05000296/LER-1980-002-03, /03L-0:on 800117,while Performing Surveillance Instruction 4.5.B.1.d,residual Heat Removal Sys Flow Control Valve FCV.74-73 Tripped in mid-position.Caused by Valve Stem Lubricant Losing Lubricity,Causing Force on Motor

/03L-0:on 800117,while Performing Surveillance Instruction 4.5.B.1.d,residual Heat Removal Sys Flow Control Valve FCV.74-73 Tripped in mid-position.Caused by Valve Stem Lubricant Losing Lubricity,Causing Force on Motor

ML18024B342
Person / Time
Site:	Browns Ferry
Issue date:	02/08/1980
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18024B341	List: 05000296/LER-1980-002, Forwards LER 80-002/03L-0 05000296/LER-1980-002-03, /03L-0:on 800117,while Performing Surveillance Instruction 4.5.B.1.d,residual Heat Removal Sys Flow Control Valve FCV.74-73 Tripped in mid-position.Caused by Valve Stem Lubricant Losing Lubricity,Causing Force on Motor
References
LER-80-002-03L-01, LER-80-2-3L-1, NUDOCS 8002140557
Download: ML18024B342 (4)

LER-1980-002, /03L-0:on 800117,while Performing Surveillance Instruction 4.5.B.1.d,residual Heat Removal Sys Flow Control Valve FCV.74-73 Tripped in mid-position.Caused by Valve Stem Lubricant Losing Lubricity,Causing Force on Motor

Event date:
Report date:
2961980002R03 - NRC Website

text

'

1. DE/>8> 36G

~

Er LlCENSEE EVENT REPORT

~01 7

8 CON'T

~D E>Z:J CONTROL BLOCK:

I A

L B

R F

9 LICENSEE CODE 1

1 7

8 0

QB EVENT DATE I4 REPDRT ~LQ 0

5 0

0 0

2 9

6 Q7 0

GO 61 DOCKET NUMBER 68 69 FVENT DESCRIPTION ANO PROBABLE CONSFQUENCES QIO

[ Mille performing surveillance instruction 4.5.B.l.d on unit 3

0 QB REPORT DATE 80 it was discovered that Qi

{PLEASE PRINT OR TYPE ALLREQUIRED INFORMATION) 6 ZQ2000000000Q34ZZZZQE~QE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58

~03 Residual Heat Removal System flow control valve FCV-74-73 tripped in mid-position.

\\

Reference Technical Specification 3.5.B.7.

Redundant systems were operable.

There 83E~'"

and no previous similar events.

7 8

9 7

8 CE3 SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~EB Qii E 0

~E QE 37 A

0 32 0

B Q74

~AQ78 9

10 11 12 13 18 19 20 SEOUENTIAL OCCURRENCE REPORT REVISION LEA(RO EVENT YEAR REPORT NO.

CODE TYPE NO, Q17 1187887

~00

~

~00 Z

~~

~~

~Z p

21 22 23 24 26 27 28 29 30 31 ACTION FUTURE EFFECT SHUTDOWN ATI'ACHMENT NPRDQ PRIME COMP.

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FOAMSUB.

SUPPLIER MANUFACTURER QIB~XQIB

~Q20

~021 O

O O

O V

Q23

~VQ24

~LQ2s L

2 O

O Q26 33 34 35 36 37 40 41 42 43 44 47 CAUSE OESCRiPTION ANO CORRECTIVE ACTIONS Q27 p

Valve stem lubricant became hard and lost its lubricit causin excessive fo electric motor causin it to tri.

Valve stem was lubricated and i operated by hand.

This item is on a lubrication schedule and will be lubricated 3

annual ly to preclude recurrence.

Limitor ue, size 2

L e

SMB.

7 8

9 FACILITY STATUS

'4 POWEA OTHER STATUS Q

~i

~

~CQ28 ~QEE NA 8

9 10 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITYQs 6

~2'33 2 Q34 7

8 9

10 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~00 0

Q77 Z

Q38 'A 7

8 9

I I 12 13 PERSONNEL INJURIES NUMBER OESCAIPTIONQ4i

~oo o

Qr.

NA 9

11 12 LOSS OF OR DAMAGE TO FACILITYQ43 TYPE

DESCRIPTION

~ZQ42 NA 9

10 PUBLICITY ISSUED OESCAIPTION~

~NQ<<NA 9

10 METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32

~B Q3i surveillance test sl 4.5.B. l.d 45 48 LOCATIONOF AELEASEQ NA 45 80 80 80 80 7

8 n

8 NAME OF PREPARER PHONE:

GB 69 NRC USE ONLY 80 80 0L O

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',i'ennrsser, Valley Authority 13ro~vns Fr.> ry Nuclear Plant Form BF-17 BF 15.2 1/10/79 I.ER SUPPLEb1ENTAL INFORMATION I3FRO 296 /

8002 Technical Specification Involved Reported Under Technical Specification T.

S. 6.7.2 Date of Occurrence 1-17-80 Time-of 9ccurrence 1510 identification and Desc~ri tion of Occurrence:

FCV 74-73 tripped in mid-position (RHR System).

3.5.B. 7 Unit Conditions Pr ior to Occurrence:

SI 4.5.B. l.d (flow test on RHR) was being run on unit 3.

Unit 3 was shutdown.

Unit 1 was in a scheduled refueling outage.

Unit 2 was at 1075 MWe.

Action specified in the 'I'echnical Specification Surveillance Requirements met due to inooerable equipment.

Describe.

Ran RHR Loop I pump per 4.5.B.l.b; Ran 4.5.A. l.b and c, CSSC pump and MOV; Ran 4.9.A. l.a Supplement a for A, B, C, and D diesel generators.

Al)p'u'ent Cause of Occurrence:

Stem lubricant had become hard and lost its lubricity causing the electric motor to draw excessive current resulting in a motor trip. It was discovered during corrective action that the stem lock nut had loosened because it has not been staked.

An ~lysis of Occurrence:

No danger to health or safety of the public, no damage to plant or equipment, no significant resulting occurrence.

Lubricant was changed and limitorque operated by hand.

Locknut was adjusted and staked.

A program of staking the locknuts was implemented per MMI-88.

The item is on a lubrication schedule and will be lubricated annually to preclude recurrence.

F;)ilure Data:

NA

~R~:tention:

neriod - Lifetime; Responsibility

- Administrative Supervisor

~Revision:

E 0

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