ML19323C472
| ML19323C472 | |
| Person / Time | |
|---|---|
| Site: | 05000514, 05000515, 05000471, Allens Creek, Perkins, Skagit, Black Fox File:Houston Lighting and Power Company icon.png |
| Issue date: | 05/06/1980 |
| From: | Plesset M Advisory Committee on Reactor Safeguards |
| To: | Ahearne J NRC COMMISSION (OCM) |
| References | |
| ACRS-R-0877, ACRS-R-877, NUDOCS 8005150676 | |
| Download: ML19323C472 (2) | |
Text
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NUCLEAR REGULATORY COMMISSION
/.- c ADVISORY COMMITTEE ON REACTOR SAFEGUARDS g
WASHINGTON, D. C. 20555 0,%,*****/
May 6,1980
$O-4 N 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 Electric 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 Perkin: 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 Pebble Springs Nuclear 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-mit applicants. Action Plan item II. A on siting introduces questions whose resolution must be achieved prior to issuance of a construction permit.
O Honorable John 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 itens 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 olants.
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 advised the ACRS that, in their opinion, there was a need for the resolution of several policy questions which relate to how and whether construction 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 available 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, Milton S. Plesset Chairman
References:
1.
Memorandum from D. F. Ross, NRC, to R. F. Fraley, ACRS,
Subject:
Trans-mittal of NTCP Requirements List, 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 Comm'. ion, "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.