ML19289G122
| ML19289G122 | |
| Person / Time | |
|---|---|
| Site: | Crane, Davis Besse  |
| Issue date: | 03/29/1979 |
| From: | Ahearne J NRC COMMISSION (OCM) |
| To: | Jennifer Davis, Harold Denton NRC OFFICE OF INSPECTION & ENFORCEMENT (IE), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906260488 | |
| Download: ML19289G122 (2) | |
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,tiSS10N E R MEF.O TO:
Harold Denton, NRR John Davis, I&E d/
FROM:
John F.
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SUBJECT:
STATUS REPORT ON DAVIS-BESSE UNIT NO. 1 In the December 20th memo to me discussing the actions taken by Davis-Besse Unit No.
1, I noted that the unit was still completing power ascension testing and had not yet operated for sustained periods above 90% power, even though the OL was issued in April 1977.
Recently, the response to Question 17 to Congressman Dingell's February 6, 1979 le.:ter indicated that the Davis-Besse Unit 1 availability and capacity factor for the year 1978 was the lowest of any reactor that operated during the year, with the exception of Duane Arnold.
I am aware of the problems associated with the Duar.e Arnold reactor; however, I am not aware of the difficulties that are occurring at Davis-Besse.
In light of the above and the fact that the Davis-Besse design is similar to that of the Three Mile Island Unit 2 design, please p.rovide me with a detailed status report on this plant.
Attached are some specific questions I would like addressed in that response.
Attachment:
As stated cc:
Chairman Hendrie Commissioner Gilinsky Commissioner Kennedy i
Commissioner Bradford I
Lee V. Gossickve' Samuel J.
Chilk Al Kenneke Len Bickwit
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1.
What are the problems that created the difficulty
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in completing the power ascension testing for this
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C reactor?
Have they been adequately resolved?
Are there any test results which the staff has not deter-
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mined to be satisfactory?
2.
What outstanding licensing issues are there?
Have any exemptions been granted for this plant?
If so, the justifications for those exemptions?
what are 3.
Is part of the reason for the low capacity factor attributable to the plant operator personnel?
How do the plant operators compare with other plant operators in Region III?
In particular, I would note the recent notifications of the Commission about problems with the valving errors on the ECCS for both the low pressure and high pressure safety injection systems.
4.
In view of the recent Three Mile Island accident, are there any plant systems related to the saf e operation of the plant which have experienced specific difficulties?
In particular, please provide me with the licensing staff's analysis of the September 24, 1977 event and all major subsequent events that have occurred at the plant.
5.
Have any safety systems been subject to a large number of LER's?
Please provide details of the staff's revieu of these items.
6.
How do LPo facility change requests for this. station compare with other operating reactors which have been licensed in about the same timeframe?
7.
Are defects which have been identified in safety-related systems analyzed and corrected in a timely fashion by the licensee?
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