05000302/LER-1979-012-03, /03L-0 on 790214:during Safeguards Test, RB-3GP-2 Light Did Not Illuminate.Caused by Burr on Relay Shaft.Relay Cleaned & Burr Removed

/03L-0 on 790214:during Safeguards Test, RB-3GP-2 Light Did Not Illuminate.Caused by Burr on Relay Shaft.Relay Cleaned & Burr Removed

ML19282B167
Person / Time
Site:	Crystal River
Issue date:	02/27/1979
From:	Stewart W FLORIDA POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19282B166	List: 05000302/LER-1979-012, Forwards LER 79-012/03L-0 05000302/LER-1979-012-03, /03L-0 on 790214:during Safeguards Test, RB-3GP-2 Light Did Not Illuminate.Caused by Burr on Relay Shaft.Relay Cleaned & Burr Removed
References
LER-79-012-03L, LER-79-12-3L, NUDOCS 7903090187
Download: ML19282B167 (2)

LER-1979-012, /03L-0 on 790214:during Safeguards Test, RB-3GP-2 Light Did Not Illuminate.Caused by Burr on Relay Shaft.Relay Cleaned & Burr Removed

Event date:
Report date:
3021979012R03 - NRC Website

text

_

~

d I

i NRC FORM 366 U. S. NUCLEAR REGULATORY COMvtS3 ION

+

(7.nl LICEP'SEE EVENT REPORT EXHIBIT A l

l CONTROL SLCCIC: l l

l l l l l (PLEASE PRINT OR TYPE ALL RECulAEO INFORMATICN) i e

lF l Ll q R\\ Pl 3 lgl 0 [ 0 l-l 01 0l 0 l Oj o j -l0 l 0 lgl 4 l 1; 1l1 l 1 lgl _wl _ ; g I

o i

i Uc s,..cco, i.

u ucasa m..

a a u u sa.. 2 w

CCN'T

,"goaj, gl 0l 5l0 l -l0 l 3[0 l 2 g 0; 2l1 l 4; 7;9 gl 0l2 l 2l7 l7 l 9 lg a

i 4

60 41 OccatT N6vgga 64 SvtNT QAfg Ja 75 ogpOm T G ATE 4J EVENT QESCRIPTICN AND PRC8A8LE CONSECUENCES h o6: 1 At 1000 while performine eneineered safecuards Monthlv Functional Test.

l gmi SP-130, RB-3GP-2 light did not illuminate. This created an event contrary ;,

o 4

1,- n %rsn4r,1 enon4f4r,r4nn 1 1 9 1 vnenena

,r*4r, e*,*n-one o

"n l'

g affect upon public health and safety as affected channel was placed in I

o 3

o e ; tripped condition. The two remaining channels were operable. Twelve previoust occurrences under this Technical Specification. Fourth occurrence for ES cabinet relays.

Sec's"

'le'd!

sveE5s cowesssT eaca su's c"c'e t sMEco

• '~

l S t Dj@ W@ l Xl@ [ Rl El L l Al Yl M @ J @ [,Zj @

o s

9 to in 12 13 18 19 23,,

SE cutNTI AL OcCumetNet st*ceT "3W5'04

, (VENTvtA4 4 E* CAT NO.

cCCE Tvet 40

@,a'Ee ao 17 19 I l--J 10 111 21 y

I 013 I lL l

[, -J W

L

,g;

_2, u

u u

u v

n a

u 2

u as Q

sf WET WCua$

$5 e

,Ce a S.

• • u E W.N 8. KEm L.x. j@Lxj@

I 7 f@

l.Zj@

l 0101 010 I ly_j@

l Ni @

'l Al @ ICl3l6iOl@

u

.s 2

2

.a en

.s o

u cAusE cEsemiericN ANo CoaREenvE Acricssh y l The cause of this event was found to be a burr on the relay shaft g

g g_(relay 63Z2E/L). The relav was cleaned and the burr removed.

Operability i restored after satisfactory completion of applicable section of SP-130.

A y

3 l special one-time test is scheduled prior to the next system test.

I I

t,,,i.,1.4_}

l 3 T

% agvgge afwga$TATUS 5.

EV 2'1COVERY OISC#'*T*34 LrJ@ l olo I a l@l u

I LaJ@l Tarkn4 4,e nh,

-,r4r-I u

u a

a,;,,,,,,

ega.,,,

.v2us, c..:mm @ l Loc.T.oso..ao.@

..a o, e...a o, NA l

NA l

(_Zj gl i

s

.,s'.i oJo ITI"il [ 0 l0 l 0 Q. @l=u:.. c,@ NA T

Zj l

so

....ess 'c.m'i.o ouca.nics@

s vei=

1010 101@l gg l

7 i:

a W. ' *" fA';',t'o? o u @

l,' l } [.,Z.}@l NA

[

=";*"'o'g s,.,

Naccu =

'"ggl i siiiiiii.1,,r o

A. Cooper, Jr.

(9 ') 785'-648 8 Nr.Ecm,.g,2,,,

- es' 7903090137 EE ATTACHED SUPPLEMENTARY INFO. fATION SHEET)

T

SUPPLEMENTARY INFORMATION Report No.:

50-302/79-012/03L-0 Facility:

Crystal River Unit #3 Report Date:

27 February 1979 Occurrence Date: 14 February 1979 Identification of Occurrence:

One inoperable engineered safety feature actuation system instrument channel contrary to Technical Specification 3.3.2.1.

Conditions Prior to Occurrence:

Mode 1 power operation (99%)

Description of Occurrence:

At 1000 while performing engineered safeguards Monthly Functional Test, SP-130, the Reactor Building channel three group 2 (RB-3-GP-2) indicating light did not illuminate.

Investigation revealed that relay 6322E/L was " hanging up".

Entered action statement 9.

Failure of this relay would have prevented channel 3 actuation of "D" Reactor Coolant Pump cooling water valves SWV-81 and SWV-85 in a 2 out of 3 coincidence network.

Designation ' Apparent Cause:

The esase of this event was found to be a burr on the relay shaf t (relay 63Z2E/L)

Analysis of Occurrence:

There was no hazard to plant or general public as the affected channel was placed in the tripped condition.

The two remaining channels were operable.

Corrective Action

The relay was cleaned, the burr removed.

Operability was restored after satisfactory completion of applicable section of SP-130.

That section of SP-130, affecting relay 63Z2E/L will be accomplished as a special one time test prior to the next scheduled system test.

This test is to assure component integrity and reliability as a result of corrective actions.

Failure Data:

12 previous occurrences reported under this Technical Specification.

Fourth. occurrence concerning ES cabinet relays.

/rc