05000346/LER-1978-065-03, /03L-0:on 780607,six Containment Isolation Check Valves Found Inoperable During Local Leak Rate Test.Caused by Improper Seating of Valves Due to Dirt or Wear.Discs & Seats Cleaned,Valves Lapped & Valves Retested

/03L-0:on 780607,six Containment Isolation Check Valves Found Inoperable During Local Leak Rate Test.Caused by Improper Seating of Valves Due to Dirt or Wear.Discs & Seats Cleaned,Valves Lapped & Valves Retested

ML19319C007
Person / Time
Site:	Davis Besse
Issue date:	07/05/1978
From:	David Brown, Cedoz R TOLEDO EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19319C006	List: 05000346/LER-1978-065, Forwards LER 78-065/03L-0 05000346/LER-1978-065-03, /03L-0:on 780607,six Containment Isolation Check Valves Found Inoperable During Local Leak Rate Test.Caused by Improper Seating of Valves Due to Dirt or Wear.Discs & Seats Cleaned,Valves Lapped & Valves Retested
References
LER-78-065-03L, LER-78-65-3L, NUDOCS 8001290732
Download: ML19319C007 (3)

LER-1978-065, /03L-0:on 780607,six Containment Isolation Check Valves Found Inoperable During Local Leak Rate Test.Caused by Improper Seating of Valves Due to Dirt or Wear.Discs & Seats Cleaned,Valves Lapped & Valves Retested

Event date:
Report date:
3461978065R03 - NRC Website

text

. - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

i7 77 %

(al LICENSEE EVENT REPORT (PLEASE P;' INT O IN L REQUIRED INFORMATION)

CONTROL SLOCK: l l

l l

lh i

e 3 l Si 1l@l 019 l l 3 i G l N l p l y ! _ l a l 3 l@l 4 il l1 11 ! 1 l@l l

l@

Of HI D lo 7

LICENSEE CODE 14

S LICENSE NuveER 25 26 L. CENSE TY PE 40 57 Ga r ta l L @l 0! S I d i - 10 l 3 l 416 @l 016 I 3 l 7 ! 718 @l017 l01517 I CCN'T lol1l 6d 69 EVENT OATE 74 75 REPCRT QATE 30 sC RC 60 61

OCKET NUMBER 2

4 EVENT CESCRIPT!CN AND PACBA8LE CONSECUENCES h isolation check valves were found inoperable ;

l o ! 21 l Fro 6/7/78 to 6/11/78, six containment Test.

The check valve

during the perfor=ance of the Contain=ent Local Leak Rate

g;3; go;,,,l leakage in each case was deter =f.ned to be in excess of the local leak race test re-There was no danger to the health and safety of the public or unit per-io,3; ; quire =ents.

isolation was maintained by existing redundant isolation valves I o is j i sonnel. Containment (NF-33-78-79)

[

} in series with the valves that were found inoperable.

go;7; l

10(4l l 30 7

3 3 COMP.

VALVE SYSTEM

CAUSE

CAUSE COCE CODE SUSCODE COMPONENT COOi SUSCOCE SUSCODE l o i s'1 i si Dl@ lE l@ 13 l@ l vi Al Li vt El xi@ l c jg l A j g 7

3 3

10 11 12 f3 18 19 23 R EVISICN SECUENTIAL CCCURRENCE REPCRT EVENT YEAR R EPORT No.

CCOE TYPE No.

l7 l3 l l -j l 0l 6l 5l l/]

l0l3l lL l

[{

l0l tg ef go hyREQERT

,_ 21 22 25 24

6 27 29 23 J0 31 J2 ON FUTURE EF8ECT SHUTCCWN ATTACHMENT N PR O-4 PRIME COMP.

CCVPCNENT AKEN ACTION CN PLANT YETHoD HoVRS 22 SUSMITTEo FCRM W9.

SUP* LIE R MANU AC RER 3 glJ4Zl@

l Z l@

jZ l@

l0 l0 l0 l J l Yl@

lY lg l43Al@ l vj l

l 5g 45 4

31 40 el 42 44 47 JJ CAUSE CESCRIPTION AND CCRRECTIVE ACTIONS failure.

Particles of cirt or wear j

l i j o j l The cause of these inocerabilities was ceroonent The discs and seats of three f

iiliJ land cit. ting crevented orcoer seatine of the valves.

