ML20049A934
| ML20049A934 | |
| Person / Time | |
|---|---|
| Site: | Armed Forces Radiobiology Research Institute |
| Issue date: | 09/30/1981 |
| From: | Bachmann R NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | CITIZENS FOR NUCLEAR REACTOR SAFETY, INC. |
| Shared Package | |
| ML20049A939 | List: |
| References | |
| NUDOCS 8110020391 | |
| Download: ML20049A934 (2) | |
Text
09/30/81 9
d O
f UNITED STATES OF AMERICA 3
NUCLEAR REGULATORY COMMISSION f[
6
.e]
Ocq BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
ARK J FORCES RADI0 BIOLOGY RESEARCH )
Docket No. 50-170 INSTITUTE
)
(Renewal of Facility
("
g
)
License No. R-84)
(TRIGA-Type Research Reactor)
)
NRC STAFF REQUEST FOR ADMISSIONS BY INTERVENOR CNRS The NRC Staff hereby requests that the Intervenor Citizens for Nuclear Reactor Safety (CNRS), pursuant to 10 C.F.R. 6 2.742 and in accordance with the Atomic Safety and Licensing Board's Special 1/
Prehearing Conference Memorandum and Order of August 31, 1981, admit the truth of the following relevant matters of fact:
1.
In a fuel element cladding failure, the only significant source of fission products which could be released is that which has accumulated in the gap between the cladding and the fuel material.
2.
Only the noble gases (krypton and zenon) and iodine will migrate into the gap between the ft:el material and the fuel element cladding.
3.
For the AFRRI Design Basis Accidents, 0.1% of total fission product noble gases and iodine was assumed to have accumulated in the gap between the cladding and the fuel material.
1/
10 C.F.R. 5 2.742(b) provides, in pertinent part that "[e]ach requested admission shall be deemed made unless...the party to whom the request is directed serves on the requesting party...a sworn statement denying specifically the relevant matters of which an admission is requested or setting forth in detail the reasons why he can neither truthfully admit nor deny them.
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60 l ENO 8110020391 810930 j
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4.
The 0.1% of the fission product noble gases and iodine referred to in 3. above corresponds to a fuel temperature of approximately 600*C according to Reference 2 of the HSR.
5.
Both high flux safety channels are checked daily prior to reactor operation and operation is prohibited unless both channels are operable.
6.
During steady-state operation, the high flux safe +.v channels will scram +he reactor at 1.1 MW.
7.
The fuel temperature safety channels will scram the reactor at approximately 600*C, which corresponds to a steady-state power level considerably higher than 1.1 MW.
8.
The fuel material in the AFRRI TRIGA reactor is zirconium hydride alloyed with uranium.
9.
Tests of chemical reactivity, in which the alloy was plunged frem a high-temperature furnace directly into water, have failed to show any reaction other than surface discoloration.
(Nuclear Fuel Elements,
- p. 84).
- 10. The fuel element cladding is 304 stainless steel, nominally 0.02 inches thick.
Respectfully submitted, m
Richard G. Bachmann Counsel for NRC Staff l
l Dated at Bethesda, Maryland j
this 30th day of September, 1981 l
--.