ML19323H830
| ML19323H830 | |
| Person / Time | |
|---|---|
| Issue date: | 05/05/1980 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Mattson R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19323H828 | List: |
| References | |
| NUDOCS 8006160235 | |
| Download: ML19323H830 (1) | |
Text
1, UNITED STATi 3 NUCLE.AR REGULATORY COMMISSION
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MEMORANDUM FOR: Roger J. Mattson, Director Division of Safety Technology Office of Nuclear Reactor Regulation FROM:
Harold R. Denton, Director Office of Nuclear Reactor Regulation
SUBJECT:
LETTER FROM AIF SUBCOMMITTEE ON SAFETY PARAMETER INTEGRATION As a matter of NRR policy; activities affecting more than one TMI Action Plan Task (NUREG 0660) and more than one NRR division are to be coordinated by DST. The attached letter from AIF dated April 23, 1980 is an example of such an action.
I am particularly interested in your division coordinatino with AIF, other NRR divisions and IE to provide recomendations regarding the following
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four related items:
- 1) A minimum set of plant status / safety parawters which should be available for display;
- 2) Unique characteristics, if any, of the parameter sets to be displayed at various locations (i.e., Safety Parameter Display console, Technical Support Center, NRC Operations Center, etc.);
- 3) Should INPD or a reactor vendor be tied in to any of the parameter displays;
- 4) The display capability (i.e., CRT, on-line typewriter, high speed printer, etc.) and the analytic / processing capability required at each location, including the NRC Operations Center.
Please provide your recomendations May 30, 1980.
/
k Harold R. Denton, Director Edse Office of Nuclear Reactor Regulation,
As stated cc:
B. Grimes D. Eisenhut S. Hanauer D. Ross B. Snyder R. Vollmar 8006160 2 3 5
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Atomic indu: trill Forum, Inc.
7101 Wisconsin Avenue WasNngton. D.C. 20014 i
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April 23. 1980 l
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Mr. Harold Denton Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Division Washington, D.C.
20555
Dear Harold:
The AIF Policy Committee on Follow-Up to the Three Mile Island Accident has formed a Subcommittee.on Safety Parameter Integra-tion, under the chairmanship of Stephen Howell of Consumers Power Company and vice-chairmanship of Warr'en Owen of Duke Power Company.
This Subcommittee will:
Oversee and coordinate current industry efforts on the content, display, use, and transmission of safety parameter information; Articulate the philosophy behind and the goals to be achieved in the activities directly related to safety parameter development and use; and
- Provide a focal ?oint for generic discussions with NRC on the approaches to be used in response to pro-posed NRC requirements on these issues.
At its first aceting on April 17, 1980, the Subcommittee reviewed the efforts underway by NSAC, the Owners Groups, and IEEE and ANS on the following issues:
Safety Parameter Display Console; Control Room Design Reviews; Technical Support Center; Emergency Operations Center; Nuclear Data Link; ring; and DUPLICATE DOCUMENT
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May 2, 1980
/ I F-uuu Mr. Harold (
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- Director, ff'ce of Nuclear Reactor Regulation U.S. Nucloar egulatory Commission Washingtor
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Dear Mr. Denton:
In the April 23 letter to you from Byron Lee, Jr., Chairman of the AIF Policy Committee on Follow up to the Three Mili Island Accident, we outlined the activities of our Subcommittee on Safety Parameter Integration.
As indicated in the letter, we proposed a meeting with an appropriate NRC management group to discuss:
(1)
A fundamental safety parameter set, (2)
Functional definitions of NRC Action Plan items related to data display and evaluation, and (3)
A coherent sequencing schedule for implementing these items.
To facilitate the discussion at the meeting which is presently scheduled for 9:00am May 20, I a eniilosing a draft imple-mentation plan / milestone cnart for your review prior to the meeting.
We have developed reference dates for these steps that are under review and expect to have proposed dates i
available at the meeting.
A principal feature is a two-path program at the outset, which separates the parameter selection process from hardware considerations.
As background information, our Subcommittee on Safety Parameter Integration met in Chicago on April 17 and prepared draft functional definitions and a draft implementation plan which involve the fundamental safety parameters and the different related uses of this information.
4t our meeting, there was general agreement on the need and value of a simple, integrated system for data acquisition and display needs that could be used in a safety panel or its equivalent; and with supplemental infor-mation, in the Technical Support Center (TSC);
possibly the Emergency Operations Center IEOC);
and the Nuclear Data Link (NDL) if it becomes a requirement.
It was agreed that the priorit fpgManrem
' cation for such system should be ar irst in the interest of helping s should incorporate the same e implementation plan has been DUPLICATE DOCUMENT ind.
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