ML19347C833
| ML19347C833 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/09/1975 |
| From: | Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| AO-16-75, NUDOCS 8103090813 | |
| Download: ML19347C833 (1) | |
Text
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,7,(f 7-9-75 1-58 PM T0- J G KEPPLER US NRC GLEN El. LYN, IL THE FOLLOWING IS CONFIRMATION OF A TELEPHONE CONVERSATION AT 1845 HOURS, JULY 9,1975 BETWEEN D E DE MOOR, CP CO, AND E L JORDAN, US NR C.
1.
REPORT NO-A0-16-75 DOCKET-50-155 2A. REPORT DATE-JULY 9,1975 2B. OCCURRENCE DATE-1%Y 30, 1975 4 LASSIFIED AS A/O ON 7-8-75/
3.
FACILITY-BIG ROCK POINT PLANT, CHARLEVOIX, ICHIGAN 4
IDENTIFICATION OF OCCURREleCE-PROCEDURAL DEFICIENCIES ASSOC-I ATED WITH REACTOR AND FUEL PIT VALVE A;V/4027/ INSPECTION AND R EPAIR.
5 CONDITIONS PRIOR TO OCCURRENCE-PLANT SHUT DOWN FOR MODIFICA-TIONS ASSOCI ATED WITH A0-1-75.
6.
DESCRIPTION OF OCCURRENCE-QUALITY ASSURANCE DEPARTMENT AUDIT OF SAFETY-RELATED MAINTENANCE ACTIVITIES ON 7(/13/75 IDENTIFIED DEFICIENCIES IN SIGNO-OFF OF PORTIONS OF THE PROCEDURE AND THESE DEFICIENCIES WERE CLASSIFIED AS NONREPORTABLE AT THAT TIME. SUB-SEQUENT INVESTIGATION AND REVIEW BY THE PLANT REVIEW COMMITTEE ON 7/8/75 IDENTIFIED THAT THE PROCEDURE USED /MGP-4, REV 0/
g-WAS GENERIC IN hATURE AND DOES NOT PROVIDE ADEQUATE DETAIL TO COVER THE ADJUSIMENTS NEEDED. THE EVENT WAS RECLASSIFIED AS AN ABNORMAL OCCURRENCE.
k 7.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE-FAILURE IN IMPLE-MENTAT10N OF ADMINISTR ATIVE CONTROLS.
8.
ANALYSIS OF OCCURRENCE-THE VALVE WAS TESTED AND MET TECHNICAL SPECIFICATION ISOLATION REQUIREMENTS FOLLOWING THE MAINTENANCE WORK. A SECOND ISOLATION VALVE IN SERIES IS ALSO FULLY OPERABLE AND THUS NO UNDUE HAZ ARD EXISTED FOR THIS EVENT.
9.
CORRECTIVE ACTION-THE SUBJECT OF GENERIC VERSUS SPECIFIC PRO-CEDURES FOR MAINTENANCE ACTIVITIES IS BEING REVIEWED. SUPERVIS-ORY PERSONNEL ASSOCI ATED WITH THE EVENT HAVE BEEN VERBALLY IN-STRUCIED IN REQUIREMENTS FOR PROCEDURE ADHERENCE AND SIGH-OFF REQUIREMENTS. THE VALVE WILL BE RETESTED AGAIN 7sTO DETERMNE THE l%RGIN OF SHUT 0FF CAPABILITY DURIN3 THE NEXT COLD SHUTDOWN FOL-LOWING DEVELOPMENT OF AN ADEQUATE PROCEDURE.
10 FAILURE DATA-REFERENCE EVENT IS A0-15-75 IN LETTER OF JUNE 10, 1975 AND USE OF THE SAME PROCEDURE /MGP-4 REV 0/ APPEARS TO HAVE CONTRIBUTED TO THE CAUSE OF THAT EVENT WHEN IT WAS USED FOR VALVE INSPECTION AND ADJUSTMENTS IN APRIL OF 1974 R B SEWELL NUCLEAR LICENSING ADMINISTRATOR END - WW CC-DIVISION OF REACTOR ICENSING nani wION, DG C J HARTMAN BIG ROCK POINT 1
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