05000259/LER-1980-025-03, /03L-0:on 800313,primary Containment Isolation Testing Revealed Failure of RHR Injection Valve 74-67 to Close Upon Isolation Signal.Caused by Limit Switch on FCV- 74-48 Not Making Good Contact.Contact Cleaned & Adjusted

From kanterella
(Redirected from ML19305D801)
Jump to navigation Jump to search
/03L-0:on 800313,primary Containment Isolation Testing Revealed Failure of RHR Injection Valve 74-67 to Close Upon Isolation Signal.Caused by Limit Switch on FCV- 74-48 Not Making Good Contact.Contact Cleaned & Adjusted
ML19305D801
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 04/11/1980
From:
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19305D787 List:
References
LER-80-025-03L, LER-80-25-3L, NUDOCS 8004150535
Download: ML19305D801 (2)


LER-1980-025, /03L-0:on 800313,primary Containment Isolation Testing Revealed Failure of RHR Injection Valve 74-67 to Close Upon Isolation Signal.Caused by Limit Switch on FCV- 74-48 Not Making Good Contact.Contact Cleaned & Adjusted
Event date:
Report date:
2591980025R03 - NRC Website

text

i

'NRC FORM 366 U. S. NUCLEAR aEIULATOaY cOMMIS$10N am LICENSEE EVENT REPORT cONTRotstOcie1 l

l l

l l IQ iPLE4sE raiNr On TYee att aEOuiaEo iNPOaM4TiOm 1

6 l^ILIBlRlFl1lgl5 0l0l-l0l0l0]0l0l-l0l0lgl4l1l1l1l1lgl l

lg o i 3

LICENSEE CODE 14 1

LICENSE NUMUEH 25 26 LICENSE TYPE JO SFCAT58 7

8 CON'T loIil Sc'E l b @l 0; 5l 0l 0l 0l 2l 5l 9gl0 l3 l1 l3 l8 l0 @l0 l 4l Il ll 81 Ol@

60 El DOCKET NUMBER tuR 69 EVENT oATE 74 7b REPORT DATE No EVE NT OFSCHIPTION ANo PROB ABLE CONSEQUENCES h y o l, y [During refueling outage, while performing primary containment isolation testing, RHR injection valve 74-67 f ailed to close upon isolation signal. Isolation capability g

,3,3, g

Valves FCV-74-66 and FCV-74-68 were g

y n g, g s required by Technical Specification 3.7.D.l.

i l

operable. There was no danger to health or safety of the public. No previous y

yyj,j g

,o i3 i goccurrences.

10171 l l

l 101s 1 I 80 8 2

  1. ^" deco ' sEs*CooE CcvPoNENT CODE SL8C o'E SL

' oot C

g l S lD l@ y@ l Bl@ l Vl Al Ll Vl 0l P l@ y@ y @

1 8

9 10 Il 12 13 18 19 20 SEQUE N Ti AL OCCURRENCE REPORT REVISloN EVENT YEAR REPORT NO.

Coof TYPE No.

@,"LE R ROl 8l 0l l-l l 0l 2l 5l l/]

l0l3l l Ll g

[

uE's

,,,, 21 22 23 24 26 21 28 29 30 3i 32 Y KEr A

o oN PL T V T MO'J R 5 22 58

[}Jg [Njg [L jg l L l 2 lYlER0lg iTT PoR S.

$U L R MAN,C LB_jg[34X jg [5ZJg [Mg@

l 0l 0l 0l l

3J J

31 40 el 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h I i I o I lCause of the event was a limit switch on FCV-74-48 in the isolation logic not making l

i i i good contact. Contact was cleaned and adjusted and logic verified correct. Valve f

g, j, j ] limit switch setting procedure is being reviewed to determine if revisions are j

ii13l l necessary.

The component part involved was the Limitorque valve geared limit switch.l l

mI 80 1

a 2 SI 4.2. A-28ISCoVERY oESCRIPTloN ST 5

% POWE R OTHE R STA TUS ois O Y

NA l

l Cjgl l

y J g l0l0l0l@l Co'0 TENT AoouN10, ACTiv,Tv @ I LoCAfioN o, REu AsE @

ACTiviiv REuAsEo oP REu AsE

"^

"A L

l LLLJ LZJ @ L2J@l 8

9 1 10 11 44 45 80 PERSONNEL $xPOSURES NUMBER TYPE oESCRIPTioN Ii i 7I I 0l 01 Ol@l z l@l I

PERso~~EtiNJUJiEs oEsCRiPfio~@

~Ue8ER NA l

l 0 l 0 l 0 l@l i x 7

8 9 11 12 80 TV E DESC PT oN Lu.11 LZJ@l "A

I i

4 3 to Su 8 LN,j@l NA l

lllllllllllllf le,se J E D

DESCRIPTION

1 A 9 10 68 69 80 5 0

NAME OF PREPARER PHONE:

8004150 g 5

'e

'l enne";see V.illey Authart:V Foria Si

Brr+ nr, Ferry Nuclear Plant BF '~

1,l.-

LER SUPPLr. MENTAL INFORMAT!ON BFhu 50, 259 / 8025

, Technral Specification Involved 3.7.D.1

    • t pt-ted Und.:r Tc. hnii:.;l Specifiestion
6. 7. 2. b (2)

Date cf 0.currence _3/13/80,_ Tarae cf Occurrence _0330 Unit 1

&n
:lication sn.1 Desermtion cf Occurrance:

RHR injection valve 74-67 failed to close upon isolation signal.

Ct.mit' tons Pi! r in Oecurre:.. e.

Unit 1 @ 0% refueling outage.

(

Unit 2 @ 85%

g Dk Unit 3 @ 100%

Act; a spec fie#1.1 the Techni al Spectfit rition Surveillance Requirement;

..4.

dtg,,J,g,,innpt ral>l<' : j u,i[g;t etty_,, De se rat e._

Removed loop 2 RHR f rom S/D cooling mode and closed 1-FCV-74-67.

Aptnere nt Cr.use of Occi.rrence Cause of event was a limit switch on 1-FcV-74-48, which is in isolation logic circuit, not making good contact.

A n t'v.u s, : O curr m.*

There was no damage to plant equipment. There was no activit.y release, no personnel exposure or injury and no danger to, health or safety of the public.

Cot t.e tive Acti,n ;

The limit switch contact was cleaned and adjusted and logic circuit verified operable. Valve limit switch setting procedure is being ret.iewed to determine if revisions are necessary.

E*.YK"._ UM3-NA

  • P.* t en tion :

'e rin<t - 1.iret mic : P.esponsibility - Administrative Supervisi Qh

  • I4 evi :i9n :

4

. j...

s

,s