ML24200A169

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Independent Spent Fuel Storage Installation, Final Safety Analysis Report, Revision 11
ML24200A169
Person / Time
Site: 07200011
Issue date: 06/26/2024
From: Ed Miller
Sacramento Municipal Utility District (SMUD)
To: Shana Helton
Division of Fuel Management, Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
DPG 24-275
Download: ML24200A169 (1)
v • d • e


Text

Powering forward. Together.

  • SMUD June 26, 2024 DPG 24-275 ATTN: Document Control Desk Director, Division of Fuel Management Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Rancho Seco Independent Spent Fuel Storage Installation Renewed Materials License No. SNM-2510 Docket 72-11 RANCHO SECO ISFSI FINAL SAFETY ANALYSIS REPORT, REVISION 11 Attention: Shana Helton Attached is Revision 11 to the Rancho Seco Independent Spent Fuel Storage Installation (ISFSI) Final Safety Analysis Report (FSAR)." The updated ISFSI FSAR includes changes to allow Manger Rancho Seco Assets to delegate Radiation Protection Manager duties as long as qualification for the position is met.

The enclosed attachments include removal/insertion instructions for the changed pages, a List of Effective Pages, Volume 1 Table of Contents, and the affected FSAR pages.

Vertical lines in the left-hand margin of the affected FSAR pages indicate the area of changed text. "Revision 11" and "June 2024" is also typed at the bottom right of each changed page.

By signature below, the Sacramento Municipal Utility District certifies that the above is true and correct. If you, or members of your staff, have questions requiring additional information or clarification you may contact me at (916) 732-6239.

Sincerely,

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p-Em est Miller Manager, Rancho Seco Assets cc w/attachments:

NRC, Region IV William Allen: Program Manager Part 72 RIC lF.099 Afft15SZD

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JH 55 Rancho Seco Nuclear Generating Station I 14440 Twin Cities Road I Herald, CA 95638-9799 I 916.452.3211 I smud.org

ISFSI FSAR REVISION 11 REMOVAL/INSERTION INSTRUCTIONS Remove List of Effective Pages (pp.1-21)

Volume 1, Table of Contents (pp. i-xvi)

Volume 1, Page 9.1-3 Volume 1, Page 9.1-4 Insert List of Effective Pages (pp.1-21)

Volume 1, Table of Contents (pp. i-xvi)

Volume 1, Page 9.1-3 Volume 1, Page 9.1-4

LIST OF EFFECTIVE PAGES Page or Figure Number VOLUME I I

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TABLE OF CONTENTS Introduction and General Description of Installation 1.1 1.2 1.3 1.4 1.5 1.6 Introduction 1.1.1 Principal Function of the Installation 1.1.2 Proposed Location of the ISFSI General Description of the Installation 1.2.1 Horizontal Storage Module 1.2.2 Dry Shielded Canister (DSC) 1.2.3 NUHOMS-MP187 Cask General Systems Description 1.3.1 Storage Systems 1.3.2 Transfer System 1.3.3 Auxiliary Systems 1.3.3.1 The Vacuum Drying System (VDS) 1.3.3.2 The Welding System 1.3.3.3 The Waste Processing System 1.3.3.4 The Security System 1.3.3.5 The Temperature and Pressure Monitoring System Identification of Agents and Contractors Material Incorporated by Reference References Site and Environment 2.1 Geography and Demography 2.1.1 Site Location 2.1.2 Site Description 2.1.2.1 Other Activities Within the Site Boundary 1.1-1 1.1-1 1.1-1 1.1-1 1.2-1 1.2-1 1.2-2 1.2-3 1.3-1 1.3-1 1.3-1 1.3-1 1.3-1 1.3-1 1.3-2 1.3-2 1.3-2 2.1.2.2 Boundaries for Establishing Effluent Release Limits 2.1.3 Population Distribution and Trends 1.4-1 1.5-1 1.6-1 2.1-1 2.1-1 2.1-1 2.1-1 2.1-2 2.1-2 2.1-2 2.1-3 2.1-3 2.1-4 2.1-4 2.2 2.3 Volume I 2.1.4 Uses of Nearby Land and Waters 2.1.4.1 Land Use 2.1.4.2 Access and Egress

