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|  DOE-STD-101-92
Regulatory Guide 3.54, "Spent Fuel Heat Generation
C.
in an Independent Spent Fuel Storage Installation."
Codes and Standards
4.4.3
ANSI/ANS 57.7-1988, "Design Criteria for an Inde-
A.
pendent Spent Fuel Storage Installation (Water-Basin Type)."
ANSI/ASME B31.1-1989, "Power Piping."
B.
"Thermosetting Fiberglass-
C.
ANSI/AWWA D120-1984,
Reinforced Plastic Tanks."
ANSI/ASME OM-1987, "Operation and Maintenance of
D.
Nuclear Power Plants," Part 2 - "Requirements for Performance
Testing of Nuclear Power Plant Closed Cooling Water Systems."
Appropriate Codes and Standards listed in Section
E.
3.3.3.
4.4.4
Supplementary Information
A.
Background Information.
1.
LA-8230-MS, "Heat Pipe Cooling System for
Underground Radioactive Waste Storage Tanks," Cooper, K.C. et
al., Los Alamos National Laboratory, February 1980.
2.
HEDL-TME-78-37, "Maximum Allowable Temperature
for Storage of Spent Nuclear Reactor Fuel, an Interim Report,"
Blackburn, L.D., et al., Hanford Engineering Development
Laboratory, May 1978.
Generic Letter 89-13, "Service Water System
3.
Problems Affecting Safety-Related Equipment," USNRC, July 1989.
Criteria for safety-related process systems or portions
of process systems are identified in this section.
Code of Federal Regulations
4.5.1
10 CFR 60.135, "Criteria for the Waste Package and
A.
its Components."
10 CFR 61.55, "Waste Classification."
B.
10 CFR 61.56, "Waste Characteristics."
C.
4-10
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