ML20236A971

Forwards Biweekly Status Rept for 870926-1009

ML20236A971
Person / Time
Site:	Davis Besse
Issue date:	10/19/1987
From:	Defayette R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 8710230271
Download: ML20236A971 (3)

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OCT 191987 MEMORANDUM FOR: Charles E. Norelius, Director, Division of Reactor Projects THRU: W. G. Guldemond, Chief, Reactor Projects Branch 2 FROM: R. W. DeFayette, Chief, Projects Section 2B

SUBJECT:

DAVIS-BESSE STATUS REPORT FOR THE PERIOD SEPTEMBER 26 THROUGH OCTOBER 9, 1987

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Enclosed is the Davis-Besse Biweekly Status Report. During this period, site coverage was provided by the resident inspectors and by a seven member Operational Safety Inspection Team (OSIT).

This Status Report is intended to provide NRC management and the public with an overview of plant activities and NRC inspections. Subsequent inspection reports uill address many of these topics in more detail.

"Origir.a1 signed by R. W. DeFayette" '

R. W. DeFayette, Chief Reactor Projects Section 2B

Enclosure:

Davis-Besse Biweekly Status Report cc w/ enclosure:

L. Storz, Plant Manager DCD/DCB (RIDS)

Licensu q Fee Management Branch Resident Inspector, RIII Harold W. Kohn, Ohio EPA James W. Harris, State of Ohio Robert M. Quillin, Ohio Department of Health State of Ohio, Public Utilities Commission DeFayet e/crr b

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. .a DAVIS-BESSE BIWEEKLY STATUS REPORT

1. Plant Status s

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During this- reporting period, the plant operated continuously at - j or'near 95 pera nt power.

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2~. Facility Operations Summary ~j d"

' After the September 6,1987 shutdown, one of the main' steam safety valves, (B3) failed to fully reseat and was subsequently removed and its position blank-flanged. The Engineering Department performed a visual inspection of the remaining safety valves and concluded that B1'should also be removed. To compensate for this and provide symmetry on the steam header, valve A3 was relocated to the B1 position and position A3 was blank flanged. As a. result of these safety valves being removed, the total relief capacity was reduced, and the plant '{

reduced power operations to approximately 95 percent.

The licensee has projected a total of 87.4 effective full power days  !

remaining on this core and a refueling outage is tentatively ' scheduled for. February 15,196 i.

3. Items of Special Interest 3.1 Augmented Inspection Team (AIT) l The team noted that the licensee's task force approach to assessment of the event was aggressive, thorough, and effective. In addition to determining the root causes and corrective actions for various equipment problems, the task force identified areas of equipment and safety performance requiring attention and provided a forum for the consideration of operator concerns arising from the event. The j team also identified five areas of concern, with regard to both i plant specific and generic aspects of the event that the licensee should evaluate. The AIT concluded that the safety significance of the event was minimal due to the nature of the initiating problem, the response of the plant systems, and to the response of the operators to the trip and to the subsequent equipment malfunctions.

3.2 Operational Safety Team Inspection (OSTI)

A seven member inspection team was assembled under the direction of the Special Inspection Branch, Division of Reactor Inspection and Safeguards, NRR to review five areas of licensed activities at Davis-Besse. The areas selected for an in-depth review using a team approach were operations, maintenance, surveillance, corrective action systems, and management oversite. The team inspection was conducted over a two week period onsite (Saptember 28 through October 9, 1987) and inciaded continuous shift observations for four days. The team completed its inspection on October 9, 1987, and its conclusions will be finalized in Inspection Report No. 50-346/87024.

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i 3.3 NRC Notifications Issued  !

l' September 28, 1987--' Daily Report: An Operational-Safety Team Inspection, led by NRR with participation by regional; inspectors, begins. Septenicer 28, 1987. The inspection is scheduled to'last  ;

two weeks.

'4. NRC Staff Activ'ities During the Period-

~The special Augmented Inspection Team (AIT) issued its report, Inspection Report No. 50-346/87025 on October-1, 1987. A_special 0perational Safety.

. Team' Inspection -(0STI), composed of seven regional, ' headquarters, and contractor personnel,. conducted its inspection and concluded its onsite activities on October.-9, 1987. Routine inspection coverage during the reporting period was provided by the resident inspectors.

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