 1 8 9 LOSS OF OH DAUAGE TO FACILITY TYPE D E SCRt P TION l SO i o 8 9 LZJ@lN^ 10 NRC USE ONLY 7

issue

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o @ 7003050 3VL l lllllllIl!II l2 l 2 l o f LN,jh] EScR.PnON NA 68 69 30 5 PHONE:_419-259-5000, Ext. 251 7 R 9 10 m 78-071 an Ba d a NAME OF PREPARER __