ML19319B935
| ML19319B935 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/17/1977 |
| From: | Fraley R Advisory Committee on Reactor Safeguards |
| To: | Rusche B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001290670 | |
| Download: ML19319B935 (2) | |
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fg UNITED STATES s,
g NUCLEAR, REGULATORY COMMISSION y
l ADVISORY COMMITTEE ON REACTOR SAFEGUARDS g
WASMNGTON, D. C. 20555 February 17, 1977 Benard C. Rusche, Director Office of Nuclear Reactor Regulation
SUBJECT:
ACRS REPORT ON DAVIS-BESSE hTJCLEAR PCWER STATION, UNIT 1, DATED JANUARY 14, 1977 During the 202nd ACRS meeting, the Comittee considered your request of January 31, 1977 for clarification of the subject ACRS report. Se memMz discussed the bases for the Comittee's report on the Davis-Besse Station and the comments noted below are reflected in the meeting minutes.
Se NRC Staff interpetation of the first matter, as it appears in the last 5 lines on page 2.nd the first 5 lines of page 3 is correct except in the following respects:
(a)
In the Comittee's opinion " currently accepted procedures for deconvolution" are not acceptable at this site for structures founded on rock. It is the Comittee's opinion that the Regulatory Guide 1.60 Design Response Spectra should be applied at the foundation level of such structures.
(b) ne systems to be investigated should include those needed for continued shutdown heat removal as well as those " systems needed for safe shutdown."
(c)
In view of the fact that the review is being made for a plant designed to different criteria, and already constructed, the responses of the components and systems reviewed r.eed not be strictly "within current acceptance limits." Instances in which those limits are exceeded may be considered acceptable on a judgment basis, with due consideration to the contribution of seismic motions to the overall response.
Se second matter, summarized on page 3 of your letter was intended to address the generic item " Instrumentation to FTllow the Course of an Accident" (Item II-ll of the ACRS report on Generic Items dated April 16, 1976) with the following clarification:
(a) Appropriate emphasis should be given to the resolution of this item so that it is acconplished prior to comercial operation of the Davis-Besse 1 Plant.
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B. Rusche February 17, 1977 (b) Additional attention should be given to develognent of proce-dures to be used by the plant operators in taking appropriate corrective action for incidents and accidents with very low probabilities of occurrence.
We Comittee plans to give further attention to the developnent of procedures to cope with operating events of intermediate probability to limit their consequences on the public health and safety. h is will be done on a generic basis, however.
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ra ey Executive Direc or cc:
L. Gossick, EDO S. 01 ilk, Secy.
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