ML19330B969
| ML19330B969 | |
| Person / Time | |
|---|---|
| Issue date: | 07/21/1980 |
| From: | Zech G Office of Nuclear Reactor Regulation |
| To: | Fraley R Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-R-0876, ACRS-R-876, NUDOCS 8008070320 | |
| Download: ML19330B969 (2) | |
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?i MEMORANDUM FOR:
R. Fraley, Director j
Advisory Committee on Reactor Safeguards l
FROM:
Gary G. Zech, Technical Assistant
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Technical Assistant Branch t
Planning and Program Analysis Staff l
Office of Nuclear Reactor Regulation
SUBJECT:
NEAR-TERM CONSTRUCTION PERMIT APPLICATIONS t
i By letter dated May 6,1980, the ACRS provided its comments and recommenda-i tions regarding the status of applications for near-term construction permits (NTCPs). ' The staff expects that in the near future it will present
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to the Commission a paper on its proposed policy for proceeding with pending construction permit and manufacturing license applications. The ACRS comments have been considered by the staff in the development of the paper. Once a policy has been approved, the staff will issue a NUREG i
report on the subject. Copies of the Commission Paper and'NUREG will be provided to the ACRS as soon as they are available.
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Honorable John F. Ahearne Chairman U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
NEAR-TERM CONSTRUCTION PERMIT APPLICATIONS
Dear Dr. Ahearne:
During its 241st meeting, May 1-3, 1980, the ACRS reviewed the status of applications for near-term construction permits (NTCPs).
In its review the Committee had the benefit.of discussions with the NRC Staff and with repre-sentatives of the applicants for the NTCPs. A subcommittee meeting on this subject was held on April 9,1980.
The six NTCP applicants and the reactor types involved are as follows:
Black Fox Station, Units 1 and 2, Public Service Company of Oklahoma, General E'ectric BWR/6, Mark III pressure suppres-sion containment Skagit Nuclear Power Project, Units 1 and 2, Puget Sound Power
& Light Company, General Electric BWR/6, Mark III pressure suppression containment Pilgrim Station, Unit 2, Boston Edison Company, Combustion Engineering custom NSSS, large dry containment Perkins Nuclear Station Units 1, 2 and 3, Duke Power Company, Combustion Engineering CESSAR System 80 NSSS, large dry con-tainment Allens Creek Nuclear Generating Station, Houston Lighting &
Power Company, General Electric BWR/6, Mark III pressure sup-pression containment w-Pebble Springs NJclear Plant, Units 1 and 2, Portland General Electric Company, Babcock and Wilcox custom NSSS, large dry containment The NRC Staff has approached this matter primarily by examining the Action Plan and judging the applicability and scheduling of each item to an NTCP.
This' procedure has resulted in placing many important items in a category wherein the NRC has yet to develop criteria applicable to construction per-Action Plan item II. A on siting introduces questions whose mit applicants.
resolution must be achieved prior to issuance of a construction permit.
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' ". HcnorabTe fohn F. Ahearne' May 6, 1980 Item II.B on degraded or melted cores bears directly on containment design, as well as other safety features.
Item II.C on reliability engineering and risk assessment could bear significantly on the design requirements for many important plant systems.
There are many other items in the Action Plan and in the ACRS report of April 17, 1980 which also might impact directly on im-portant design aspects of these plants.
Mr. Harold Denton advised the Committee that he envisaged permitting con-struction to proceed if there are no obvious site-related questions in terms of the Report of the Siting Policy Task Force (NUREG-0625) and if the contain-ment design pressure were such as to withstand hydrogen combustion, on the assumption that other design aspects could be changed later if so required.
The utility representatives advise'd the ACRS that, in their cpinion, there was a need for the resolution of several policy questions which relate to how and whether cdnstruction permit applications will be processed in the near term.
The utilities identified the following six policy issues as being in most urgent need of resolution:
1.
Siting 2.
Emergency planning 3.
Degraded core conditions 4.
Control room design 5.
Management for design and construction 6.
Reliability and risk assessment The utility representatives recommended that a concerted effort be under-taken to develop an acceptable interim approach to resolution by the Commis-sion of such issues in.the next few months. The ACRS supports this recom-mendation and urges that appropriate Staff resources be made availa.ble for~
this purpose.
An ACRS Subcommittee plans to work actively with the Staff on the topic with the anticipation that the full Committee would review the NTCP matter within a few months.
Sincerely, ed h
Milton S. Plesset Chairman
References:
l.
Memorandum from D. F. Ross, NRC, to R. F. Fraley, ACRS,
Subject:
Trans-mittal of.NTCP Requirements 1.ist, dated April 22, 1980.
2.
Memorandum from William F. Kane, NRC, to Addressees,
Subject:
Request for Review of Proposed TMI-2-Related Requirements for NTCP Applicants, dated April 4, 1980.
3.
U. S. Nuclear Regulatory Commission, "NRC Action Plans Developed as a Result of the TMI-2 Accident," USNRC Report NUREG-0660 Draft 3, dated March 5,1980.
4.
U. S. Nuclear Regulatory Commission, " Report of the Siting Policy Task Force," USNRC Report NUREG-0625, dated August,1979.
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