05000324/LER-1981-076-01, /01T-0:on 810804,following Reactor Scram,Safety Relief Valve 2-B21-F013B,Model 67,failed to Manually Close After Being Manually Opened.Cause Unknown.Pilot Valve F013B Replaced

/01T-0:on 810804,following Reactor Scram,Safety Relief Valve 2-B21-F013B,Model 67,failed to Manually Close After Being Manually Opened.Cause Unknown.Pilot Valve F013B Replaced

ML20010C490
Person / Time
Site:	Brunswick
Issue date:	08/12/1981
From:	Pastva M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20010C487	List: 05000324/LER-1981-076, Forwards LER 81-076/01T-0 05000324/LER-1981-076-01, /01T-0:on 810804,following Reactor Scram,Safety Relief Valve 2-B21-F013B,Model 67,failed to Manually Close After Being Manually Opened.Cause Unknown.Pilot Valve F013B Replaced
References
LER-81-076-01T, LER-81-76-1T, NUDOCS 8108200132
Download: ML20010C490 (1)

LER-1981-076, /01T-0:on 810804,following Reactor Scram,Safety Relief Valve 2-B21-F013B,Model 67,failed to Manually Close After Being Manually Opened.Cause Unknown.Pilot Valve F013B Replaced

Event date:
Report date:
3241981076R01 - NRC Website

text

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7 U. S. NUCLEAR REGULATORY COMMISSION NRC F(RM 366 f7-77)

LICENSEE EVENT REPORT J

CONTROL BLOCK: l l

l l

l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

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7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 b 7 CA T $8 CON'T lolil 3{ny l L }@l 0] S j 0 l - l 0 l 3 l 2 l 4 @l 0 l 8 l 0 l 4 l 8 l 1 @l0l8l1l2l8l1l@

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60 61 DOCKET NUMBE R 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h I o l 2 l l Following a reactor scram with a Group 1 Isolation, infety-relief valve, 2-B21-F013B, l [o13l l model number 67, was manually opened at a reactor pressure of 1040 psi to reduce pres-l -

lo l4 l l sure. When pressure decreased to approximately 900 psi, an attempt to close the

]

l o l s l l valve proved unsuccessful and it remained open until it aut.omatically reset at 325 psi l lo is ] l reactor pressure. This event did not affect the health and safety of the public.

l l o 171 I I

lOlal l Technical Specifications 3.4.2, 6.9.1.81 l

80 7

8 9 SYSTEM

CAUSE

CAUSE COVP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE lOl91 l Cl Jl@ l El@ l B l@ lV l A lL lV [0 [P [@ l J[@ ]@

7 8

9 10 11 12 13 18 19 20 SEQUENTI AL OCCU R R E N CE REPORT REVISION

_ EVENT YE AR REPORT NO.

CODE TYPE N O.

b "LE R ROl8l1l

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_ 21 22 i3 24 26 27 N

29 30 31 32 T KEN ACT N ON PL T

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SUPPL IE MANUFACTURER l C l@l C l@

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40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h I i I o l l The F013B pilot valve was removed and sent to Wyle Laboratorv to determine the cause l 11 11l l of the valve failure to manually close or automatically reset.

The pilot valve was l

li[2] l replaced with one from stock and following an operational test of the valve it was l

lil3ll returned to service. The safety relief-valves' pilot valves are scheduled to be l

i 4 l replaced with others of a different design during the 1982 refueling outage.

l 7

8 9 80 ST i

% POWE R OTb:sR STATUS 1 CO RY DISCOVERY DESCRIPTION I1 I5llGlh l0l0l0l@l _

NA l

lAl@l Operational Event l

A TIVITY CONTENT HELEASED OF PE LE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE l1 l6 l W @ l Zl@l NA l

l NA l

7 8 9 10 11 44 45 80 PERSONNE L F xPOSUHES NUYB E R TYPE

DESCRIPTION

l 0 l 0 l 0 l@l Z l@l NA l

i 7 PE n SO~N A',wunS DESCniPTiON@

NuvnE n l0l0l0l@l NA l

i a 7

H 9 11 12 80 LOSS OF OR D AM AGE TO F ACILITY TYPE D E SC HIP T IO N lZl@l NA l

i o 7

8 9 10 80

@lDESCRIP TIONVarious local reports on radio, television and newsonnern llIlllllllIlllI 19SU l,2 l oj C108200132 68 6'

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