ML17331A523

LER 80-034/03L-0:on 801204,during Inservice Insp Testing, Containment Isolation Valve NCR-252 Was Not Fully Seated W/Shut Indication in Control Room.Cause Undetermined.Valve Stroke Adjusted & Valve Shut Completely

ML17331A523
Person / Time
Site:	Cook
Issue date:	12/31/1980
From:	Keith R INDIANA MICHIGAN POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17319A679	List: ML17319A678 ML17331A523
References
LER-80-034-03L, LER-80-34-3L, NUDOCS 8101060795
Download: ML17331A523 (4)

Text

(

NRC FORM 366 (7 77)

[os]

CONTROI BLOCK:

M I D C C 1

2 Q2 0 I

0 0 LICENSEE EVENT REPORT 6

0 QI 0 0 0 0 0 0 0 Q34 U. S. NUCLEAR REGULATORY COMMISSION (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 1 1 1Q4~Q8 LICENSEE CODE 'I4 15 LICENSE NUMBER 25 26 I.ICENSE TYPE 30 57 CAT 58 8 9 CON'T

~oi """ ~LQB 0 5 0 0 0 3 1 6 Q7 1 2 0 4 8 0 QB 1 2 3:.1 8 0 80 Qe DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 UNIT WAS SHUTDOWN IN MODE 5 WHILE CONDUCTING ISI TESTING OF CHECK VALVE PW 275 IT 3

WAS FOUND THAT CONTAINMENT ISOLATION VALVE NCR-252 WAS NOT FULLY SEATED WITH SHUT

~o 4 INDICATION IN THE COI'ITROL ROOM. WHILE CONTAINMENT ISOLATION IS NOT REQUIRED IN, .

6 MODE 5 IT IS POSSIBLE NCR-252 MAY NOT HAVE BEEN FULLY OPERABLE AS A CONTAINMENT

~OB ISOLATION VALVE SINCE JULY 29, 1980 IN VIOLATION OF T.S ~ 3.6. 1. 1. THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT EFFECTED - (SEE SUPPLEMENT).

~OB 80 7 8 9 SYSTEM CAUSE CAUSE COMP VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 8 9 10 Q>> x Q>> ~zos 12 13 v A L v 0 0 18 Q LoIQ78 19

~0Q78 20 SEQUENTIAL OCCURRENCE REPORT REVISION EVENT YEAR REPORT NO. CODE TYPE NO.

Q17 LER7'RP 88>>>> ~80 21 22 I:I 23

~03 24 4

26 Q~

27 LOD3I 28 29 UL 30 LJ 31 Uo 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDX PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER Qls&ZQ19 ~ZQ30 ~ZQ>> 0 0 0 0 Y Q33 ~NQ24 A Q38 0 2 5 5 Q38 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 COULD NOT BE DETERMINED. THE VALVE OPERATOR WOULD STROKE THE VALVE BUT IMPROPER ADJ T 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.

4 80 7 8 9 FACILITY METHOD OF OTHER STATUS QSO DISCOVERY DISCOVERY DESCRIPTION Q32 STATUS  % POWER 5 ~oQ3s ~00 0 Q39 NA 44

~BQ>>

45 46 OPERATOR TECHNICIAN OBSERVATION 80 7 8 9 10 12 13 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q LOCATION OF RELEASE Q 7

8 8

~ZQ33 9

~ZQ 10 11 NA 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~17 ~00 0 Q37 Z Q38 13 NA 80 7 8 9 11 12 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION 9 Z Q4, NA F/IF) 8 9 10 80 7

O ISSUED PUBLICITY 44 DESCRIPTION ~ NRC USF ONLY Cl C4 I

'" 68 69 804 g 8 9 10 R. S. KEITH PHDNE 616 465-5901 EXT. 1313 NAME OF PRFPARER

V i

,/'

SUPPLEMENT TO LER,80 - 034/03-L-0 ITEN 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 obs'erved 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 C81 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.