05000366/LER-1979-041-01, /01T-0 on 790523:during Maint Outage,Review Indicated Solenoid on Reactor Sample Isolation Valve Did Not Have Complete Qualification Testing.Caused by Design Error. Solenoid Will Be Replaced

From kanterella
(Redirected from ML19259C265)
Jump to navigation Jump to search
/01T-0 on 790523:during Maint Outage,Review Indicated Solenoid on Reactor Sample Isolation Valve Did Not Have Complete Qualification Testing.Caused by Design Error. Solenoid Will Be Replaced
ML19259C265
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 05/30/1979
From: Thomas Greene
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19259C262 List:
References
LER-79-041-01T, LER-79-41-1T, NUDOCS 7906140509
Download: ML19259C265 (3)


LER-1979-041, /01T-0 on 790523:during Maint Outage,Review Indicated Solenoid on Reactor Sample Isolation Valve Did Not Have Complete Qualification Testing.Caused by Design Error. Solenoid Will Be Replaced
Event date:
Report date:
3661979041R01 - NRC Website

text

L 4L,tIdOLL E.V Lf4 8 litt'Ull 8 CONinOLINOcK: l l

l 1

I i 1h (PLEASE PRINT OR TYPE ALL REQUIRED INFOn&4AT10N)

B la l A l E l i l4 l ? l@l 0 l 0 l - l 0 l n l n I n 10 l-ln 10 !@h l1 l1 l1 l1 l@l l

l ss C.At tes @

  • 9

'LICLMLL CODE is 15 LACE %L NuumLH 2S M

LacL%L syn JJ B

l'*Z LL@l n l s 10 i n in 13 f c is Gi n I c 19 1 1 7 10 @ln I s i 3 i n 17 lo l@

S 60 64 Occx LT NuvutM tad (d

EVENT DATE d4 th SEPOf t T DATE b3 tvENT oE:Cn PricN ANo enoBABLE CCNSEQUENCEs B l Durina the Februarv - March r9aintanance cutaca Pech*al raviaw of ci,ec IE electric. I 2

Dl al ecuicment in the devwall in retoonse to IER 7o-01 indic='ad that tha colennid en I

BI reactor sarole isolation valve 2831-Fnlo did not hava a cemiata ta-ara' ora and I

BI radiation cualification test recort document to coalifv it to parforn undar an accid- !

D1 ent conditicn.

Thore was no sicnificant effect en ol ant e a ~'tv from this evant cinca i

]I this valve v:Ould have failed in the closed conditien and there is a radundant valva l

DI to assure that crimarv containrant isolation is cet.

(continuedi

- I as a

SYSTEM CAtrE

CAUSE

Cot?.

VALVE CODE COCE SU3 CODE COMPOhtyT CODE St." C::DE SUSCCDE D'

I c l n lO Ls_l@ Le_l@ I vl A l t i v f o l o !@ I F i@ ILl @

S 9

30 13 82 IJ 35 IJ

?J E OUEN TI AL OCCUR R E NCE Rf* ORT REVISION (gn po E VE NT YE A R REPOn T NO.

COOE T1PE n;O.,

-@,ngg I 71 Cl l-j l ni al 11 lf_.]

Ini1I I-I l-1 l n_l 2i 22 22 24 a

2r as 23

.s si 22 K f4 C

ON

.T U

Od HOURS

5 8 FOR1 S.

L M UA F ER Wgl A l@

lZl@

4a1@

l0]010101 W@

lNl@

lAl@

l A I J 1919 '@

r u

2-i o

se 4a ai A2 e

u 4,

cAust c sca PTioN ANDCORRECTIVE ACTIONS h B I At the tima of installation wa wara'co mi'ted to car +=in anvir e ant =1 fece rac ni ro-I DI ments: however, desien did not recuest thaso cualificatinne fm, t h.2 enmaaan* - = n u #-

I '

i gl ac ture r.

This IEEE recuirement calls for test recort data on radiation and tncarat-1 I

DI ure cualification be furnished.

Althouch it was found that 'ne oricinally installad!

I A

g L SCO model STXS320 A103U did meet the temoerature cualificaric s.

(continuedl I

=

ST US

  • PCWE R OTHERSTATU:

ct H

OCCOWHY DESCRIPTICP4 i

J L11@ In i n i n l@l n's I

in l@l "ess I.

',!nv,Tv CaTENT

- OuyrO,AcnvTY @ i tOCAntN Oc REuE @

l REu AsEO 0, E uf L11 @ 11@l

"'a I

l m

u

.a PERSONNEL EXPCOURES NUM8ER TYPE DESCDtPTION loIoloi@lzl@l N/A I

8 3 II I?

13 M

PERSONNE L IP4JuetiES NuvefR OE$CRIP TION 2279 276 i

1010 in l@l N/a i,

i,

=

I LOG 3 05 On O AVAct iO f ACILITV TWE LIOCnt8 tion l Zl@l N/A I

io

,i

=

Puetic;Tv Q

r. uto occaia tion U NHC LLE ONLY

!I WQ')I N/A l

l I I l I I I I I I I ! ! :2

- 'I m

a s no sa si w:

I Y b W "0-

'UI PII-V-

PilONE 3I2 % 7 77 I NAME OF PREPAnEn e

7906140507 =

s

Georgia Power Ccmpany Plant E. I. Hatch Baxley, Georgia 31513 i

t Event Description and Probable ConsequencesThis is a non-repetitive occurrence.

Cause Description and Corrective Actions~

no radiation qualifications could be furnished. Although the installed sole-noid doesn't meet radiation qualifications, this is of no consequence since it would function for a reasonably safe period until a ne'.t solenoid can

-[

be installed at the first cold shutdcun outage upon recefpt of the new sole-noid.

2279 277 f

it:

i i

1, f

(

4

.i,

?

NARRATIVE

FOR LER 79-041-01-T-0 l

t On May 23, 1979, during the hanger maintenance outage a Bechtel Power i

Corporation review of Class IE electrical equipment in the drywell in res-ponse to IE Bulletin 79-01 indicated that the solenoid on reactor sample isolation valve 2B31-F019 did not have a complete temperature and radia-tion qualification test report document to qualify it to perform under an accident condition.

There was no significant effect on plant safety from this event since this valve would have failed in the closed condition and there is a redundant valve to assure that primary containment isolation is met.

l i

At the time of installation of the solenoid valve, we were committed to certain environmental IEEE requirements; however, design did not request these qualifications from ASCO.

This IEEE requirecent calls for test rep-ort data on radiation and temperature qualification be furnished. Although it was found that the originally installed ASCO model 3TX8320A103 U sole-noid did meet the temperature qualifications, no radiation qualificaticns could be furnished.

l Although the installed solenoid doesn't meet radiation qualifications, this is en no consequence to plant safety since it would functicn for a reasonably safe period until a new solenoid can be installed.

A new ASCO model N8320A185E has been ordered and will be installed at the first cold shutdown outage upon receipt of the new solenoid.

.2279 278 l

l Y

g