05000267/LER-1979-055-03, /03L-0:on 791026,during Surveillance Testing,Check Valve V-22370 Was Stuck Open,Making Fire Water Booster Pumps Inoperable for Helium Circulator Drive.Cause Unknown.Valve to Be Opened & Inspected

/03L-0:on 791026,during Surveillance Testing,Check Valve V-22370 Was Stuck Open,Making Fire Water Booster Pumps Inoperable for Helium Circulator Drive.Cause Unknown.Valve to Be Opened & Inspected

ML19210E341
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/26/1979
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19210E340	List: 05000267/LER-1979-055, Forwards LER 79-055/03L-0 05000267/LER-1979-055-03, /03L-0:on 791026,during Surveillance Testing,Check Valve V-22370 Was Stuck Open,Making Fire Water Booster Pumps Inoperable for Helium Circulator Drive.Cause Unknown.Valve to Be Opened & Inspected
References
LER-79-055-03L, LER-79-55-3L, NUDOCS 7912040363
Download: ML19210E341 (1)

LER-1979-055, /03L-0:on 791026,during Surveillance Testing,Check Valve V-22370 Was Stuck Open,Making Fire Water Booster Pumps Inoperable for Helium Circulator Drive.Cause Unknown.Valve to Be Opened & Inspected

Event date:
Report date:
2671979055R03 - NRC Website

text

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7 7H LICENSEE EVENT REPORT CONTROL BLOCK: l l

l l

l l

lh,

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

lCi0lFlSlVl1l@l0 0 l-l 0 l 0 l 0 l 0 l 0 l-l010 l@l 4l ll 1l2 l 0 @l l@

o 1

7 8 9 LICENSEE COOE 14 15 LICENSE NUM8ER 25 26 LICENSE TYPE Jo 57 GAT Sd CON'T Oi1 Z,"CE I b h 0l 5 l0 l0 l0 l2 6l7 @l110l2l61719 @l11112l617l9 @

?

8 60 61 DOCKET NUM8ER 68 63 EVENT DATE 74 75 REPORT DATE 80 EVENT OESCRIPTION AND PROBABLE CONSEQUENCES h During scheduled surveillance testing a check valve (V-22370) was found to be stuck I

o 2

o 3 jopen. This event made the fire water booster punps inoperable for helium circulator l 10 4

1 drive. The reactor had been operated at power since the last demonstrated operability l [of the booster pumps. LCO 4.2.19 requires that one booster pump be operable when the l o

3 ir eactor is at power. It must be assumed that the reactor was operated at power with-l Lo e

1 out an operable booster pump. There was no effect upon the health or safety of the j

lo 7

p ublic. Redundant systems were available. Reportable per Tech. Spec. AC 7.5.2(b)2.

l g

g 90 7

8 9 CE COOE SL8C E COMPONENT COOE SL8 OCE SL E

lClBl@

@l Blh l Vl Al Ll Vl El Xlh l Clh l A h O

9 7

8 9

10 t1 12 1J 18 19 20 SE QUENTI AL OCCUR AENCE REPCRT REVISION

,_ EVENT YE AR REPORT NO.

COOE TYPE N O.

h 'LER Ro l 7l 9l l-l l 01 Sl 5l l/l l 013 l L

l-l l Ol yu'NE a7

_ 21 22 23 24 26 27 28 29 30 31 32 iAK N AC 0 ON P NT MET MOURS S8 i FOR S.

SL PPLI E MANLFACTURER l X l@[]{_j@

( Z_J@

l,,Z_j@

l0 l0 0 lo l Y@

lN l@

lN l@

lW l0 l3 0l@

3J 34 3S 36 31 40 el 42 43 4A 47 CAUSE CESCRIPTION ANO CORRECTIVE ACTIONS ojIThe cause of the valve malfunction is not known at this time.

At the time of the I

i

!i i

event the valve was rapped sharply which f reed it for coeration.

The v,1ve I

lwill be opened and insoected and the results will be recorted as a sunolecent to this 2

3 l report. The valve is a Walworth 4 inch check valve, body model WO8 with a R13 disc.

I i

4 1

7 8 9 80 ST

% POWER OTHER STATUS 015 RY OISCOVERY OESCllPTION l G @ l0 l0 l0 l@] N/A l

l Bl@l Operator Observation l

i 5

ACTIVITY CO TENT aELEASED OF RELE ASE AMOUNT CF ACTIVITY LOCATION OF RELEASE

@ y @ l N/A l N/A 1

6 7

8 9 to 11 44 45 80 PERSONNEL EXPOSURES NUM8ER TYPE OESCRIPTION l0l0l0l@lZl@l N/A l

7

' ES PERSONNEL INJU I

NUMBER

DESCRIPTION

l0l0l0l@l N/A

,l i

a OSS OF OR O AGE O FACILITY 4

TYPE O ESCRt* T't ON l Zl l N/A l

1 9

7 6 )

10 go OE CRiPriON @

7912040 3/,3 NRC USE CNLY

.SSUE @l N/A l

fIIItiltifIil}

N o

AME OF PREPARER PHONE:

a

/