The Engineering Test Reactor Critical Facility Hazards Summary Report
Title | The Engineering Test Reactor Critical Facility Hazards Summary Report PDF eBook |
Author | D. R. DeBoisblanc |
Publisher | |
Pages | 110 |
Release | 1958 |
Genre | Engineering test reactors |
ISBN |
The Engineering Test Reactor Critical Facility Hazards Summary Report
Title | The Engineering Test Reactor Critical Facility Hazards Summary Report PDF eBook |
Author | D. R. DeBoisblanc |
Publisher | |
Pages | 96 |
Release | 1958 |
Genre | Engineering test reactors |
ISBN |
Advanced Test Reactor Critical Facility Safety Analysis Report
Title | Advanced Test Reactor Critical Facility Safety Analysis Report PDF eBook |
Author | E. E. Burdick |
Publisher | |
Pages | 90 |
Release | 1964 |
Genre | Nuclear reactors |
ISBN |
Reactor Accident Analysis Methodology for the Advanced Test Reactor Critical Facility Documented Safety Analysis Upgrade
Title | Reactor Accident Analysis Methodology for the Advanced Test Reactor Critical Facility Documented Safety Analysis Upgrade PDF eBook |
Author | R. T. McCracken |
Publisher | |
Pages | |
Release | 2003 |
Genre | |
ISBN |
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 acontractor 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.110 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 thatwas 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.
TID.
Title | TID. PDF eBook |
Author | |
Publisher | |
Pages | 252 |
Release | 19?? |
Genre | Energy development |
ISBN |
Final Hazards Summary Report to the Advisory Committee on Reactor Safeguards on a Research Reactor for the Massachusetts Institute of Technology
Title | Final Hazards Summary Report to the Advisory Committee on Reactor Safeguards on a Research Reactor for the Massachusetts Institute of Technology PDF eBook |
Author | Theos Jardin Thompson |
Publisher | |
Pages | 156 |
Release | 1956 |
Genre | Nuclear reactors |
ISBN |
Hazards Summary Report for Operation of the 630A Maritime Reactor Critical Experiment at the Low Power Test Facility
Title | Hazards Summary Report for Operation of the 630A Maritime Reactor Critical Experiment at the Low Power Test Facility PDF eBook |
Author | General Electric Company |
Publisher | |
Pages | 157 |
Release | 1962 |
Genre | Nuclear merchant ships |
ISBN |