ML20235Q153

Forwards Augmented Investigation Team Final Charter of Investigation of Events Associated w/870906 Reactor Trip

ML20235Q153
Person / Time
Site:	Davis Besse
Issue date:	09/10/1987
From:	Greenman E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Chrissotimos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20235Q101	List: ML20235Q098 ML20235Q117 ML20235Q135 ML20235Q153
References
NUDOCS 8710070510
Download: ML20235Q153 (12)

Text

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SEP 101987 MEMORANDUM FOR: N. J. Chrissotimos, Team Leader, Davis Besse Augmented InvestigationTeam(AIT)

• FROM: E. G. Greenman, Deputy Director, Division of Reactor Projects I

SUBJECT:

AIT CHARTER ,

Enclosed for your ' implementation is the final Charter for the investigation of the events associated with the Davis Besse reector trip which occurred on September 6, 1987. T is Charter, prepared in accordance with the NRC Incident Investigation Manual',h' Revisionreflects =1, the needs of Regio'n III NRR, and AE0D management. The objectives of the AIT.are to communicate the facts surrounding this event to regional and headquarters management, to identify and communicate any generic safety concerns related to this event to regional and headquarters management, and to document the findings and conclusions of the onsite investigation.

If you have any questions regarding these objectives or the enclosed Charter, please do not hesitate to contact either myself or W. Guldemond of my staff.

f&k. h Y E. G. Greenman, Deputy Direct.or Division of Reactor Projects

Enclosure:

AIT Chartel cc w/ enclosure:

A. B. Davis, RIII C. J. Paperiello, RII:

F. Miraglia, NRR J. Partlow, NRR -

C. Rossi NRR G. Holahan, NRR W. Lanning,'NRR M. Virgilio, NRR

, R. Cooper, EDO l ' P.' Byron,' SRI'

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E B710070510 871001 PDR G ADGOK 05000346 .

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DAVIS BESSE EVENT AUGMENTED INVESTIGATION TEAM (AIT) CHARTER

1. . Develop and validate the sequence of events associated with.the September 6,1987, reactor trip at Davis-Besse. This sequence should begin with plant conditions immediately prior to the event, including known significant deficiencies in safety-related and. balance of plant equipment, and extend until the plant was stable on the Decay Heat [

Removal System. Key items to be included are all equipment malfunctions, major plant evolutions / status changes, operator errors, licensee management / support organization response, and reports made to the NRC.

2. Evaluate the significance of the event with regard to radiological consequences, safety system performance, and plant proximity to' safety limits as defined in the Technical Specifications.

3. Evaluate the accuracy, timeliness, and effectiveness with which 1 information on this event was reported to the NRC.

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4. For each equipment malfunction, to the extent practical, determine:

a. Root cause.

b. If the equipment was known to be deficient prior to the event. )

c. If equipment history would indicate that the equipment had either been historically unreliable or if maintenance or modifications had Si been recently performed. 6

d. Pre-event status of surveillance, testing (e.g.,Section XI), and/or  !

preventive maintenance.

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L e. The extent to which the equipment was covered by existing corrective -j action programs and the implication of the failures with respect to n

.i program effectiveness.

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l 5. Identify any human factors / procedural deficiencies related to this event.

6. Through operator injerview, determine if any of the following played a significant role in the event: ' plant material condition; the quality '

of maintenance; or the responsiveness of engineering to identified problems. Unles.s.,these concerns involve immediate safety issues, team action should be limited to communicating the concerns to NRC management.

7. Provide a Preliminary Notification update upon initiation and conclusion of the inspection.

8. Prepare a special inspection report documenting the results of the above activities within 30' days,of inspection completion.

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SEP 18 est Tolvdo Edison Company- )

1 ATTN: Mr. Donald Shelton i

Vice President Nuclear Edison-P1aza '

300 Madison Avenue Toledo, OH 43652 l Gentlemen:

On September 6,1987, the Davis Besse Nuclear Power Plant exp'erienced an automatic reactor trip with multiple equipment failures. Because of the significance the NRC attaches to such events, and in light of prior history at-Davis Besse, Region !!! with the support of NRC Headquarters, on September 8, 1987, dispatched an Augmented Investigation Team to the site to

. review the circumstances leading _up to the reactor trip and to evaluate the significance of and your response to the subsequent equipment failures. Based on the results of that team inspection and your.results presented at the meeting with the NRC in Bethesda, Maryland on September 15, 1987, we conclude' 1 that your investigation into the circumstances surrounding the reactor trip and the subsequent equipment failures, was thorough; that the investigation identified root causes associated with the various occurrences; and that you established l an appropriate action plan to support plant restart. i After consultation with Senior NRC Management. I have concluded that'it is I appropriate that you be authorized to restart the Davis Besse facility and '

conduct norr.a1 operations. Notwithstanding the findings of the Augmented Investigation Team and the information that you presented to us during our 1 meeting of September 15th, concerns,still persist regarding the overall- j material condition of the Davis Besse facility and the rate at which that 1

. material condition is being addressed by your existing Course of Action programs.

You are, therefore, requested to review your existing plans for improving the 1 overall material condition bf the Davis Besse plant, and in coordination with l the commitments set forth in your Course of Action document, make a determination l as to whether a reprioritization of your activities is appropriate. You are further requested to meet with the NRC in approximately 45 days to discuss .the i

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.loledo Edison Company 2 findings of your reviews and conclusions in this regard. Specifically, you s hould be prepared to discuss the outstanding backlog of corrective and preventive maintenance, actions taken or planned to reduce that backlog, and I the impact of that backlog on continued safe and reliable plant operations, hh n-.- --er -

A. Bert Davis Regional Administrator L. Storz, Plant Manager DCS/RSB (RIDS) q Licensing Fee Management Branch -

1 Resident inspector Rll!

Harold W. Kohn, Ohio EPA James W. Harris, State of Ohio {

Robert M. Quillin, Ohio j Department of Health I

-State of Ohio, Public 1 Utilities Consnission 1 T. Rehm, EDO R. Cooper, EDO.

W. Fanning,'AEOD j l

F. Miraglia, NRR  !

G. Holahan, NRR M. Virgilio, NRR ]'

J. Partlow, NRR P. Byron, SRI J. Strasma, Rlli 1 d

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