ML20202G713
| ML20202G713 | |
| Person / Time | |
|---|---|
| Site: | 05000128 |
| Issue date: | 07/11/1986 |
| From: | TEXAS A&M UNIV., COLLEGE STATION, TX |
| To: | |
| Shared Package | |
| ML20202G702 | List: |
| References | |
| NUDOCS 8607160074 | |
| Download: ML20202G713 (10) | |
Text
m
. 3.6.2 Material Limitations '
Applicability O
- This specifitation applies to experiments installed in the reactor and its experimental facilities.
Obiective .
, The objective is to prevent da= age to the reactor or excessive relea ce of radioactivity by limiting material quantity and radioactive material inventory of the experiment.
Specifications -
. (a) ' Explosive ma'terials in quantitics greater than 5 pounds shall not be allowed within the reactor building.
Irradiation of explosive materials shall be restricted as follows:
(1) Explosive materials in quantities greater than 25 milligrams.shall not be irradiated in the reactor pool. Explosive materials in quantities less than t']:
z_ 25 milligrams may be irradiated providad the pressure produced upon detonation of the explosive has been calculated and/or experimentally demonstrated to be less than the design pressure of the container.
(2) Explosive materials in quantities greater than 25 milligrais shall be restricted from the reactor .
pool, the upper research level, decineralizar
, room, cooling equipment room and the interior of the pool containment structure.
- ' I (3) Explosive materials in quantities greater than 5 pounds shall not be irradiated in experimental f acilities; *
(4) Cumulative exposures for explosive materials in !
quantities greater than 25 milligrams shall not exceed 1012 n/cm2 for neutrons or 25 roentgen for S gamma exposures.
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' .(b)
Each fualed experiment shall be controlledatsuch the th total inventopy of iodine isotopes 131 through 135 in
() '
Bases the experiment is no greater than l 5 curies.. .
(a)
This specification,is ince'nded to prevent damage o the t
reactor or reactor safety systems resulting from a ure f il of an experiment involving explosive materials .
(1)
This specification is intended to prevent damage o t the reactor core and safety related reactor components located within the reactor, pool in the event of
, failure of an experiment involving the irradiation of explosive materials.
Limited quantities of less than 25 milligrams and proper containment of such experiment provide the required safety for in pool irradiation.
(2)
This specification is intended to prevent dam age to vital equipment by restricting the quantity and c- location of explosive materials within the re G) building. ac tor Explosives in quantities c2 :eeding 15 silligrams are restricted from areas containi ng :he reactor bridge, reactor console, pool water coolr.nt and purification systecs and reactor safety equipment. ated rel (3)
.' Tne failure of an experiment involving the i
. rradiation of up to 5 lbs of explosive material in an expe,ri-mental facility located external to the reactor pool structure will not result in damage to the r ~
eactor or the reactor pool containment structure .
(4)
This specification is intended to prevent any increase in the sensitivity of explosive m ,
, aterials
~
~ due to radiation damage during exposures .
(b)
The 1.5 curie limitation on iodine 131 that in the event of failure of a f through 135 assures
-s to total release of the iodine ueled experiment. leading 10 CFR Partexclusion area boundary , the exposure dose will be lessatthathe e
20 for an unrestricted area. n that allowed by
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3.6.3 Failura end Palfunctions
, Apolicability .
Q.
This specification applies to experiments installed in the .
reactor and its experimental facilities.
Obiective . .
. The objective is to prevent damage to the reactor or excessive
. release of radioactive materials in the event of an experiment failure.
Specifications (a) Experiment materials, except fuel materials, which could off-gas,. sublime, volatilize, or' produce aerobols under (1) normal operating conditions of the experiment or reactor, (2) credible accident conditions in the reactor, or -(3)'possible uccident conditions in the experiment shall be limited in activity such that if 100% of the i gaseous activity or radioactive aerosols produced escaped to the- reactor room or the at'mosphere, the air-i; j borne concentration of radioactivity averaged over f year would not exceed the limit of /.ppendix B of 10 CFR Part 20.
(b) In calculations pursuant to (a) above, the following .
assumptions shall be used:
(1) If the ef fluent from an experimental facility in exhausts through a holdup tank which closes automatically on high radiation level, at least
, 10% of the gaseous activity orfaerosola produced
. . will escape.
(2) If the effluent fras e ; e?. erimental facility 4
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exhausts through a .116.e 2nstallation designed,for
, greater than 99% efficiency for'O.3 micron particles. -
, at least 10% of these vapors can escape..
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(3) For . materials whose boiling point io abova 130 F and where vapo'rs formed by boiling this caterial can escape only through an undistributed colu=n of water above the core, at least 10% of these vapors can escape. .
(c) If a capsule fails and releases material which could damage the reactor fuel or structure by corrosion or other means, removal and physical inspection'shall be perfor=cd to determine the consequences and need for corrective action.
The results of the inspection and any corrective action taken shall .be reviewed by the Director or his designated alternate and determined to be catisfactory before operation of the reactor is resumed.
B as es (a) This specification is intended to reduce the likelihood that airborne activities in excess of the limit's of Appendix B of 10 CFR Part 20 will be released to the atmosphere outside the facility boundary'of the NSC.
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(b) These assumptions are used to evaluate the potential airborne radioactivity release due to an experiment failure.
(c) Operation of the reactor with reactor fuel or structure damage is prohibited to avoid release of fission products. Potential damage to reactor fuel or b
, structure must be brought to the attention of the Director (NSC) or his designated alternate for review to assure safe operation of the reactor.
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