. 2.1.4.3 Water Supply Nearby Industrial, Transportation, and Military Facilities 2.2.1 Industrial 2.2.2 Transportation 2.2.3 Military Meteorology 2.3.1 Regional Climatology 2.3.1.1 General Climate 2.3.1.2 Severe Weather Rancho Seco ISFSI FSAR 1

2.2-1 2.2-1 2.2-1 2.2-2 2.3-1 2.3-1 2.3-1 2.3-2 Revision 11 June 2024

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2.4 2.5 2.6 TABLE OF CONTENTS 2.3.2 Local Meteorology 2.3.2.1 Data Sources 2.3.3 On-Site Meteorological Measurements Program 2.3.4 Diffusion Estimates Hydrology 2.4.1 Characteristics of Streams and Lakes in Vicinity 2.4.2 Topography 2.4.3 Terminal Disposal of Stream Runoff 2.4.4 Historical Flooding 2.4.4.1 Floods From Frontal Storms 2.4.4.2 Floods From Thunderstorms 2.4.4.3 Spillway Capacity 2.4.5 Prediction of Land Urbanization 2.4.6 Groundwater 2.4.6.1 Occurrence and Movement 2.4.6.2 Water Supply 2.4.6.3 Quality 2.4.7 Wells Geology and Seismology 2.5.1 Geology 2.5.2 Seismology Soils 2.6.1 Rancho Seco Site 2.6.2 Rancho Seco ISFSI Site

2. 7 References Principal Design Criteria 3.1 Purpose of Installation 3.1.1 Material to be Stored
3. l.1.1 Physical Characteristics 3.1.1.2 Thermal Characteristics 3.1.1.3 Radiological Characteristics 3.1.2 General Operating Functions 3.1.2.1 Handling and Transfer Equipment 3.1.2.2 Waste Processing, Packaging and Storage Areas 3.2 Structural and Mechanical Safety Criteria 3.2.1 Tornado and Wind Loadings 3.2.1.1 Applicable Design Parameters 3.2.1.2 Determination of Forces on Structures 3.2.1.3 Ability of Structures to Perform Despite Failure of Structures Not Designed for Tornado Loads 3.2.1.4 Tornado Missiles Volume I Rancho Seco ISFSI FSAR 11 Page 2.3-3 2.3-3 2.3-4 2.3-4 2.4-1 2.4-1 2.4-1 2.4-1 2.4-1 2.4-2 2.4-2 2.4-2 2.4-3 2.4-3 2.4-3 2.4-4 2.4-5 2.4-5 2.5-1 2.5-1 2.5-1 2.6-1 2.6-1 2.6-1 2.7-1 3.1-1 3.1-1 3.1-1 3.1-1 3.1-1 3.1-2 3.1-3 3.1-3
  • 3.1-3 3.2-1 3.2-1 3.2-1 3.2-1 3.2-2 3.2-2 Revision 11 June 2024

3.3 3.4 Volume I TABLE OF CONTENTS 3.2.2 Water Level (Flood) Design 3.2.2.1 Flood Elevations 3.2.2.2 Phenomena Considered in Design Load Calculations 3.2.2.3 Flood Force Application 3.2.2.4 Flood Protection 3.2.3 Seismic Design Seismic-System Analyses 3.2.4 Snow and Ice Loadings 3.2.5 Load Combination Criteria 3.2.5.1 Horizontal Storage Module 3.2.5.2 Dry Shielded Canister 3.2.5.3 NUHOMS-MP187 Cask Safety Protection System 3.3.1 General 3.3.2 Protection by Multiple Confinement Barriers & Systems 3.3.2.1 Confinement Barriers and Systems 3.3.2.2 Ventilation - Off gas 3.3.3 Protection by Equipment and Instrumentation Selection

