05000259/LER-1980-022-03, /03L-0:on 800212,during Scheduled Refueling Outage,Total Leak Rate of Primary Containment Penetrations Exceeded Tech Spec Limit.Caused by Wear of Valve Seating Surfaces.Valves Repaired & Retested

/03L-0:on 800212,during Scheduled Refueling Outage,Total Leak Rate of Primary Containment Penetrations Exceeded Tech Spec Limit.Caused by Wear of Valve Seating Surfaces.Valves Repaired & Retested

ML19305A939
Person / Time
Site:	Browns Ferry
Issue date:	03/12/1980
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19305A935	List: 05000259/LER-1980-022, Forwards LER 80-022/03L-0 05000259/LER-1980-022-03, /03L-0:on 800212,during Scheduled Refueling Outage,Total Leak Rate of Primary Containment Penetrations Exceeded Tech Spec Limit.Caused by Wear of Valve Seating Surfaces.Valves Repaired & Retested
References
LER-80-022-03L, LER-80-22-3L, NUDOCS 8003180598
Download: ML19305A939 (3)

LER-1980-022, /03L-0:on 800212,during Scheduled Refueling Outage,Total Leak Rate of Primary Containment Penetrations Exceeded Tech Spec Limit.Caused by Wear of Valve Seating Surfaces.Valves Repaired & Retested

Event date:
Report date:
2591980022R03 - NRC Website

text

~

nU 1

f,Rga u s. NUCLEAR CEpaLATOY COMMISSION LICENSEE EVENT REPORT CONTROLClOCK l l

l l

l l lh (PLE ASE PRjNT OR TYPE ALL REQUIRED INFORMATIONI t

6 d l A l L l B lR lF l1 l@l0 l0 l-l 0 l 0 l0 l 0 l 0 l - l 0 l 0 l@[ 4 l 1 l 1 l 1 l 1 l@l l

[g d 9 LiLENSEE COD (

14 lb L*CE NSE NUMBEH 25 26 LICENSE TYPE 40 67 L. A f be CON'T [n"g* ll h l0 l3 [0 l0 l0 l2 l5 l9 Ql 0 l 2 l 1 l 2 l 8 l 0 )@[ 0 l 3 l 1 l 2 l 8 l 0 l@

EVENT OESCD PTION AND *n0B A L NE ENCEs o 2 IWith unit in scheduled refueling outage, the total leak rage _gf primary contaiomeat_. _l i o 13 ; l penetrations exceeded the allowable of 655 SCFH during performance of Surveillange _

l 10141 l nstruction

4. 7. A. 2. g -3.

The total leakage was 6919 SCFH. There was no_

l I

I in[3, lsignificant resulting occurrence and no danger to the health or safety of the oublic.

I y l Redundance does..Ot apply. See Technical Specification 4e7.A.2.

Provi nsie 1

[TlTl lsimilar occurrences: LER BFRO-60-259/7903. -259/7723.

I I

ITTTli 8 s DE CO E SL8C f COMPONENT CODE SLSCOCE 5

E E

IS l@ L8J@ 18 l@ I V l^ I L lV l E lX lh [XJh [1] h 8

3 50 it 12 13 18 19 20 5t OVE N TI A L OCCUR R E NCE REPORT RE V'5 ION

(( n rit, EVENTVfAR REPORT No.

CODE TYPE NO

@ 0,,g; I810 I l -I 1 01 21 21 [gj l 01 a l lLI l--J LO_]

2R 29 Ju 31 ti

_We 22 23 24 26 TA ON PL A F Et*

HOLHz 58 1T 70R S

SUPPL 1 M AP. FA TiRER TAE A

LB_J@Lz_J@

Lz_l@

L1J@

101010 lo I l_xj@

tr_JO LLJ@

Iz 19 9I91C JJ J4 J3 36 37 40 el 42 43 M

el CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h vane nf tha 1

l i l e l l There was excessive leakage by valve seatinn surfaces e maed by haing e mn14=A l

y l valve seating surfaces. The valve numbers and naneolate clers nra g j as a supplement to this report. The valves were repaired and retested en I

g l demonstrate compliance. Further recurrence control is beine studied.

