ML19207B062
| ML19207B062 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/25/1979 |
| From: | Carbon M Advisory Committee on Reactor Safeguards |
| To: | Rogovin M NRC - NRC THREE MILE ISLAND TASK FORCE |
| References | |
| TASK-TF, TASK-TMR NUDOCS 7908230318 | |
| Download: ML19207B062 (2) | |
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UNITED STATES e
! h, [,j NUCLEAR REGULATORY COMMISSION f1 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS gg7 WASHINGTON, O. C. 20S55 o,%, v; p
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July 25, 1979 i
j Mr. Mitchell Rogovin, Director 7
NRC/'IMI Special Inquiry Group U. S. Nuclear Regulatory Concission y
gQ' %) Ct 35N Washington, D. C.
20555
Dear Mr. Rogovin:
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Your letter to me of June 19, 1979 requested information regarding significant ACRS recommendations, in 14 areas, which were made on non-B&W plants prior to March 28, 1979. Attachment A contains such recommendations by ACRS where spe-cific documentation could be found and is organized to follow the ordering of your letter. hhile other examples could undoubtedly be added, I believe that Attachment A contains a fully representative set.
Tabs 1, 2, 3, 4, 6, 7, 8, 9,10,12 and 14 of the Attachment contain informa-tion related to the corresponding items in your letter.
Tabs 11 and 13 in-clude narrative responses to your items 11 and 13. Tab 5 is blank because we find no significant written material on the subject of programming of simulators.
The atmosphere in which the above recommendations were generated included con-tinuing interaction with members of the Regulatory Staff (AEC and NRC) and ap-plicants in several cases.
In the course of the associated discussion, the reg-ulatory requirements and plant designs were often modified without specific Com-mittee recommendation.
For this reason, and in the hope that it might be useful in your investigation, I have included, under the appropriate Tabs, examples of such interactions taken fron pertinent sections of full Committee and Subcoc:ait-tee meeting minutes and tranceript s in addition to specific reccccendations and comments taken from ACRS letter reports.
In connection with Item No.10, " Requirements for Containment Isolation Actua-tion," nuterial has been included which illustrates the early interaction be-tween the ACRS and the AEC Regulatory Staff in establishing the original require-ments for diversity of the signals which actuate Engineered Safety Features, in-cluding the Containment Isolation System.
Similarly, in connection with Item No. 6, on the effect of noncondensible gases in the primary system, several il-lustrations have been included demonstrating the Committee's early interest in evaluating situations or sequences of events which could lead to the formation of such gases.
You also requested the Cccmittee's views on the NRC's responsiveness to its rec-ommendations in the specific areas listed in your letter.
Tae Committee feels that the response of the NRC (and of the AEC before it), in connection with "in-strumentation to follow the course of an accident" has not been adequate.
Al-though this item has been addressed by the issuance of a Regulatory Guide, that 790823032 M 1. 2 3 2 o
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Mr. Mitchell Rogovin July 25, 1979 Guide has not, to the Committee's knowledge, yet been implemented on any operat-ing nuclear power plant.
Finally, although the NRC has given increased attention and resources to the so-called " unresolved generic itens" within the past tw years, w would welcome additional emphasis on resolution of these matters.
I trust that the above will prove responsive to your needs.
Sincerely, Max 1. Carbon Chairman Attachments:
Reply to M. Rogovin, Director NRC/TMI Special Inquiry Group, Attachment A-cc:
M. W. Carbon, w/o attmt.
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