  • 3.3.3.1 Equipment 3.3.3.2 Instrumentation 3.3.4 Nuclear Criticality Safety 3.3.4.1 Control Methods for the Prevention of Criticality 3.3.4.2 Spent Fuel Loading 3.3.4.3 Model Specification 3.3.4.4 Criticality Calculation 3.3.4.5 Error Contingency Criteria 3.3.4.6 Verification Analysis 3.3.5 Radiological Protection 3.3.5.1 Access Control
  • 3.3.5.2 Shielding 3.3.5.3 Radiological Alarm Systems 3.3.6 Fire and Explosion Protection 3.3.7 Materials Handling and Storage 3.3. 7.1 Spent Fuel Handling and Storage 3.3.7.2 Radioactive Waste Treatment 3.3.7.3 Waste Storage Facilities 3.3. 8 Industrial and Chemical Safety Classification of Structures, Components, and Systems 3.4.1 Major ISFSI Components 3.4.2 Geological and Seismological Characteristics 3.4.2.1 Soil Characteristics at the ISFSI Pad 3.4.2.2 Soil Liquefaction 3.2-2 3.2-3 3.2-3 3.2-3 3.2-3 3.2-3 3.2-4 3.2-5 3.2-6 3.2-6 3.2-6 3.2-7 3.3-1 3.3-1 3.3-1 3.3-1 3.3-1 3.3-2 3.3-2 3.3-2 3.3-2 3.3-3 3.3-5 3.3-5 3.3-7 3.3-11 3.3-11 3.3-13 3.3-13 3.3-14 3.3-14 3.3-14 3.3-15 3.3-15 3.3-15 3.3-15 3.3-15 3.4-1 3.4-1 3.4-1 3.4-1 3.4-2 Rancho Seco ISFSI FSAR 111 Revision 11 June 2024

TABLE OF CONTENTS Page 3.4.2.3 Soil Amplification Due to Soil-Structure Interaction 3.4-3 3.5 Decommissioning Considerations 3.5-1 3.6 Summary of ISFSI Design Criteria 3.6-1 3.7 References 3.7-1

4.

Installation Design 4.1-1 4.1 Summary Description 4.1-1 4.1.1 Location and Layout of Installation 4.1-1 4.1.2 Principal Features 4.1-1 4.2 Storage Structures 4.2-1 4.2.1 Design Bases and Safety Assurance 4.2-1 4.2.2 Compliance with General Design Criteria 4.2-2 4.2.2.1 10 CFR 72.122 Overall Requirements 4.2-2 4.2.2.2 10 CFR 72.124 - Criteria for Nuclear Criticality Safety 4.2-3 4.2.2.3 10 CFR 72.126 Criteria for Radiological Protection 4.2.2.4 10 CFR 72.128 Criteria for Spent Fuel, High-level Radioactive Waste, and other Radioactive Waste Handling and Storage 4.2.2.5 10 CFR 72.130 Criteria for Decommissioning 4.2.3 Structural Specifications 4.2.4 Installation Layout 4.2.5 Individual Unit Description 4.2.5.1 Horizontal Storage Module (HSM) 4.2.5.2 Dry Shielded Canister 4.2.5.3 The NUHOMS-MP187 Cask 4.3 Auxiliary Systems 4.3.1 Ventilation and Offgas Requirements 4.3.2 Electrical System Requirements 4.3.3 Air Supply System 4.3.4 Steam Supply and Distribution System 4.3.5 Water Supply System 4.3.6 Sewage Treatment System 4.3.7 Communication and Alarm Systems 4.3.8 Fire Protection System 4.3.9 Cold Chemical System 4.3.10 Air Sampling System 4.4 Decontamination System 4.4.1 Equipment Decontamination 4.4.2 Personnel Decontamination 4.5 Repair and Maintenance Volume I Rancho Seco ISFSI FSAR IV 4.2-4 4.2-4 4.2-5 4.2-5 4.2-5 4.2-5 4.2-5 4.2-5 4.2-8 4.3-1 4.3-1 4.3-1 4.3-2 4.3-2 4.3-2 4.3-2 4.3-2 4.3-3 4.3-3 4.3-3 4.4-1 4.4-1 4.4-1 4.5-1 Revision 11 June 2024