I i

4 I

I 80 F

il 1

• POWER QTHE R $f A TU$

0 $CO n DISCOb ERY OESCRIPTION NA l

[B_J@l Surveillance testing l

[ H j@ l0 l 0 l0 l@l

s ACivvtiv CO TENT RELEASE AMOUNT OF ACTtvlTV LOC AT80N oF RELE A$[

u_[sJ LZ J @D OF RFLE ASELZJ@l NA l

l NA l

t e 9 10_

tt 44 45 80 PERSONNEL I

• PfJ%bH[$

NUUrt R Tvpf DE sci 4IP TICN NA l

8 10 1 0101@lzl@l

,imso~,, 'L,~ 20.',is oEstniPr ON@

NuMni n "A

I U_LJ l I

I l@l 80 7

8 9 91 12 LO55 08 OR DAM AGE TO FACILITY TvPE DE SCHiP TION "A I

L'zj@l

' 9 8,

I.,

NRc Use oNiv

• 'L's"c.R.,rioN @

,mE NA l

lllllllllllll}

[N hl 2

'l 68 69 80.

7 8 9

'O N A*.9E OF PREP AR E R PHONE:

sco318oS3

Tennessee Valley Authority Form BF-17 Browns Ferry Nuclear Plant BF 15.2 1/10/79 LER SUPPLEMENTAL INFORMATION 80 22 4.7.A.2 BFilu-50 259__/

Technical Specification involved 6.7.2.B.4 Reported Under Technical Specification NA I

Date of Occurrence 2/12/80

" ie of Occurrence Unit Identification and Description of Occurrence:

The total leak rate of primary containment penetrations during SI 4.7. A.2. g-3 was 6919 SCFH. This exceeded the allowable 655 SCFH.

Conditions Prior ta Occurrence:

Unit 1 - scheduled refueling outage.

Unit 2 - hot shutdown.

Unit 3 - 1107 MWe steady state power Action s;>ccified in the Technical Specification surveillance Requirements met due to inoperable 3uipment. Describe.

NA - Unit'in scheduled refueling outage. Redundancy does not apply.

Aoparent Cause of Occurrence:

There was excessive leakage by valve seating surfaces which had deteriorated through normal operation of velves.

Analysis of Occurrcace:

There was no danger to health or safety of the public, no release of activity, no damage to plant or equipment, no resulting significant occurrence.

Corrective Action

Valves were repaired and retested to demonstrate compliance. A study of valve seating surf ace wear is being done to determine if further action is necessary.

l Failure Data:

Previous occurrences LER BFRO-50-259/7903, LER BFRO-50-259/7723

• Raten tion :

[eriod - Lifetime; Responsibility - Administrative Supervisor CN k'N /

• Revision :

\\/

4

... s BFRO-50-259/8022 f

64-29/30/32/33 VALVE 1-15, 37, 52 1 3-554, 572 f64-17/18/19 71-32/592 73-23/603 Atwood &

Atwood &

Rockwell Velan Walworth

MFCR Morrill Morrill Hancock Crane Chapman 2"

1688 2"._.._.._..20" I'

SIZE 26" 24" 18" G1 be Swing Check Butterfly Globe Stop GlobeStopCheck{

IYPE Check; Lift Swing Check iCheck I

e

{

I MODEL 20851 el I

lH0DEOF 4

OPERATION Air Oper.

Air Oper.

l l

I 1250 PSIG 1700 PSIG 125 PSIG 150 PSIG 300 PSIG i VENDOR

'150 PSIG 150 PSIG

@ 575 F l RATING

@ 2100F l

i l

I 1 NORMr.

1150 PSIG 1375 PSIG 1.5 PSIG 150 PSIG 150 PSIG i

l OPPRESS

@ 5620F

@ 3760F

@ 1200F

@ 3250F

@ 3250F y

=-

w--_--

t I-i.

I i

Path Leak Ratet

......__.3 g

3 LEAKAGE Isolation Valve i

d

. PATl!

I X-7A 1-15 i

664.3706 I

I i

l

• X-7C 1-37 1

67.3185 1

I

(

j X-7D 1-52 133.2914 l

l l

i

, X-9A 3-554 80.6004 l

l I

X-9B 3-572 77.6542 i

i i

84-19 i

X-25 1731.5374 l

64-17/18/19 t

l 84-20 3769.7989 l

X-231 64-29/30/32/33 X-212

!71-32/592 44.1818 I

t X-222 23/603 22.0889 l

i I

i h

9 f