ML20206J252
| ML20206J252 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte, 05000000 |
| Issue date: | 01/24/1986 |
| From: | Peterson A SANDIA NATIONAL LABORATORIES |
| To: | Agrawal B NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| Shared Package | |
| ML20204G644 | List:
|
| References | |
| RTR-NUREG-1150 NUDOCS 8704160053 | |
| Download: ML20206J252 (1) | |
Text
Sandia National Labaatches J
AlbuQuef Que, New Mexico 87185 JcnuSry 24, 1986
/ y.4 t
Dr. Bharat Agrawal Containment Systems Research Branch U.S. Nuclear Regulatory Commission 7915 Eastern Avenue Silver Spring, MD 20901
Dear Bharat:
As you requested, this letter transmits an early draft of the Executive Summary from the " Analysis of Station Blackout Accidents for the Bellefonte Pressurized Water Reactor" i
This report by R. D. Gasser, P. P. Bieniarz and J. A. Tills.
Executive Summary was slightly expanded (several tables of calculated results) from what may appear in the report so that it transmits a detailed summary of the calculated radiological releases.
As noted in the Summary, without direct heating from the injection of molten core debris into the containment environment, failure of the containment and subsequent radiological releases into the atmosphere are unlikely.
However, if more than 50% of the core is dispersed into and directly heats the containment environment, containment failure and radiological releases are likely.
The initial draft of the report is scheduled to be completed by March 15, 1986.
Very Truly Yours, m
A. c. Peterson Reactor Safety Technology Division 6411 Copy to:
NRC T. J. Walker 6411 P. N. Demmie TVA J. A. Raulston 6411 M. K. Fuentes TVA K. D. Keith, Jr.
6411 R. D. Gasser I
INEL R. J. Dallman 6412 A. L. Camp ORNL S. A. Hodge 6415 F. E. Haskin SEA C. J. Shaffer 6415 S. E. Dingman SAI L. N. Smith 6427 J. T. Hitchcock BCD R. S. Denning 6427 C. C. Wong UofW G. Moses 6442 W. A. von Riesemann 6410 J. W. Hickman 6444 J. M. McGlaan 6411 A. S. Benjamin 6445 D. B. King 6449 K. D. Bergeron 8704160053 B70400 l
PDH NUREG 1150 C PDR
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