LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 11, Radioactive Waste Management, Table of Contents

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Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 11, Radioactive Waste Management, Table of Contents
ML17046A491
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Site: Salem  PSEG icon.png
Issue date: 01/30/2017
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Public Service Enterprise Group
To:
Office of Nuclear Reactor Regulation
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LR-N17-0034
Download: ML17046A491 (7)


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Section 11.1 11.1.1 11.1.2 11.1.3 11.1.4 11.1.5 11 .. 1.5.1 11.1.5.2 11.1.5 .. 2 .. 1 11.1.5 .. 2 .. 2 11.1 .. 5.2.3 11.1.5.2.4 11 .. 1.5.2.5 11.1.5.2.6 11 .. 1.6 11.1.7 11.1.8 11.1.9 11.2 11.2.1 11.2.2 11.2.3 11.2.4 11.2.5 11.2.6 11.2.7 SGS-UFSAR SECTION 11 RADIOACTIVE WASTE MANAGEMENT TABLE OF CONTENTS SOURCE TERMS Determination of Activity in Reactor core Activities in the Fuel Rod Gap Fuel Handling Sources Reactor COolant Fission Product Activities Tritium Production General -overall sources Specific Individual Sources of Tritium Ternary Fissions -Clad Diffusion Tritium Produced from Boron Reactions Tritium Produced from Lithium Reactions Control Rod Sources 11.1-8 Tritium Production from Deuterium Reactions Total Tritium Sources Volume Control Tank Activity Gas Decay Tank Activity Activity in Recirculated Sump Water References for Section 11.1 LIQUID WASTE SYSTEM Design Objectives System Description System Design Operating Procedures Performance Tests Estimated Releases Release Points 11-i 11.1-1 11.1-1 11.1-1 11.1-3 11.1-4 11.1-6 11.1-6 11 .. 1-6 11.1-6 11.1-7 11.1-8 11.1-9 11.1-9 11.1-10 11.1-10 11.1-11 11.1-11 11.2-1 11.2-1 11.2-2 11.2-5 11.2-10 11.2-10a 11.2-11 11.2-12 Revision 16 January 31, 1998 Section 11.2.8 11.2.9 11.2.10 11.3 11.3.1 11.3.2 11.3.3 11.3.4 11.3.5 11.3.6 11.3.7 11.3.8 11.3.9 11.4 11.4.1 11.4.2 11.4.2.1 11.4.2.1.1 11.4.2.1.2 11.4.2.2 11.4.2.3 11.4.2.4 11.4.3 11.4.4 11.5 11.5.1 11.5.2 SGS-OFSAR TABLE OF CONTENTS (Cont) Dilution Factors Estimated Doses (Potential) Reference for Section 11.2 GASEOUS WASTE SYSTEM Design Objectives System Description System Design Operating Procedures Performance Tests Estimated Releases Release Points Dilution Factors Estimated Doses RADIOLOGICAL MONITORING Design Objectives Radiation Monitoring System Radiation Monitoring System Description Radiation Monitoring System -Unit 1 Radiation Monitoring System -Unit 2 Process Radiation Monitoring System Channel Description Process Filter Monitoring System Channel Description Area Monitoring System Channel Description Sampling Inservice Tests and Calibrations SOLID RADWASTE SYSTEM 11.5-1 Design Objectives System Design 11-ii 11.2-12 11.2-13 11.2-17 11.3-1 11.3-1 11.3-2 11.3-6 11.3-13 11.3-15 11.3-15 11.3-16 11.3-16 11.3-16 11.4-1 11.4-1 11.4-1 11.4-3 11.4-3 11.4-5 11.4-7 11.4-17 11.4-18 11.4-21 11.4-23 11.5-1 11.5-2 Revision 23 October 17, 2007

