ML20137D259
| ML20137D259 | |
| Person / Time | |
|---|---|
| Site: | Indian Point |
| Issue date: | 08/09/1985 |
| From: | Felton J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Sholly S UNION OF CONCERNED SCIENTISTS |
| Shared Package | |
| ML20136F845 | List: |
| References | |
| FOIA-85-448, RTR-NUREG-1116 NUDOCS 8508220438 | |
| Download: ML20137D259 (2) | |
Text
s.
gf o,,
UNITED STATES NUCLEAR REGULATORY COMMISSION 3
o O
p WASHINGTON, D. C. 20555
%,*****/
AUG 0 S 1985 Mr. Steven C. Sholly Technical Research Associate Union of Concerned Scientists 1346 Connecticut Avenue, NW, Suite 1101 IN RESPONSE REFER Washington, DC 20036 TO F01A-85-448
Dear Mr. Sholly:
This is in further response to your letter dated June 21, 1985, in which you requested, pursuant to the Freedom of Information Act (F0IA), all records concerning the probabilities, consequences, impacts and magnitudes of.
in-vessel /ex-vessel steam explosions occurring during core meltdown accidents at light water reactor power plants.
The enclosed Appendix B identifies four additional records responsive to your request. These records are being placed in the NRC's Public Document Room in file folder F01A-85-448 for your inspection and copying.
This completes NRC's action on your request.
Since ely, s
J. M. Felton, Director Division of Rules and Records Office of Administration
Enclosure:
As stated 8508220438 850809 PDR.FDIA SHOLLY85-448 PDR
}
e Re:
F01A-85-448 APPENDIX B e
1.
03/07/85 Memo for Chairman Palladino, et. al., from William J.
Dircks re: STATUS OF CURRENT ACTIVITIES REGARDING REVIEW 0F THE P0TENTIAL FOR CONTAINMENT FAILURE FROM IN-VESSEL STEAM EXPLOSIONS DURING CORE MELT ACCIDENTS IN LWRS.
(3 pages) 2.
04/19/85 Memo for James Meyer from T. A. Rehm re: ADDITIONAL INFORMATION ON STEAM EXPLOSIONS, (2 pages) 3.
04/?5/85 Memo for William J. Dircks from James K. Asselstine re:
STEAM EXPLOSIONS.
(1 page) 4.
06/18/85 Memo for Commissioner Asselstine from William J. Dircks re:
STEAM EXPLOSIONS w/ enclosures:
(1) Response to Questions Group Members; (3) plosions; (2) List of Steam Explosion Review Regarding Steam Ex Executive Summary for NUREG-1116; (4) List of Some Published Material on Steam Explosion Phenomena; (5) Statement of Work Describing Program on Analysis of Steam Explosion Uncertainties; and (6) Topical Note on Reassessment of TMI-2 Core Damage.
I i
i l
l l
s