Supplementary Information

DOE-STD-101-92

ANSI/ANS 6.1.2-1989, "Neutron and Gamma-Ray Cross

Sections for Nuclear Radiation Protection Calculations for

Nuclear Power Plants."

ANSI/ANS 6.4-1985, "Guidelines on the Nuclear Anal-

ysis and Design of Concrete Radiation Shielding for Nuclear Power

Plants."

"Specification for Radiation

ANSI/ANS 6.4.2-1985,

Shielding Materials."

ANSI/ANS 8.3-1986, "Criticality Accident Alarm Sys-

tem."

ANSI N2.3-1979, "Immediate Evacuation Signal for

Use in Industrial Applications."

Supplementary Information

8.2.4

ERDA 76-21, "Nuclear Air Cleaning Handbook," Bur-

chsted, C.A., Kahn, J.E., and Fuller, A.B., Oak Ridge National

Laboratory, March 31, 1976.

NCRP Report No. 49, "Structural Shielding Design

and Evaluation for Medical Use of X-Rays and Gamma-Rays of

Energies up to 10 MeV," National Council on Radiation Protection

and Measurements.

Schaffer, N.M., Ed., "Reactor Shielding for Nuclear

Engineers," USAEC, 1973.

BNWL-SA-3139, "The Effects of Radiation Levels from

Plutonium on

Fuel Fabrication Process Design," Faust, L.G.,

and Van Tuyl, H.H., Battelle Pacific Northwest

Smith, R.C.,

Laboratories,

1970.

8.3

8.3.1

Code of Federal Regulations

10 CFR 20.102, "Determination of Prior Dose."

10 CFR 20.202, "Personnel Monitoring."

10 CFR 61.12, "Specific Technical Information."

10 CFR 61.13, "Technical Analyses."

"Controlled Area of an ISFSI or

10 CFR 72.106,

MRS."

8-5