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Minor Revision of Design Basis Accident Dose Limits for Independent Spent Fuel Storage and Monitored Retrievable Storage Installations

nuclear-waste · Nuclear Regulatory Commission · Published 1998-10-13 · 63 FR 54559

Document

Document number
98-27349
Federal Register citation
63 FR 54559
CFR reference
10 CFR 72
Type
Rule
Action
Final rule.
Category
nuclear-waste
Sub-agency
Nuclear Regulatory Commission
Publication date
1998-10-13

Abstract

The Nuclear Regulatory Commission (NRC) is amending its regulations governing the dose limits and the dose calculational methodology used in design basis accident analyses for Independent Spent Fuel Storage Installations (ISFSIs) and Monitored Retrievable Storage Installations (MRS). This final rule amends ISFSI and MRS design basis accident dose limits to conform to the dose calculational methodology currently used in the regulations that specify standards for protection against radiation and make a minor change to match the Environmental Protection Agency's (EPA) regulations. This action will ensure that limits for design basis accidents at ISFSI and MRS installations are consistent with the dose methodology specified in NRC radiation protection regulations, and will allow licensees the flexibility provided by that dose methodology when performing design basis accident analyses.

Source

Authoritative
Federal Register document
Machine
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