The valves were success-l Iii21 Ivalves were cleaned of dirt and all the valves were lacoed.

]

lt l3) i fully retested oer the Local Leak Rate Test.

I li I A I I so 7

3 3 S

%PCWER QTkER STATUS 015 RY OtSCOVERY OESCRioT1CN NA l

l 3l@l Surveillance Test, ST 5061.0.

l li i 5 l I G lh l 0 ! 0 l 0 l(l ACilVITY CONTENT LCCATION oF "ELEASE RELEASED OpRELEASE AMCUNT CF ACTivtTY li 181 l Z l @ l

!@l NA l

I NA l

30 44 45 7

3 3 10 11 PER$oNNEL EXPCSURES NUYSER TYPE O E SCRIPTICN l

l1 l 7 l l010 l0 j'-l NA 3 7 11 12 13 PERSCNNE L INJURIE3 NuveER OESCRIPTION l

l1 l3l 0 l0 l0 l NA 80 d

7 3 7 11 12 LOSS OF CR D AMAGE To FAC:LITY a 0 012, 6

l voE 3ESCRIPTION l 2 l@l NA 7

. 3

0 NRC USE CNLY ESCRIP?lCN @

l lIIIIIII II If l?

SSU E I: I al IN l NA k

58 69 30 7

e >

JVR 78-102 Dick 3rewn / Roger cede P-ONE: 419-2 50-5000, nr. 250

?

y2ygc,,ogy,ggg

TOLEDO EDISON COMPANY

)

DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION

~M SUPPLEMENTAL INFORMATION FOR LER NP-33-78-79 DATE OF EVENT: June 7, 1978 through June 11, 1978 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Six Containment Isolation Check Valves were found inoperable by the Local Leak Rate Test.

Conditions Prior to Occurrence:

The unit was in Mode 6, with Power (MWT) = 0, and Load (MRE) = 0.

Description of Occurrence:

On June 7, 1978 through June 11, 1978, the Containment Isolation Check Valves listed below were found inoperable during the perfor=ance of the " Containment Local Leak Rate Test", ST 5061.02:

1.

Containment Vessel Air Sample Isolation Check Valve, CV125 2.

Hydrogen Dilution System 1-1 Containment Isolation Check Valve, CV210 3.

Hydrogen Dilution System 1-2 Containment Isolation Check Valve, CV209

<s 4.

Instrument Air System Containment Isolation Check Valve, IA501 5.

Station Air System Containment Isolation Check Valve, SA502 g

N-6.

100 PSI Nitrogen Header Containment Isolation Check Valve, NN58 The check valve leakage in each case was determined to be in excess of the local leak rate test requirements.

The unit was in Mode 6 and thus did not enter the Action Statement of Technical Specification 3.6.3.1, which requires the containment isolation "al ras to be operable in Modes 1, 2, 3 and 4.

These incidents are being repot : (d ac component failures.

Designation of Acoarent Cause of Occurrence:

The cause of these inoperabilities was component failure. Some of the check valve internals contained particles of dirt which prevented proper seating of the valves while performing the local leak rate test.

The valves also had indications of wear and pitting which prevented proper seat.ng.

Analvsis of Occurrence: There was no danger to the hea2th and safety of the public or unit personnel.

Containment isolation was maintained by existing redundant isolation valves in series with the valves that were found inoperable.

The redundant isolation valves were tested per the Local Leak Rate Test and de-termined to be satisfactory.

[

) LER #78-065 V

TOLEDO EDISON COMPANY DAVIS-BESSE CTIT ONE NUCLEAR POWER STATION SUPPLEMENTAL INFORE\\ TION FOR LER NP-33-78-79 PAGE 2

Corrective Action

The discs and seats of valves IA501, SA502 and Cv125 were cleaned of dirt and all the valves were lapped per Maintenance Work Orders 78-1354 (IA501),

78-1358 (CV125), 78-1359 (,Cv210), 78-1360 (CV209), 78-1362 (NN58), and 78-1379 (SA502). The valves were retested per the Local Leak Rate Test, ST 5061.02 on June 9, 1978 through June 18, 1978. All of the valves passed the test and were declared operable. The Toledo Edison Power Engineering and Construction Depart-ment is presently evaluating the application of these check valves.

Failure Data: There have been no previous similar occurrences.

LER #78-065 s

I i

l

__~.. _ _ _, _,