05000293/LER-1979-018-01, /01T-1: on 790519,recirculation Pump Started W/Delta Temp Between Loops Greater than 50 F & Reactor Coolant Temp Greater than 212 F.Caused by Failure to Follow Station Operating Procedures & Temp Monitors

/01T-1: on 790519,recirculation Pump Started W/Delta Temp Between Loops Greater than 50 F & Reactor Coolant Temp Greater than 212 F.Caused by Failure to Follow Station Operating Procedures & Temp Monitors

ML19259C067
Person / Time
Site:	Pilgrim
Issue date:	06/06/1979
From:	Mathis C BOSTON EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19259C066	List: 05000293/LER-1979-018, Forwards LER 79-018/01T-1 05000293/LER-1979-018-01, /01T-1: on 790519,recirculation Pump Started W/Delta Temp Between Loops Greater than 50 F & Reactor Coolant Temp Greater than 212 F.Caused by Failure to Follow Station Operating Procedures & Temp Monitors
References
LER-79-018-01T, LER-79-18-1T, NUDOCS 7906120305
Download: ML19259C067 (1)

LER-1979-018, /01T-1: on 790519,recirculation Pump Started W/Delta Temp Between Loops Greater than 50 F & Reactor Coolant Temp Greater than 212 F.Caused by Failure to Follow Station Operating Procedures & Temp Monitors

Event date:
Report date:
2931979018R01 - NRC Website

text

.

. ' ORT "llpdate Rep l ort - Previous Report Date05-23-79" CONTROL DLOCK: l l

l l

l lPt[ASE PRINT OR TYPE Att REQUIRED INFORMAilON) t e

o

• l M l A l P l P lS l I l@thl 0 l 0 l 0 l 0 l0 l0 l0 l0 l 0 l 0 l 0 l@l 4l 1l 1l 1l I Ql l

lg 1

8 9 LICENSEE CUtJE 84 LICENSE NUMUEll 24 2th LICENbt 1YPE JU bl L A T t,U ON'T

(($ lL j@] 0l 5 l O l - l 0 l 2 l 9 l 3 @l' 0 l 5 l 1 l 9 l 7 l 9 l@[0 l6 l 0l 6l 7 l 9 l@

00 61 DoCKE T NUMitEf t 64 b'J E%EN T DATE 74 75 ftEPoltT DATE 41 0 EVENT DESCR:PTION AND PHODADLE CONSEQUENCES h

,_{1] I On May 19. 1979, while shutdown for modifications to seismic restraints, recirculation l

Tl pump P-201A was started with delta temperature between loops greater than 50 degrees.

g 14 l l When the pump was started it was also observed that reactor coolant temperature was g

s [ greater than 212 degrees and primary containment integrity was not beit', ma'ntained.

y c l The recirculation pump was secured immediately, primary containment integrity was 9

l7l l established and reactor Cooled to less than 212 degrees.

j a l I

80 SYSTE M

CAUSE

CAUSE

' COMP.

VALVE COOL CODE SUCCoOE CoMPoNE NT CODE SU8 CODE SUDCoOC pJ l c I n l@ L^J@ l ^_J@ l PI ui M i r l x i x ig in je g g

'8 9

10 -

11 12 f3 18 19 20 SEOUCNTI AL OCCU R R E f 4CE REPORT REVISloN E E R /fiO EVENT YE AR flE PORT No.

CODE 1YPE No.

h gigR,T, l 7l 9l l-l l 0l 1l 8l l/l l0 l1 l W

l-l [1 j

_ 21 22 23 24 2G 21 28 2J 30 31 32 _

Nti AKEfJ 'A Tl t

. o J PL T At T HOURS SU t811E F f U B.

S P11 i MA LFA TU ER y g nl g Q g. W @

l 0l 0] 0l 0l gg l Nlg l N jg l B l 5 l 8 l 0lg 33 34 35 3G 31 40 41 42 43 44 47 CAUSE [JESCRIPTION AND CORRECTIVE ACllONS g

The cause for exceeding the delta temperature limitations was failure to follow station l

pl operating procedures and the violation of primary containment resulted from trending l

g g temperature monitors which were not responding to the changes in reactor coolant pl temperature increase.

Disciplinary action was taken aga' inst the personnel involved, y

gg and they were rescheduled for specific' training on Recire. Operation.

g 80 ST S

% PoWE R OTH E R ST AT E'S ISC fY El LcJ@ l 9I 01 Ol@l DISCOVERY DESCn PTION 4 I ^ 1@l OperatLnal Event l

N^

ACTIVITY CONTENT RELE ASEo or RELE ASE AMOUNT OF ACllVITY b (.JJ g l F.lhl LOCATION Of RELEASE NA l'

l NA l

8 9 10 t1 44 45 PERSONNEL EXPOSURES tlG NUMBER

@ l 0 l 0 l 0 lhl TYPE @l DESCRIPTION

'[

El NA l

PER$oNNE L INJulilES NUMHER

DESCRIPTION

8 1 01 0 LO_1 8 1 NA l

8 9 11 12 LOSS OF oft DAMAGE To FACILITY 00 I"""'"

N NA 7906120 3 c f 3l 8 9 to Punt ICITY 80 r

] ISSUtrQflDESCItIPTioN NHC USE ONLY NA

, l ' l l l l l l l l l l l l j,,:

e 9 10 68 69 uo ;.

NAME OF PHEPAf tEH Charles.I.

Mathis

- / - 9.