05000321/LER-1980-027-03, /03L-0:on 800310,during Review of Surveillance Schedule,Discovered Rod Block Monitor Functional Test & Calibr Not Performed within Required Interval.Caused by Personnel Oversight.Surveillance Acceptably Performed

/03L-0:on 800310,during Review of Surveillance Schedule,Discovered Rod Block Monitor Functional Test & Calibr Not Performed within Required Interval.Caused by Personnel Oversight.Surveillance Acceptably Performed

ML19309B604
Person / Time
Site:	Hatch
Issue date:	04/01/1980
From:	Nix R GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19309B595	List: 05000321/LER-1980-027, Forwards LER 80-027/03L-0 05000321/LER-1980-027-03, /03L-0:on 800310,during Review of Surveillance Schedule,Discovered Rod Block Monitor Functional Test & Calibr Not Performed within Required Interval.Caused by Personnel Oversight.Surveillance Acceptably Performed
References
LER-80-027-03L-01, LER-80-27-3L-1, NUDOCS 8004040426
Download: ML19309B604 (2)

LER-1980-027, /03L-0:on 800310,during Review of Surveillance Schedule,Discovered Rod Block Monitor Functional Test & Calibr Not Performed within Required Interval.Caused by Personnel Oversight.Surveillance Acceptably Performed

Event date:
Report date:
3211980027R03 - NRC Website

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o 2 l During normal operation and while reviewina the surveillance schedule, the Rod Block Monitor Functional Test and Calibration was found not to l

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have been performed within the interval required by Tech Specs, Table l

Io Isl l 4.2-7, Item 4.

The last allowable date was 3/9/80 and the procedure was l

0 s l performed on 3/10/80.

A similar event was reported on LER 50-321/1980-05.

I There was no effect upon public health or safety due to this event.

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NARRATIVE

REPORT Georgia Power Company Plant E. I. Hatch

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Baxley. Georgia 31513 Reportable Occurrence No.

i-321/1980-027.

During normal plant operation the Functional Test and Calibration procedures for the Rod Block Monitor was not performed within the interval specified by Tech Specs, Table 4.2-7, Item 4.

The last all.owable date was March 9,1980.

The Rod Block Monitor Functional Test and the Rod Block Monitor Calibration procedures were performed immediately upon discovery on March 10, 1980. The results of the test was satisfactory.

A similar event was reported on LER 50-321/1980-05.

The changes, to our surveillance program, that were made as a result of the previous occurrence are sufficient and additional training and discipline should prevent these errors in the future.

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s Georgia Power Compcry Post Othee Bom 442 Baxley.Georg.a 31513 Telephone 912367 7781 912 537 9444 b

Georgia Power Edwin I. Hatch Nuclear Plant the southem etextrc system April 1,

1080 PM-80-392 PLANT E.

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HATCH Licensee Event Report Docket No. 50-321 United States Nuclea' Regulatory Come: tis s ion Office of Inspection and Enforcement Region II Suite 3100 101 Marietta Street Atlanta, Georgia 30303 ATTENTION:

Mr. James P.

O'Reilly l

Pursuant to section 6.9.1.9'.d of Hatch Unit 1

Technical Specifications, please find attached Reportable Occurrence Report # 50-321/1980-028.

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J. H.

Miller, Jr.

R. J.

Kelly W.

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60 61 COCKET NUMBER 68 69 EVENT OATE 74 75 REPORT C ATE 80 EVENT oESCRIPTION ANo PROB ABLE CONSEQUENCES h O 2 During steady state, full power operation / secondary containment inteq-1 trity was momentarily violated twice on 3'-13-80 and once on 3-17-80, at i

0 2 [the 164' elevation reactor building airlock.

Licensed operations person-l O 4 pel verified the doors reclosed immediatley and secondary containment i

a s tintegrity was maintained by ) /=

water vacuum pressure to comply with I

O s 1017 ] Fech Specs 4.7.C.2.

This is a repetitive occurrence:

see LER #50-321/ l lOisi11980-021.

There were no effects upon public health or safety.

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34 35 36 37 40 41 42 43 44 47 33 CAUSE oESCRIPTION AND CORRECTIVE ACTIONS h Rhe cause of these events was design deficiency.

The present design of I

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$he airlock interlock system will not prevent the simultaneous opening i

i i i, i,i pf two airlock doors.

Design Change" Request 79-409 has been written to l

l,13l l revise the present system to prevent the recurrence of this type event.

1 l Implementation is awaiting delivery of parts and completion of design.

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7 8 9 10 912-367-7781 NAME oF PREPARER.C. L. CoqQin. Suot. Plt. Ena. Serv.

PacN g:

LER #:

50-321/1080-028 Licensee; Oeorgia Power Company Facility Name:

Edwin I.

Hatch Docket #:

50-321 Narrative Rep.orf for LER 50-321/198,0-028 O

A t.

1616' hours and 1025 hours0.0119 days <br />0.285 hours <br />0.00169 weeks <br />3.900125e-4 months <br /> on 3-13-80, and at41640 hours on 3-17-80, while at steady state operation, secondary containment integrity was momentarily violated when personnel inad"9rtently opened two 164' elevation reactor building airlock doors simultaneously.

Licensed operations pe-sonnel visually inspected the airlock doors to insure that they had been properly reclosed and that secondary containment integrity was restored.

Licensed operations personnel also verified that secondary containment integrity was maintained by greater than or equal to 1/4" water negative ' pressure to comply with Tech Specs 4.7.C.2,

" Secondary Containment, Su rv e illa :.c e After Integrity Violated."

This type of violation of secondary containment integrity has happened in the past and is caused by the inadeounte design of the present airlock interlock system.

Although plant i

personnel ' nave been instructed in the proper usage of the airlock doors, the present airlock interlocking scheme does not provide a

rapid enough response to prevent the simultateous opening of two airlock doors.

Design Change Request 79 400 has been written to revisc the present airlock interlock system, thereby alleviating the recurrence of this event.

This modification wi' assign a priority to one of the

doors, and the revised interlocking scheme will be onahled brfore the first door is allowed to open.

The problem of secondary containment integrity violations at.

i the airlocks is inherent to both-Hatch Unit 1,

Docket #50-321, and Hatch Unit 2,"

Docket

1. 50-366.

Design Change Request 79-409 will be inplemented for both Hatch Unit 1 and Hatch Unit 2 airlock doors.

The present target date for completion of this modification is 10-1-80.

Upon finalization of the architectural design and delivery of remaining materials, implementation will begin at the-most heavily trafficked airlocks.

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