Enclosure 3
REFERENCE PUBLICATIONS
Section 1
- Regulatory Guide 1.70, Rev. 3, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants"
Section 2
- Regulatory Guide 1.21, Rev. 1, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants"
- Regulatory Guide 4.1, Rev. 1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants"
Section 8
- Regulatory Guide 2.6, Rev. 1, “Emergency Planning for Research and Test Reactors”
Section 15
- Regulatory Guide 1.28, Rev. 3, "Quality Assurance Program Requirements (Design and Construction)”
- Regulatory Guide 1.33, Rev. 2, “Quality Assurance Program Requirements (Operation)”
Section 18
- Regulatory Guide 1.99, Rev. 2, "Radiation Embrittlement of Reactor Vessel Materials"
Section 19
- Regulatory Guide 1.99, Rev. 2, "Radiation Embrittlement of Reactor Vessel Materials"
Section 23
- Regulatory Guide 1.160, Rev. 2, “Monitoring the Effectiveness of Maintenance at Nuclear Power Plants”
- Regulatory Guide 1.182, “Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants”
Section 24
- Regulatory Guide 1.162, “Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels”
Section 33
- Regulatory Guide 1.174, Rev. 1, “An Approach for Using Probabalistic Risk Assessment in Rick-Informed Decisions on Plant-Specific Changes to the Licensing Basis”
- Regulatory Guide 1.175, “An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing”
- Regulatory Guide 1.176, “An Approach for Plant-Specific, Risk-Informed Decisionmaking: Graded Quality Assurance”
- Regulatory Guide 1.177, “An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications”
- Regulatory Guide 1.178, Rev. 1, “An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Inspection of Piping”
- Regulatory Guide 1.201, “Guidelines for Categorizing Structures, Systems and Components in Nuclear Power Plants According to Their Safety Significance”
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