05000296/LER-1981-029-01, /01T-0:on 810616,fire Protection Preaction Sprinkler Sys for Reactor Bldg Elevations 565,593 & 621 Were Found Isolated.Caused by Personnel Error.Valve Opened. Personnel Familiarized W/Isolation Valve Operation

/01T-0:on 810616,fire Protection Preaction Sprinkler Sys for Reactor Bldg Elevations 565,593 & 621 Were Found Isolated.Caused by Personnel Error.Valve Opened. Personnel Familiarized W/Isolation Valve Operation

ML20005B058
Person / Time
Site:	Browns Ferry
Issue date:	06/29/1981
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20005B054	List: 05000296/LER-1981-029, Forwards LER 81-029/01T-0 05000296/LER-1981-029-01, /01T-0:on 810616,fire Protection Preaction Sprinkler Sys for Reactor Bldg Elevations 565,593 & 621 Were Found Isolated.Caused by Personnel Error.Valve Opened. Personnel Familiarized W/Isolation Valve Operation
References
LER-81-029-01T-01, LER-81-29-1T-1, NUDOCS 8107060267
Download: ML20005B058 (3)

LER-1981-029, /01T-0:on 810616,fire Protection Preaction Sprinkler Sys for Reactor Bldg Elevations 565,593 & 621 Were Found Isolated.Caused by Personnel Error.Valve Opened. Personnel Familiarized W/Isolation Valve Operation

Event date:
Report date:
2961981029R01 - NRC Website

text

.

U. S. N1JCLE AR E EZULATORY COMMISSION NRC F ORM 366

!.lCENSEE EVENT REPORT CONTROL BLOCK: l l

l l

l lJh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

lo lil l Al L l B l R l F l 3 lglIS0 l 0 l - l 0 l 0 l 0 l 0 j 0 l - l 0 l 0 lgl 4 l 1 l 1 l 1 l 1 lgl CAT 6 l

a u 9 EiCENSEE COOg 14 LICENSE NUMSEH 2%

24 LICENCE TYPE JO 67 101il R3 L _J@l I 5 1 0 1 0 1 0 1 2l9l6lg[0l6l1l6l8l1j@lnlA I

! 9loinlil@

CON' T 60 61 DOCKET NUMBER 68 69 EVENT O ATE 74 FS REPORT D ATE 83 sO 3

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES C10 g l During normal operation, the fire pr6tection preaction sprinkler systems for reactor building elevations 565, 593, and 621 were found isolated. (See T.S. 3.11.A.1.a) io,3 i ;

There was no danger to the health or safety of the public. There were no previous j,,,j i

similar events

There are no redundant systems.

io,3j i i

IO ls i l I

lo lil i I

10181I so C DE CODE SUSC E SUS O'E SU E

l A lB l@ @@ @ @ l V lh MPONENY l EE lX lg g g g g lL l O 9

)

H 9

to It 32 13 18 19 20 REOR(O'9l y l FlD 1l g

[._ ]

dN Y

EVENT YFnR

@ llLiniHO18l1l g

l 0l

=

_ 28 22 23 24 26 27 28 29 30 31 32 AKEN CT t O PL NT ME HOURS 22 58 IT FOR 8.

SUPPL R MAN F CTURER [JiJ@LsJ@

LZJ@

L2_J@

l0Io10101 1YJO LNj@ J@

l Ml 417l 5?@

33 34 34 36 37 40 41 42 43 64 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS b27

,,,o, l Lack of familiarity with the iso 11 tion valve operating characteristics caused The Mueller type AWA valve was opened and the l; m personnel to believe valve was open.

Personnel were familiarized with the isolation

,,,,, g systems were returned to nonnal.

,,,,,l valve characteristics. A precaution to verify the isolation valves are open will be added to plar.t instructions.

, 4 80 OECOVERY8ESCRIPTION I

DIS E @RV I

'4 POWER OTHER ST ATUS L

"5P' t "

I S*r'*

NA 1

I l

1.2.eJ L.EJ@ l 019 l 8 lgl

/

A fivt f y CO TENT LOCATION OF RELE ASE HE LE AstD UF RELE ALE AMOUNT OF ACTIVITY Li_L ] L.ZJ @ L2._J@l NA l

l NA l

80 el 9 10 11 44 45 PEH50NNtil FXPOEU51ES

. NUf.1HE M TYPE

DESCRIPTION

I i I 7 I I 01 01 Oj@LZj@l NA J

PERsONNE't iNiu'n%ES NUMREH

DESCRIPTION

li lu i lOl0l0l@l NA l

0 5 OF OR O TO FACIL8TY NA l

l8 191 U@L 80 t

n

• )

to E SCRIP TION

?!A l

l l l l I l l I l l l 1 l; I".0Ujf@l L

leloj 68 69 80.

i g g 10 O

8107060267 810629' PHONE-PDR ADOCK 05000296 S

POR s

Form BF 17 Ten'nessee Valley Authority BF 15.2

, Browns Ferry Nuclear Plant 6/04/81 LElt SUPPLEMENTAL INFORMATION BFilO-50-_ 296 / 81029 Technical Specification Involved 3.11.A.1.a 6/30/81 Mcported Under Technical Specification 6.7.2.a(2)

• Date due NRC:

3 Date of Occurrence _6/16/,81 Time of Occurrence 1730

_ Unit Identification and Description of Occurrence:

Thb fire'~hf6te~ctioh~preacticrrspMnkler systems for reactor building elevations 565, 593, and 621 were found isolated. This system had been taken out of service the previous day and a patrolling fire watch established per T.S. 3.11.A.3.

The hold order, under which this maintenance was performed was lifted. The valve was manually opened, subsequently, the system pressure was checked on the (continuedonattachment#2)

Conditions Prior to Occurrence:

I?iit i refueling olinge Unit 2 modification outage Unit 3 at 98%

Action specified in the Technical Specification Surveillance Requirements met iltuito inoperable eguipment.

Describe.

Established patrolling fire watch.

Apparent Cause of Occurrence:

Lack of familiarity with the isolation valve operating characteristics.

Analysis of Occurrence:

l There was no dinger to the health or safety of the public, no release of activity, no damage to the plant or equipment, and no resulting significant chain of events.

l l

f

Corrective Action

The valves were7pened, returning the systens to normal, and personnel were familiarized with the isolation valve operating characteristics. A precaution l

to verify the valves are open will be added to plant instructions.

I Failure Data:

Ifone ljetention:

Per' d - I.ifetime; Responsibility - Document Control Supervisor h

• Revision:

w---

,. ~.,

,m r

~

l I

ATTACHMENT 2 LER SUPPLEMENTAL INFORMATION BFR0-50-296/81029 Identification and Description of Occurrence (Continued) three elevations in the reactor building. He then notified the shift engineer that the system was in service and relieved the fire watch.

It appears that the valves were not opened (there is no position indication on the valves) and that the observed pressure was the result of the system nmin-taining pressure due to the isolated condition. The pressure on the isolated portion subsequently bled down over a period of time and was noted to be low by an NRC inspector. At 1100 on the day the system pressure was noted low, the isolation valves were rechecked and found to be not fully opened. The isolation valves were fully opened and system pressure reestablished.

t l