TABLE OF CONTENTS 4.5.1 Repair 4.5.2 Maintenance 4.6 Cathodic Protection 4.7 Fuel Handling Operation Systems 4.7.1 Individual Unit Description 4.7.1.1 Function 4.7.1.2 Lifting Yoke and Extension 4.7.2 Design Bases and Safety Assurance 4.7.3 Structural Specifications 4.7.4 Installation Layout 4.7.5 Individual Unit Descriptions 4.7.5.1 Function 4.7.5.2 Components 4.7.6 Design Basis and Safety Assurance 4.8 References

5.

Operation Systems 5.1 Operation Description 5.1.1 Narrative Description 5.1.2 Process Flow Diagram 5.1.3 Identification of Subjects for Safety Analysis 5.1.3.1 Criticality Control 5.1.3.2 Chemical Safety 5.1.3.3 Operation Shutdown Modes 5.1.3.4 Instrumentation 5.1.3.5 Maintenance Techniques 5.2 Fuel Handling Systems 5.2.1 Spent Fuel Handling and Transfer 5.2.1.1 Function Description 5.2.1.2 Safety Features 5.2.2 Spent Fuel Storage 5.2.2.1 Safety Features 5.3 Other Operating Systems 5.3.1 Operating System 5.3.2 Component/Equipment Spares 5.4 Operation Support System 5.4.1 Instrumentation and Control Systems 5.4.2 System and Component Spares 5.5 Control Room and/or Control Areas 5.6 Analytical Sampling Volume I Rancho Seco ISFSI FSAR V

Page 4.5-1 4.5-1 4.6-1 4.7-1 4.7-1 4.7-1 4.7-2 4.7-2 4.7-2 4.7-2 4.7-3 4.7-3 4.7-3 4.7-3 4.8-1 5.1-1 5.1-1 5.1-1 5.1-1 5.1-2 5.1-2 5.1-2 5.1-2 5.1-2 5.1-2 5.2-1 5.2-1 5.2-1 5.2-2 5.2-2 5.2-2 5.3-1 5.3-1 5.3-1 5.4-1 5.4-1 5.4-1 5.5-1 5.6-1 Revision 11 June 2024

6.
7.

TABLE OF CONTENTS

5. 7 References Waste Confinement and Management 6.1 6.2 6.3 6.4 6.5 6.6 Waste Sources Off-gas Treatment and Ventilation Liquid Waste Treatment and Retention Solid Wastes Radiological Impact of Normal Operations - Summary References Radiation Protection 5.7-1 6.1-1 6.1-1 6.2-1 6.3-1 6.4-1 6.5-1 6.6-1 7.1-1 7.1 Ensuring that Occupational Radiation Exposures Are As Low As Is Reasonably Achievable (ALARA) 7.1-1 7.1-1 7.1-1 7.1-3 7.2 7.3 7.4 7.5 7.6 Volume I 7.1.1 Policy Considerations 7.1.2 Design Considerations 7.1.3 Operational Considerations Radiation Sources 7.2.1 Characterization of Sources 7.2.2 Airborne Radioactive Material Sources 7.2.3 Sealed Sources Radiation Protection Design Features 7.3.1 Installation Design Features 7.3.2 Shielding 7.3.2.1 Radiation Shielding Design Features 7.3.2.2 Shielding Analysis 7.3.3 Ventilation 7.3.4 Area Radiation and Airborne Radioactivity Monitoring Instrumentation Estimated Onsite Collective Dose Assessment 7.4.1 Operational Dose Assessment 7.4.2 Site Dose Assessment Health Physics Program 7.5.1 Organization 7.5.2 Equipment, Instrumentation, and Facilities 7.5.3 Procedures Estimated Offsite Collective Dose Assessment 7.6.1 Effluent and Environmental Monitoring Program 7.6.2 Analysis of Multiple Contribution 7.6.3 Estimated Dose Equivalents 7.6.4 Liquid Release Rancho Seco ISFSI FSAR Vl 7.2-1 7.2-1 7.2-1 7.2-2 7.3-1 7.3-1 7.3-1 7.3-1 7.3-1 7.3-1 7.3-2 7.4-1 7.4-1 7.4-2 7.5-1 7.5-1 7.5-1 7.5-2 7.6-1 7.6-1 7.6-1 7.6-1 7.6-1 Revision 11 June 2024

