ML20148P415: Difference between revisions

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| number = ML20148P415
| number = ML20148P415
| issue date = 11/20/1978
| issue date = 11/20/1978
| title = LER#78-063/03L-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
| title = /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
| author name = Baxley S
| author name = Baxley S
| author affiliation = GEORGIA POWER CO.
| author affiliation = GEORGIA POWER CO.

Latest revision as of 19:54, 7 August 2022

/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 Southern Nuclear icon.png
Issue date: 11/20/1978
From: Baxley S
GEORGIA POWER CO.
To:
Shared Package
ML20148P410 List:
References
LER-78-063-03L-01, LER-78-63-3L-1, NUDOCS 7811280220
Download: ML20148P415 (2)


Text

MQt.NSLQ (EVENY REPORT coninot utock:

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LLj@ o p t.E Act nuNr oH lYPE ALL HfoUthrD INr oHMAllOM 9Il[h]ij Al fj Il Hl Pj@1*> 0 l 0 l 0 l 0 l 0 l 0_[_0 (_Lit.L')f.: Ll 1100 t; 9 L IL L tr.L L (ty.)l 14 L I C t f C,t: te u'.' 4 H PJ 26, 0 lJJ Oj._0j@l 4 l 1jlj_

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0'> bl L,'rA L T l.ti'J a! H id fe J IVLN1 DAll #4 l hEFO41 OAl E LJ cvt ot semPTiod AND s'HOULL.E CONSEQUEr:CLS h 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 BD + #

SYSif fA CAU3E CAUSE . C O'.t P. VALVE COLE CODE SUCCODE COMPONE NT CODE SUDCODC SUL1 CODE diel 1717 l@ L A_J@ l A l@ L71 71 71 71 71 Il@ tz.JO L2J @

6 9 1U 81 12 13 Irl 19 20

_,, SEOUC NTI AL O'; Curt RE NCE ntrORT AEVISION gg E VENT YE AR HCPOHT NO. CODE TYPE NO.

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.S)J 31 33 36 3/ 43 41 42_ 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 ST S *2 POV.fR. OTH C F151 A100 iC ' Y OtSCOVf kY DESChlPTif1N

@ l UlO 10 l 0 l0jg[ NA l Q@l Plant Personr.el ebservation l A Hvit y CCNitNT HH l' A08 D Orf:ltr MF. A*AOUNT OF AC11VIT V L OCATION OF riCLEASC  !

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l 482j a 7811280 m - -

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

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