ML17331A671

Updated LER 80-034/03X-2:on 801204,containment Isolation Valve NCR-252 Found Not Fully Seated W/Shut Indication in Control Room During Mode 5.Cause Undetermined.Valve Stroke Adjusted

ML17331A671
Person / Time
Site:	Cook
Issue date:	03/04/1981
From:	Rischling J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17331A670	List: ML17331A668 ML17331A671 ML17331A672 ML17331A673
References
LER-80-034-03X, LER-80-34-3X, NUDOCS 8103100566
Download: ML17331A671 (4)

Text

L AR R LATDRY coMMlssloN UPDATE REPORT PREVIOUS REPORT DATE l 2+gym LlCENSEE EVENT REPORT NTROL BLOCK: 1 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 8 9 tn I I.ICENSEE CODE I 4 ~

14 15 6

LICENSE NUMBER 25 Q3 26 LICENSE TYPE 04~

30" 57 CAT 58 Qs CON'T

~01 REPORT 0 3 0 4 8 7 8

~Q6 60 61 DOCKET NUMBER 68 69 O 4 EVFNT DATE 74 Qs 75 REPORT DATE 1

80 QB EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 UNIT WAS SHUTDOWN IN MODE I WAS FOUND THAT CONTAINMENT ISOLATION VALVE,NCR-252 W S

~O4 INDIC I 6 MODE 5 IT IS POSSIBLE NCR-252 MAY NOT HAVE BEEN FULLY OPERAB

~OB ISOL

~o 7 SAFETY OF THE PUBLIC WERE NOT EFFECTED. SE PP

~OB 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENTCODE SUBCODE SUBCODE 8

~S[)

9 10 Qll y Q12 LLI 12 Q13 13 18 Q14

[gJ 19 Q16 [gJ 20 Q16 7

SEOUENTIAL OCCURRENCE REPORT REVISION LERIRO P>>REPORT ACTION FUTURE EVENT YEAR

~9P 22 21 EFFECT

~

23 SHUTDOWN

~Q3 24 REPORT NO.

4 26 ATTACHMENT CODE NPRDQ TYPE PRIME COMP.

~r 32 COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~Q18 ~Q19 ~Q20 gJQ21 40 hJ Qs 41 IJLIQ4 42 LaJQ>>

43 44 47 Qs CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o HE EXACT CAUSE FOR THE P DETERt1INED. THE VALVE OPERATOR WOULD ST NOT PERMIT VALVE TO SHUT COMPLETELY. THE VA V 3 SHUT COMPLETELY AND CYCLING TIt1E WAS ACCEPTABLE.

NUTS ARE SEALED IN PLACE WITH ELOCTITE.

80 7 8 9 FACILITY METHOD OF OTHER STATUS QBO D I 5C OV E R Y DISCOVERY DESCRIPTION Q32 STATUS  % POWER O~Z LJQ26 LtLLOJaJQ>>

10 12 13 44 LalQ31 45 46 80 7 8 9 ACTIVITY CONTENT 9

RELEASED OF RELEASE AMOUNT OF ACTIVITY NA Q LOCATION OF RELEASE Q36

~Z Q33 ~ZQ34 8 9 10 11 44 45 80 7

4 PERSONNEI. EXPOSURES NUMBER TYPE DESCRIPTION Q39

~77 7 8

~pp 9

p 11 Q 12 Z Qss 13 NA 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 7

9 8

~pQ49 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION

,~1e ~Q42 80 8 9 10

~2O ISSUED

~Q44 PUBLICITY DESCRIPTION ~ NRC USE ONLY 49 44 O

68 69 804 g 0

Jack Rischlin 41 0 0

~~ ~

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SUPPLEMENT TO LER 80 - 034/03-L-0 ITEM 10 Ophrations Department was performing ISI Test on Check Valve PW-275 on the Primary Hater Supply to the Containment. Air operated valve NCR-252 was placed in the shut position and the test connection between these two valves opened to verify PW-275 seats on reverse flow in system. When leak-age was observed at test connection the Operator looked at NCR-252 and found i was not fully seated,, even though Control Room indication indicated valve was'hut.. A C8 I Technician found- the stroke adjusting nut improperly set and not permitting the valve to fully shut. The stroke was readjusted and the valve timing cycle was verified acceptable. The test connection was again opened with NCR-252 in the shut position and verified NCR-252 and PW-275 were both shut with no leakage from the test connection.

A review. of maintenance and testing records revealed the last maintenance and stroke adjustment to NCR-252 were performed on February 4, 1980. Check valve PW-275 was successfully tested on July 4, 1980 with no leakage back through the check valve or through NCR-252. Valve NCR-252 had been, cycled for Surveillance Testing on July 29, 1980 with acceptable timing and correct valve position indication in the Control Room.

Unit 2 had entered Mode 4 on July 12, 1980 and Mode '1 on July 13, 1980 and had operated at various power levels up to 100% until October 18, 1980 when the Unit tripped with a generator ground. Unit 2 had entered Mode 5 again on October 21, 1980. The maximum time NCR-252 could have been in a condition of not being able to fully shut as a Containment Isolation Valve was 81 days, but the exact number of days could not be determined.

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