05000366/LER-1978-063-03, /03L-0 on 781102:reactor Maximum Cooldown Rate of 100 Degrees F Exceeded During Reactor Auto Scram & Vessel Depressurization.Caused by Personnel Error;Personnel Have Been Admonished

/03L-0 on 781102:reactor Maximum Cooldown Rate of 100 Degrees F Exceeded During Reactor Auto Scram & Vessel Depressurization.Caused by Personnel Error;Personnel Have Been Admonished

ML20148P415
Person / Time
Site:	Hatch
Issue date:	11/20/1978
From:	Baxley S GEORGIA POWER CO.
To:
Shared Package
ML20148P410	List: 05000366/LER-1978-063-03, /03L-0 on 781102:reactor Maximum Cooldown Rate of 100 Degrees F Exceeded During Reactor Auto Scram & Vessel Depressurization.Caused by Personnel Error;Personnel Have Been Admonished
References
LER-78-063-03L-01, LER-78-63-3L-1, NUDOCS 7811280220
Download: ML20148P415 (2)

LER-1978-063, /03L-0 on 781102:reactor Maximum Cooldown Rate of 100 Degrees F Exceeded During Reactor Auto Scram & Vessel Depressurization.Caused by Personnel Error;Personnel Have Been Admonished

Event date:
Report date:
3661978063R03 - NRC Website

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hEFO41 OAl E LJ ot semPTiod AND s'HOULL.E CONSEQUEr:CLS h cvt 70 j l Reactor maximum cooldoun ra te _ of 100 degrys F Per_ lLQUEJIU_.cyceeded on *,'cL_2.._.1928 ]

of,; [ Due to injection of condensate water into reactor vessel followinq a reactor scram I

gj l from rated pressure, reactor pressure decreased di,Lq_t?_mjn_timbjnn seals supplied I

o ;,,,, by nuclear steam to below condensate booster pump pressure and allowed condensate l

o g,, l water to be injected into reactor vessel through feeduater lines, resulting in a cool-1 o,; ; doen rate of 119 degrees F. in a one hour period.

Reactor r1SIV's were closed and j

gi injection of condensate water to vessel stopped, reactor coolant temocratures (con ' t )J B D

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SYSif fA CAU3E

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43 44 47 AUSE DESCRIPTloN AND COnHECTIVE ACTsoN3 h i l o'] [ During reactor auto scram and vcM dopycssuri7atiartj.Lerconnal allowed confersnto I

TlT) I water to be injected into Reactor vessel when pressure decrmsed bninw condebte 1

73 g j booster purp discharge pressure, thus causino rapid croldewn of Reactor coolant i

,j,j[ temperature.

Personnel have been cauticned about reactor nrossure decrexes bolo r I

g l a systen pressure, that could_ inject into vosnel durinq an enernencv condition (rnn'tjj e 9 e3

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Georgia Power Company s

Edwin 1. Hatch Power O caxies, ceorsie 31sia Reportable Occurrence f! umber:

50-366/1978-63 l

' Event Description Con't were back within limits in-15 minutes.

Evaluation of occurrence by reactor engineering confirmed that due to evaluatien of other temperatures indications for overall reactor coolant systems and by o');erving rccctor vessel metal temperatures (Delta T's) that no significant stress occurred'io reactor vessel or coolant systems.

There were no personnel injuries or overexposure or any release of radioactive materials to the environs as a result of this occurrence.

Cause Description Con't

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and to observe pressure decrease and level increase very closely in transient conditions to prevent exceeding reactor cooldcun rates.

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