ML17331A579

LER 80-034/03X-1:on 801204,containment Isolation Valve NCR-252 Was Not Fully Seated W/Shut Indication in Control Room.Cause Undetermined.Valve Stroke Adjusted & Valve Shut Completely

ML17331A579
Person / Time
Site:	Cook
Issue date:	01/08/1981
From:	Keith R INDIANA MICHIGAN POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17331A578	List: ML17331A577 ML17331A579
References
LER-80-034-03X, LER-80-34-3X, NUDOCS 8101210451
Download: ML17331A579 (4)

Text

NRC FORM 366 U UCLEAR REGULATORY COMMISSION I7-771 LICENSEE EVENT REPORT CONTROL BLOCK: Qi (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

~01 7 8 9 N 1 D LICENSEE CODE C C 2 QE 14 15 0 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 QE 26 4 1 1 I.ICENSE TYPE 1 1QE~QE 30 57 CAT 58 CON'T, soURcE LQQB 0 5 0 0 0 3 1 6 Q7 1 2 0 4 8 0 Qs 0 1 0 8 8 1 Qe 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10

~o2 UNIT WAS SHUTDOWN IN MODE 5. WHILE CONDUCTING IS I TESTING OF CHECK VALVE PW-275 IT WAS FOUND THAT CONTAINMENT ISOLATION VALVE NCR-252 WAS NOT FULLY, SEATED WITH SHUT INDICATION IN THE CONTROL ROOM. WHILE CONTAINMENT ISOLATION IS NOT REQUIRED IN MODE 5 IT IS POSSIBLE NCR-252 MAY NOT HAVE BEEN FULLY OPERABLE AS A CONTAINMENT ISOLATION VALVE SINCE JULY 29, 1980 IN VIOLATION OF T S ~ ~ 3~6~1~1 ~ THE HEALTH AND o 6 SAFETY OF THE PUBLIC WERE NOT EFFECTED - (SEE SUPPLEMENT).

o s PREVIOUS OCCURRENCE 80 007/03 L 0 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 8

~30 9 10 Ql'1 11 X QEE ~zpn 12 13 V A L V 0 P 18 Q4 ~DQE 19

~DQ'E 20 SEOUENTIAL OCCURRENCE REPORT REVISION Q11 LERIRO REPQRT ACTION FUTURE EVENT YEAR

~30 22 EFFECT

~

23 SHUTDOWN

~03 24 REPORT NO.

4 26

~~

27

~03 28 ATTACHMENT CODE 29 NPRDR TYPE

~z 30 PRIME COMP.

~

31

~1'1 NO.

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS +22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~EQER LZJQER ~ZPEE ~ZQ>> O O O Z ~VP>> ~NPE4 ~APER 0 3 3 3 PER 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o THE EXACT CAUSE FOR THE OPERATOR FOR NCR-252 BEING OUT OF ADJUSTMENT COULD NOT BE DETERMINED. THE VALVE OPERATOR WOULD STROKE THE VALVE BUT IMPROPER ADJUSTMENT WOULD NOT PERMIT VALVE TO SHUT COMPLETELY. THE VALVE STROKE WAS ADJUSTED AND THE VALVE SHUT COMPLETELY AND CYCLING TIME WAS ACCEPTABLE. NO FURTHER ACTIONS PLANNED.

3 4

7 8 9 80 FACILITY METHOD OF

% POWER OTHER STATUS QBO DISCOVERY DISCOVERY DESCRIPTION A32 STATUS 0 QEE ~00 10 0 PEE NA 44

~DPE1 45 46 OPERATOR/TECHNICIAN OBSEAfATION 80 7 8 9 12 13 4 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q LOCQTION OF RELEASE Q 7 8 Lzj 9

Q>> LzJQEE 10 NA 44 45 NA 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 8

~00 0 QE ZQEE 13 NA 80 7 9 11 12 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY ~43 g or zt oM/

TYPE DESCRIPTION

~PE Z PEE NA 7 8 9 10 80 PUBLICITY 'RC ISSUED DESCRIPTION Q NA USE ONLY KH L~ 8 9 JQ44 10 68 69 80 E

R. S. KEITH 616-465-5901 EXT ~ 1313 NAME OF PREPARER

t SUPPLEMENT TO 4

LER 80 - 034/03X-"1,',

ITEM 10 Operations Department was performing ISI Test on Check Valve PW-275 on the Primary Water 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 it was not fully seated, even though Control Room indication indicated valve was shut. A CSI 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, 1005 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.

JC ~

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