ML19260C713

LER 79-039/03L-0:on 791128,while Shut Down for Repair of Feedwater Sys Nozzles,Maint Was Performed W/O Local Leak Rate Test,Therefore Leakage Rate Not Confirmed.Cause Not Stated.Administrative Procedures Mod

ML19260C713
Person / Time
Site:	Millstone
Issue date:	12/26/1979
From:	Stratman R NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19260C708	List: ML19260C707 ML19260C713
References
LER-79-039-03L, LER-79-39-3L, NUDOCS 8001080490
Download: ML19260C713 (3)

Text

__ _ __ _ .. . _

-m

• LICENSEE EVENT REPORT CONTROL block: l i

l l I I I Ih 6

(PLEASE PRINT OR TYPE ALL REQUIRED INFoRMATION) o i 81 9 lCITIMlNlSI2l@l0l0l-l0l0l0l0I-l0l0l0l@l4 11 Il Il 11 l@l LICENSEE CODE le 15 LICENSE NuMutR 25 26 LICENSE TYPE 40 l

57 CAT SE l@

oN'T o i S

,"cu,"c 60 Ll@l01510l0l0I3l3l6I@l1l11218l7Iol@l1l?I?IAI7Iol@

61 DOCKET NUM8ER 68 69 EVENT OATE 74 75 REPORT DATE 80 EVENT oESCRIPT!oN AND pro 8ABLE CONSEQUENCES h o 2 i While shutdown for repair of the feedwater system nozzles. maintananca was rarfor-ad I o 3 l on several valves u the crimary samoling system and a valve in the Reector Buildino I o . l closed cooling system without first performing a local leak rate test. Consecuently. I ois the combined leakage rate for all penetrations subject to Tyoes B and C testino was I o s I not able to be confinned to be lest than 0.60La as recuired by Technical Specifica- I o 7 l tion 3.6.1.2.8. Subsequent to repairs, the combined measured leakace rate was I o a i found to be less than 0.60La as required. I

• Co S'E "^"o*E Cc sNE$oE CeuPoNENT CooE st Si"c"o'E sEEE o 9 I el A l@ l e l@ La_j @ l p l e l N I c l r l p l@ L7_J@ 171 @

8 9 10 11 12 13 18 19 20

_ SEQUENTIAL OCCURRENCE REPCRT REVISION EVEP:T YE AR REPORT NO; CODE TYPE NO.

LE R/ RO

@ ,atg u 1719 l 21 22 l-l 23 l 01 3 91 24 25

~ l /l 27 lo 13 28 29

[_LJ 30 L- .]

31

(_0.]

32 N CT P T M HCuRS S8 i PCR s 8. SUP LIE MANUPA RER l010101Ol l33B l@34HI@ lZl@

35 l36Zl@ 37 40 l41Y l@ lNl@ l A l@ l Xl 9 91 91 @

43 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTloNS @

t o l The before-recair leakace rates of all valves. which wara ranairad as a ra<ni t V I i i i Tvoe C local leak rate testina were not recorded ranspanan+1y i+ w nn+ =hla I i 2 l to be confirmed that the leakace rate did not exceed 0.6La. Subsecuent to rocairs. I i 3 l the combined leakage for all cenetrations subject to Tvoe: B and C testina was i .i I found to be less than 0.6La. I 7 3 9 80 A  % POWER OTHERSTATUS ISCO RY DISCOVERY CESCRIPTION i s l Gl@ l 01 01 Ol@ NA l l B l@l local leak rate testing I 7 " " '8 8' s AEnvr-v Co'0 TENT AucuNT op 4Criviry @ toc 4 Tion oP RETE 4sE @

i s l Zl 4sEo@ePRELEasElZl@l RETE NA l NA l 7 8 9 10 11 44 45 80 PER$CNNEL EXPOSURES TYPE DESCRIPTION i 7 l INuMBER0l 010l@l Z j@l M l PERseNNEt inau'EEs NuuS E r, oEsCRimeN@

i.a 8 9 i nininl@l 11 12 u

80 I

8001080t M 7

i 9

'oS5 Ty o' o" f,^C"^cgo,1 '^c" @ NA

)g3 j89 l 7 a 9

}@l10 80 issus CE CRIPTION 7

2 o 8 9 hl to NA l 68 69 lll1lllllllI[$;

80 5

.... __ _ ..___ Dnhart 3 9tratman .. .. 7n1 d 7.1701 Y Olit 2

._. _ _ _ _ _ . _ _ _ _ _- __ . _ _ . _ _ . _ _ - _ _ _ . m ATTACHMENT LER 79-39/3L-0 Millstone Unit 2 Docket No. 50-336 Event Description While shutdown for repair of the feedwater system nozzles, maintenance was done on primary sampling system valves 2-RC-001, 002, 003, and 045 without first performing a local leak rate test as required by Surveillance Procedure 26050.

Further, maintenance was authorized for Reactor Building closed cooling system valve 2-RB-28.38. A review of this job showed that a local leak rate test was not required prior to repair of this valve due to the nature of the maintenance to be performed. However, during the course of the repair, the original scope of work was changed such that a local leak rate test would have been required prior to this repair.

Consequently, the combined leakage rate for all penetrations subject to Types B and C testing was not able to be confirmed to be less than 0.60La prior to these repairs as required by Technical Specification 3.6.1.2.8.

Subsequent to the repairs, local leak rate testing of these valves was performed as required, and the combined leakage rate for all penetrations subject to Types B and C testing was found to be less than 0.60La.

Similar Events: LER 79-il/3L-0, dated 5/18/79.

1703 190

Cause Description The before-repair leakage rates of all valves, which were repaired as a result of Type C local leak rate testing, were not recorded. Consequently, it was not able to be confirmed that the combined leakage rate did not exceed 0.6La. Subsequent to repairs, the combined leakage rate for all penetrations subject to Types B and C testing was found to be less than 0.6La. To prevent a future occurrence of this event a list of all valves subject to local leak rate testing has been provided for the Shift Supervisors' use in screening maintenance on these valves. Also, changes to the Administrative Control procedures and associated job order and maintenance request forms are being considered to better control maintenance on equipment subject to local leak rate testing.

1703 191