05000219/LER-1978-035-01, /01T-0 on 781227:torus Water Temp in Excess of Tech Specs.Caused by Failure of Operations Personnel to Recognize Torus Water Temp Nearing Tech Spec Limit

/01T-0 on 781227:torus Water Temp in Excess of Tech Specs.Caused by Failure of Operations Personnel to Recognize Torus Water Temp Nearing Tech Spec Limit

ML19289C404
Person / Time
Site:	Oyster Creek
Issue date:	01/05/1979
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19289C402	List: 05000219/LER-1978-035, Forwards LER 78-035/01T-0 05000219/LER-1978-035-01, /01T-0 on 781227:torus Water Temp in Excess of Tech Specs.Caused by Failure of Operations Personnel to Recognize Torus Water Temp Nearing Tech Spec Limit
References
LER-78-035-01T, LER-78-35-1T, NUDOCS 7901120139
Download: ML19289C404 (3)

LER-1978-035, /01T-0 on 781227:torus Water Temp in Excess of Tech Specs.Caused by Failure of Operations Personnel to Recognize Torus Water Temp Nearing Tech Spec Limit

Event date:
Report date:
2191978035R01 - NRC Website

text

.m LICENSEE EVENT REPORT CONTROL BLOCK: l l

l

}

}

I lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) i e

l N l J l 0 l C l P ) 1 l@l 010 l - l 0 ! 010 l 010 l-l 010 l@{ 4 l 1 11 11 l l ]@l l

l@

o li 4 9 LICENSEE COOE 14 15 u;ENSE NVVhE R 26 26 LICENSE TYPE JO 51 C AT 66 ON'T s[$"c[lLj@l01510l0l0l2lIl9}@l112l2l2I7l8l@l0I1 l.0l517lol@

C 1

8 F

61 COCKET NUMB ER 68 6fr EVE NT DATE 74 76 REPORT D ATE 80 EVENT DESCRVTION AND PROSABLE CONSEQUENCES h o

2 l During normal operation, the torus water temperature was found to be in l

ggi excess of the Tech Spec limits.

The average value for the four suppres-l sion pool thermocouolas at the time of the incident was 95.35'F.

The i

o 4

o6e l Tech Spec torus water limit is 95'F.

Safety significance of this event I

o is is considered minimal sincu 15'F. marcin exists between the Tech SOec.

I o17 I limit and the reactor scram recuirement of 110'F, l

l 0

8 l

60 8 9 SYSTEu

CAUSE

CAUSE Cov7 VALVE C00E CODE SUSCO E CovF0t,!NT C005

$UECOOE SUBOCDE oul I S l e l@ I A l@ I A l@ ly.J E 15 IS It It l@ Irl@ 121@

E 9

10 11 12 13 1E 16 20

'ECUENTi&L 00C J PENCE REFORT A E VIS80N L E E' ' A O EVENT YE A A RE*0AT NC.

COOE TYPE N O.

@,at;;g 17 18 I l-l 10 13 I 5 I id 10 11 I ITI l-J 10 1

_ 21 22 23 24 26 27 N

29 30 31 32 N

HOURS h S PO US.

sUPPLI MAN FA RER eM T K N A

ON ON PLANT ME l x l@l c l@

I z l@

I z l@

I0 l01010 I IV @

l vl@

12 l @

Iz 19 la 19 l@

S; 34 35 36 3

40 41 42 43 44 47 cAUSE OEsORIPTION AND CORRECTIVE ACTIONS i it l The cause of the occurrence is attributed to the failure 'f operations l

o 3 si j

personnel to recognize that the torus water temperature was nearinc the i

,7 l

T.S.

limit.

Tne water temperature was reduced by operating the contain-l 3 ;3 I

ment spray system.

Procedure changes will be made to insure that this I

system is operated as recuired to keep the temperature below the limit.

1 i 64 l

80 E 9 Si S

% POWER OTHER STATUS SO RY DISCOVERY DESORIP' TON NA l

lAl@l Operator observat ion l

i E j@ l01919 l@l i

s 88 A!Ti viTY CO0 TENT AVOUNT OF ACTivtTY LOCATION O* RELEASE RELE ASE@O 08 AELE ASFlZl@l lZj NA l

l NA l

1 is 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUY3EP TYPE

DESCRIPTION

I 1010101@izi@!_

m i

2 PERSCNNEL INJ). A ES Nuv5ER

DESCRIPTION

NA l

l0l0l0l@l 3

a 60 8 9 11 12 LOSS OF CR DAMAGE TO FAOILITY TveE DESCRt8 TION NA l

hl 1

9 e

e 9 i

~

,$$g g "@lOESC RirTION Veekly press release - January 9, 1979 l lltl1lll l t j i [f y

o

(!

112016 201-455-8764 e

Donald A. Ross 8"ONE.

,g NAVEOrpAEpApEp

Reportable Occurrence No. 50-219/78-35/IT-0 Page 2 January 5, 1979 Analysis of Occurrence The suppression pool water temperature limits were established to reduce the affects of the steam quenching vibration phenomenon which may occur at elevated suppression pool water temperature during a loss-of-coolant accident.

The requirement for reactor scram for suppression pool water temperature in excess of 110*F. was developed to prevent exceeding 160*F.

during relief valve operation.

The 95'F. limit for power operation is intended to provide a 10*F. allowance for testing which adds heat to the suppression pool and still provide a 5'F. margin below the scram requirement.

Since the suppression pool water temperature did not exceed the IIO*F.

limit during this incident, there appears to be minimal safety significance.

Additionally, the time the suppression pool temperature exceeded the 95'F.

limit was minimal.

Corrective Action

The torus water temperature was reduced to less than 95'F. by operation of the containment spray system.

The appropriate procedure changes will be made to insure that the containment spray system is operated as required to maintain torus water temperature to less than 90*F.

The PORC recognizes that there is an increasing frequency of administrative related problems and will formally address these problems in the near future.

Failure Data None.