  • Section 11.5.3 11.5.4 11.5.5 11.5.6 11.5.7 11.5.8 11.6 11.6.1 11.6.2 11.6.3 11.6.4 SGS-UFSAR TABLE OF CONTENTS (Cent) Equipment Description Expected Volumes Packaging Storage Facilities Shipment Reference for Section 11.5 OFFSITE RADIOLOGICAL MONITORING PROGRAM Program Objective Preoperational and Operational Programs Expected Pathways Physical Characteristics of Samples 11-iii 11.5-2 11.5-3 11.5-3 11.5-3 11.5-3 11.5-4 11.6-1 11.6-1 11.6-2 11.6-2 11.6-2 Revision 6 February 15, 1987 Table 11.1-1 11.1-2 11.1-3 11.1-4 11 .. 1-5 11.1-6 11.1-7 11.1-8 11 .. 1-9 11.1-10 11 .. 1-11 11.1-12 SGS-UFSAR LIST OF TABLES Core Activities Deleted Deleted Deleted Deleted Deleted Parameters Used in the Calculation of Reactor Coolant Fission Product Activities Reactor Coolant Equilibrium Fission and Corrosion Product Activities Tritium Production in the Reactor Coolant Tritium Sources from the Reactor Employing Ag-In-Cd Absorber Rods Volume Control Tank Activities Gas Decay Tank Activity 11-iv Revision 16 January 31, 1998
  • Table 11.1-13 11.1-14 11.1-15 11.2-1 11.2-2 11.2-3 11.2-4 11.2-5
  • 11.2-6 11.2-7 11.2-8 11.2-9 SGS-UFSAR LIST OF TABLES (Cent) Deleted Deleted Deleted Liquid Waste System Performance Data Estimated Annual Liquid Discharge to Waste Disposal (per unit) Waste Disposal Component'S Code Requirements Component Data Summary Estimated Annual Liquid Discharge to Liquid Waste System Estimated Annual Liquid Release by Isotope {Two Unit Basis) Concentration of Radionuclides in Fish Due to Plant Operation Concentration of Radionuclides in Blue Crabs Due to, Plant Operation Potential Radiation Exposure Pathways to Man {Liquid) (Based on 0.2 percent failed fuel defects) 11-v Revision 23 October 17, 2007 I I I Table 11.3-1 11.3-2 11.3-3 11.3-4 11.4-1 11.4-2 11.4-3 11.4-4 11.6-1 11.6-2 SGS-UFSAR LIST OF TABLES (Cent) Estimated Annual Gaseous Release by Isotope from Gas Decay Tanks -per Unit Estimated Total Radioactive Gaseous Releases -Two Unit Basis Estimated Off-Site Radiation Exposures Releases -Two Unit Basis Gaseous Radioactive Potential Radiation Exposure Pathways to Man {Gaseous) Unit 1 Process Radiation Monitoring System Unit 2 Process Radiation Monitoring System Unit 1 Area Radiation Monitoring System Unit 2 Area Radiation Monitoring System Deleted Summary of Radionuclide Concentrations in Artificial Island Preoperational Radiological Environmental Monitoring Program Samples 11-vi Revision 15 June 12, 1996 Figure 11. 2-1A 11.2-18 11.3-1A 11.3-18 11.4-1 11.4-2 11.4-3 11.4-4 11.4-5 11.4-6 11.4-7 11.4-8 SGS-UFSAR LIST OF FIGURES Title Deleted: Refer to Plant Drawing 205239 Deleted: Refer to Plant Drawing 205339 Deleted: Refer to Plant Drawing 205240 Deleted: Refer to Plant Drawing 205340 Unit No. 2 Overall Radiation Monitoring System Makeup Unit No. 1 Air Particulate, Iodine and Gas Monitor (Typical) Unit No. 2 Air Particulate, Iodine and Gas Monitor (Typical) Unit No. 1 Liquid Monitor (Typical) Unit No. 2 Liquid Monitor (Typical) DELETED Unit No. 1 Area Monitor (Typical) Unit No. 2 Area Monitor (Typical) 11-vii Revision 27 November 25, 2013