ML19320B659
| ML19320B659 | |
| Person / Time | |
|---|---|
| Issue date: | 07/01/1980 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Ahearne J NRC COMMISSION (OCM) |
| Shared Package | |
| ML19320B660 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8007140572 | |
| Download: ML19320B659 (2) | |
Text
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fpN UNITED STATES t'A [f Rg i,
.hg NUCLEAR REGULATORY COMMisslON WASHINGTON. D. C. 20555 e
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THIS DOCUMENT CONTMNS y
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_ _ _J POOR OUAUTY PAGES MEMORANDUM FOR: Chairman Ahearne Acting Executive Director Ib7:hT. A.Rehitif J illiam J. Dircks 7-THRU:
erations FROM:
Harold R. Denton, Director Office of Nuclear Reactor Regulation
SUBJECT:
NSAC BRIEFING Coranents on the two points raised in your June 12, 1980 memo follow.
Point (1) possible use of the utility load dispatch microwave links to insure communication between NRC and a plant.
Comment The possibility of using the utility load dispatch microwave systems for communication has always been considered as a backup to the normal NRC-to-site telephone system. The Office of Administration is currently evaluating the use of the load dispatch links as part of an overall evaluation of the NRC needs for site and regional conmunication. The Office of. Inspection and Enforcement is developing a list of utility load dispatcher telephone numbers for use in the.NRC Operations Center, so that messages could be relayed through the load dispatchers if necessary.
Point
"(2),the role of Reg Guide 1.97 in determining the safety vector" Ccmment The staff intent is to derive, to the extent practical and necessary, the
- list of parameters for the Safety Parameter Display (the " safety vector") '
as well as the onsite Technical Support Center, the near-site Emergency Operations Facility and the Nuclear Data Link from those to be required by Regulatory Guide 1.97. The variables for the Safety Parameter 80 0 7:140 Sp2
Chairman Ahearne 2
Display (SPD) may not, however, be limited to a subset of those in Reg. Guide _1.97.
Rather, th>
are to be selected by the licensee based on analyses which demonstrate that the display will be responsive to transient and accident sequences for a part;cular plant. Thus, some of the SPD variables may oe different for different plants.
The SPD, TSC, EOF, NDL are inextricably related. This relationship will be described in detail when the staff presents its discussion of the NDL to the Commission next month. A draft of the functional specifications for these various elements is attached. A refined version will be supplied with the NDL paper due to reach the Commission around July 1.
HaroldR.Dbnton, Director Office of Nuclear Reactor Regulation
Enclosure:
Draft of Functional Specifications cc: Commissioner Gilinsky Comissioner Kennedy Commissioner Hendrie Commissioner Bradford 4
Secretary OPE OGC 4
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