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AOL 4
BASIS
(cont’d)
NOTE:
Revision 1.
.%vtcmher 1993
The FSAR Safety Analysis made the following assumptions dealing with SNM
containers which are not part of this AOL requirement:
Contain 6,000 grams (WG Pu equivalent) of oxide or 2,000 grams (WG Pu
equivalent) of metal.
POC and waste container radioactive material loading is credited in the evaluation of
postulated facility fire, spill, puncture, container explosion, and facility explosion
accident scenarios. N-: SNM container radioactive material loading is credited in
the evaluation of postulated material frre and puncture accident scenarios.
WG Pu equivalent radioactive material considers the higher dose consequences
associated with accidents involving americium in concentrations greater than that
expected from ingrowth due to the decay of 241Pu. The formula for calculating
WG l?u equivalency is:
WG PU equivalency (in grams) = WG Pu (in grams) + 66*Am (in grams)
This formula should only be used for waste containers containing more than
approximately 0.3% americium in the radioactive material content. If the radioactive
material contains less than 0.3% americium, the americium content is consistent with
the natural ingrowth of americium in WG h.
In order to restrict highly radioactive material containers from the BUILDING 991
COMPLEX, verifkation of every POC and waste container brought into the facility
for compliance with the requirement is specified. The compliance verification can
occur at time of receipt or at the container originating facility prior to shipment by
examination of container. In addition, a general verification of POC and waste
container radioactive material content is specified for identification of high
radioactive material containers during facility operations. This latter verification is
only expected to examine container inventories during routine reading of container
databases or to examine container inventories when attempting to locate a specific
container. This latter verification is not expected to fmd highly radioactive material
content containers due to the numerous checks made before a container is stored in
the BUILDING 991 COMPLEX.
Movement of highly radioactive material containers is not exempted from any
requirements that may be placed on the containers by Criticality Safety. If the
container is infracted under the Criticality Safety Program, removal of the container
is subject to the requirements of that program.
A-117 Building 991 Complex FSAR
Appendix A