05000321/LER-1980-095-03, /03L-0:on 800808,w/reactor at Steady State of Power,During RHR Valve Operability Surveillance on RHR a Loop W/B Loop Out of Svc,Inboard Injection Valve 1E11-F015A Failed to Open.Caused by Burned Motor Windings & Rotor

/03L-0:on 800808,w/reactor at Steady State of Power,During RHR Valve Operability Surveillance on RHR a Loop W/B Loop Out of Svc,Inboard Injection Valve 1E11-F015A Failed to Open.Caused by Burned Motor Windings & Rotor

ML19344E668
Person / Time
Site:	Hatch
Issue date:	08/26/1980
From:	Nix R GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19344E667	List: 05000321/LER-1980-095, Forwards LER 80-095/03L-0 05000321/LER-1980-095-03, /03L-0:on 800808,w/reactor at Steady State of Power,During RHR Valve Operability Surveillance on RHR a Loop W/B Loop Out of Svc,Inboard Injection Valve 1E11-F015A Failed to Open.Caused by Burned Motor Windings & Rotor
References
LER-80-095-03L-01, LER-80-95-3L-1, NUDOCS 8009020444
Download: ML19344E668 (2)

LER-1980-095, /03L-0:on 800808,w/reactor at Steady State of Power,During RHR Valve Operability Surveillance on RHR a Loop W/B Loop Out of Svc,Inboard Injection Valve 1E11-F015A Failed to Open.Caused by Burned Motor Windings & Rotor

Event date:
Report date:
3211980095R03 - NRC Website

text

%U

UCENSEE EVENT REPORT -

~- (] CONTROL BLOCK:

l l

l l

l l

(PLEACE PRINT OR TYPE ALL REOtJIRED INFORMATION).

V, t;

6 l Gl - Al E l-I l H l 1 l@tbl 0 l 0 l - l' 0 l 0 l 0 l ~0 l 0 l - l 0 l 0 l@l 4 l 1 l 1 l 1 l 1 l@l l@

o i LICENSEE COOE I4 LICENSE NUMUEH 2b 26 LICENSE TYPE JD b7 CAI$8

~7.

8 9-CON'T.

$[ "C l Ll@l 0l 5 l 0l 0 l-0 l 3l 2 l 1 l@l 0 l 810 l 818 l 0 l@l 01 81 21 6l 8l Ol@

o 1 7

8-00 61 DOCKET NUMBER 68 G9 EVENT DATE 74 7b HEPORT DATE EO EVENT DESCRIPTION AND PROBADLE CONSEQUENCES h O 2 l While performing the RHR Valve Operability Surveillance on the "A" loop l

0 3 l of Rl!R, with the reactor at a steady state of power, the inboard injection l

o 4 l

valve, IE11-F015A, failed to open.

The surveillance was being performed I

o s I due to the "B"' loop of RHR being out of service for routine maintenance.

l IO in i I One loop of the RHR system is required to be operable per Tech Spec 3.5.B.3.

l 10 l 7 l l This was not a repetitive event.

Public health and safety were not affected l

l0mil by this incident.

I 7

8 9 SO

' $IE" S0eCODE C

C0DE COMPONENT CODE SUBC dE SU E

lC lF l@ [Ej@ 'l A l@ l V l A l L l V l 0 l P [@ {@ J @

O 9 7

8 9

10 II 12 13 18 19 20 SEQUENTIAL OCCUR RE NCE REPORT REVISION L E R /RO EVENT YEAR REPORT NO.

- CODE TYPE NO.

@y l810l

[_j [019l5l jf_j 1013 l l Ll l, _]

l 0_J R

_2n 22 23 24 26 27 28 M

30 31 32 KLF AC ON ON L T E t HOURS g

' SB IT 00 1 8.

S PPL1 MAN FACTURER LE_J@[Zj@

l 21@'

LZ_j@

l0l0l010l lYl@

[tLj@

lA]@

l L l 2 l 0 l 0 l@

JJ 34 3b 36 3#

40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTloNS h lil0 l l The "B" loop of RHR was immediately returned to service to meet the require-l-

11 til I ments of Tech Spec 3.5.B.2.

Upon investigation of the failure of the i

i 2 l 1E11-F015A valve, the motor windings and rotor were found to be severely l

i 3 l burned.

The motor was-replaced and the RHR Valve Operability Surveillance l

l' was performed and found satisfactory.

I i 4 7

8 9 80

$A S

'6 POWER OTHE R STATUS IS O R DISCOVEftY DESCRIPTION lE l@ l 0 l 9 l 6 l@l NA l

W @l Surveillance testing l

i s ACTIVITY CO TENT-RELEASE @D OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE B-]

. LZJ@l NA

' l; l

NA l

i a PEnSONNE t ExPOSu,'iES -

NUMBER TYPE

DESCRIPTION

l0 l0 l0 l@y@[

NA l

7

' PERSONNE't iN;UifiES NUMSER -

DESCRIPTION

l 0 l 0 l 0 l@l NA l

i a Pc 8 9

.11 12 80 L S OF OR DAMAG 10 FACILITY [Zj@l NA l

i 9

-.10 80 7.

H 9,

81,Njt @[DE ISSU RIPTION NA l

l l - l l l l l' l l l l l [ f

'BB09020VVK 68 59 80 5 NAME OF PHEPAREH PHONE: 912-367-7781

L I

11ARRATIVE REPORT i

Georgia Power Company Plant E.1. Hatch Baxley, Georgia Reportable Occurrence Report flo. 50-321/1980-095 i

On August 8, 1980, with the reactor at 96" power, the 1E11-F015A, RliR Inboard Injection Valve, failed to open while performing the RHR Valve Operability surveillance.

Personnel began complying with Tech Spec 3.5.B.3 as the "3" loop of P.HR was already out of service for routine maintenance. The "B" loop of RliR was placed back in scevice to comply with Technical Specifications 3.5.B.2.

Both the Core Spray System and the associated diesel generators were operable at the time of this incident.

There was no effect on safe plant operation.

Upon investigation of the failure of the 1E11-F015A valve, the notor windings and rotor were found to be severely burned.

The valve was manually operated to insure that there was no internal binding.

After the electrical circuits were checked, the motor was replaced and the required surveillance performed satisfactorily.

This was not a repetitive event and there were no effects to public health and safety, tio inherent problems were discovered during the generic review.