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Title: Reactor Accident Analysis Methodology for the Advanced Test Reactor Critical Facility Documented Safety Analysis Upgrade

The regulatory requirement to develop an upgraded safety basis for a DOE nuclear facility was realized in January 2001 by issuance of a revision to Title 10 of the Code of Federal Regulations Section 830 (10 CFR 830).1 Subpart B of 10 CFR 830, “Safety Basis Requirements,” requires a contractor responsible for a DOE Hazard Category 1, 2, or 3 nuclear facility to either submit by April 9, 2001 the existing safety basis which already meets the requirements of Subpart B, or to submit by April 10, 2003 an upgraded facility safety basis that meets the revised requirements.1 10 CFR 830 identifies Nuclear Regulatory Commission (NRC) Regulatory Guide 1.70, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants”2 as a safe harbor methodology for preparation of a DOE reactor documented safety analysis (DSA). The regulation also allows for use of a graded approach. This report presents the methodology that was developed for preparing the reactor accident analysis portion of the Advanced Test Reactor Critical Facility (ATRC) upgraded DSA. The methodology was approved by DOE for developing the ATRC safety basis as an appropriate application of a graded approach to the requirements of 10 CFR 830.
Authors:
;
Publication Date:
OSTI Identifier:
911287
Report Number(s):
INEEL/CON-03-00048
TRN: US0704511
DOE Contract Number:
DE-AC07-99ID-13727
Resource Type:
Conference
Resource Relation:
Conference: Energy Facility Contractors Group (EFCOG) Safety Analysis Working Group (SAWG) 2003 Annual Meeting,Salt Lake City, UT,06/21/2003,06/27/2003
Research Org:
Idaho National Laboratory (INL)
Sponsoring Org:
DOE - NE
Country of Publication:
United States
Language:
English
Subject:
12 - MGMT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES, 21 - SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS, 22 - GENERAL STUDIES OF NUCLEAR REACTORS; ATRC REACTOR; CONTRACTORS; NUCLEAR POWER; REACTOR ACCIDENTS; REGULATIONS; REGULATORY GUIDES; SAFETY; SAFETY ANALYSIS methodology; safety analysis