ML19260C617
| ML19260C617 | |
| Person / Time | |
|---|---|
| Issue date: | 11/14/1978 |
| From: | Fouchard J NRC OFFICE OF PUBLIC AFFAIRS (OPA) |
| To: | Gilinsky V, Hendrie J, Kennedy R NRC COMMISSION (OCM) |
| References | |
| REF-GTECI-A-08, REF-GTECI-CO, TASK-A-08, TASK-A-8, TASK-OR NUDOCS 8001080122 | |
| Download: ML19260C617 (3) | |
Text
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7 UNITED STATES g/
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WASHINGTON, D. C. 20555 (j
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q,3 MEMORANDUM FOR:
Chairman Hendrie Commissioner Gilinsky Commissioner Kennedy Commissioner Bradford Commissioner Ahearne FROM:
Joseph J.
Fouchard, Director Office of Public Affairs
SUBJECT:
PUBLIC ANNOUNCEMENT OF REPORT ON CONTAINMENT SYSTEMS Enclosed is the text of a public announcement that the staff has issued a report describing acceptable methods fo r analyzing the performance of Mark II type presure suppression containment systems.
The announcement text has been approved by the Director of the Office of Nuclear Reactor Regulation, and we plan to issue it on Friday, November 17.
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Joseph J.
Fouchard, Director Office of Public Affairs
Enclosure:
Public Announcement cc:
SECY J.
Kelley, OGC C.
Kammerer, OCA L.
R.
Mattson, NRR C.
Long, NRR 1701 060 80 010 8o I DA.
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UNITED STATES
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OFFICE OF PUBLIC AFFAIRS WASHINGTON, D.C. 20555 No.
78-FOR IMMEDIATE RELEASE
Contact:
Frank Ingram (Mailed - November 17, 1978)
Tel.
301/492-7715 NRC STAFF ISSUES REPORT RELATED TO CONTAINMENT SYSTEMS The staff of the Nuclear Regulatory Commission has published a report describing acceptable methods for analyzing the performance of Mark II type pressure suppres-sion containment systems.
There systems are used with boiling water power reactors to assure plant safety.
The report marks an important milestone in one element of the Commission's technical activities program for resolving generic safety issues.
Pressure suppression containment systems consist of two vessels--a " dry well" containing the reactor and a " wet well,"
containing water.
In the case of a loss-of-coolant accident or discharges from safety relief valves, the resulting steam and air are vented from the " dry well" into the " wet well" to reduce the pressure inside the containment.
However, the rapid discharge of air and steam into the pool of water creates forces which the pool and related piping and other equipment must be designed to withstand.
At present there are 11 plants under construction which will use General Electric Company reactors with the Mark II pressure suppression containment systems.
The NRC staff's report evaluates the methods used by owners of these facilities to calculate the forces resulting from rapid discharges of steam and air into the " wet well,"
the methods which the staff finds acceptable for use in individual Safety Analysis Reports, and the basis for the staff's conclusions.
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During its safety review of individual applications to operate these fr.cilities, the staff will use the methods described in the report to evaluate the ability of each containment system to withstand the maximum calculated forces resulting from a loss-af-coolant accident or the opening of safety relief valves.
The report is titled " Mark-II Containment, Lead Plant Program, Load Evaluation and Acceptance Criteria Report" and is identified as NUREG-0487.
Copies may be purchased at the National Technical Information Service, Springfield, Virginia 22161 in about two weeks.
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