TABLE OF CONTENTS 7.7 References

8.

Analysis of Design Events 8.1 8.2 Volume I Normal and Off-Normal Operations 8.1.1.1 Dead Weight 8.1.1.2 Design Basis Internal Pressure 8.1.1.3 Design Basis Thermal Loads 8.1.1.4 Normal Operational Handling Loads 8.1.1.5 Off-Normal Handling Loads 8.1.1.6 Design Basis Live Loads 8.1.1.7 DSC Fatigue Evaluation 8.1.1.8 Cask Fatigue Evaluation 8.1.1. 9 Thermal Cycling of the Cask 8.1.2 Horizontal Storage Module Accident Analyses for the ISFSI 8.2.1 Accidental Cask Drop 8.2.1.1 Postulated Cause of Event 8.2.1.2 Detection of Event 8.2.1.3 Analysis of Effects and Consequences 8.2.1.4 Corrective Actions 8.2.2 DSC Leakage 8.2.2.1 Postulated Cause of Event 8.2.2.2 Detection of Event 8.2.2.3 Analysis of Effects and Consequences 8.2.2.4 Corrective Actions 8.2.3 Accident Pressurization 8.2.3.1 Postulated Cause of Event 8.2.3.2 Detection of Event 8.2.3.3 Analysis of Effects and Consequences 8.2.3.4 Corrective Actions 8.2.4 Earthquake 8.2.4.1 Postulated Cause of Event 8.2.4.2 Detection of Event 8.2.4.3 Analysis of Effects and Consequences 8.2.4.4 Corrective Actions 8.2.5 Fire 8.2.5.1 Postulated Cause of Event 8.2.5.2 Dectection of Event 8.2.5.3 Analysis of Effects and Consequences 8.2.5.4 Corrective Action Rancho Seco ISFSI FSAR Vll 7.7-1 8.1-1 8.1-1 8.1-1 8.1-6 8.1-7 8.1-9 8.1-12 8.1-12 8.1-13 8.1-13 8.1-14 8.1-14 8.2-1 8.2-1 8.2-2 8.2-2 8.2-2 8.2-9 8.2-10 8.2-10 8.2-10 8.2-10 8.2-11 8.2-11 8.2-11 8.2-11 8.2-11 8.2-12 8.2-12 8.2-12 8.2-12 8.2-12 8.2-13 8.2-13 8.2-13 8.2-13 8.2.14 8.2-15 Revision 11 June 2024

8.3 8.4 8.5 TABLE OF CONTENTS Load Combination Evaluation 8.3.1 DSC Load Combination Evaluation 8.3.2 Cask Load Combination Evaluation 8.3.3 Summary of Design Requirements Met Site Characteristics*Affecting Safety Analysis References 8.3-1 8.3-1 8.3-2 8.3-2

9.

Conduct of Operations 8.4-1 8.5-1 9.1-1 9.1-1 9.1-1 9.1-1 9.1-2 9.1-2 9.1-2 9.1 9.2 9.3 9.4 Volume I Organizational Structure 9.1.1 Corporate Organization 9.1.1.1 Corporate Functions, Responsibilities, and Authorities 9.1.1.2 In-House Organization 9.1.1.3 Interrelationship with Contractors and Suppliers 9.1.1.4 Technical Staff 9.1.2 Operating Organization, Management and Administrative Control System 9.1.2.1 Onsite Organization 9.1.2.2 Personnel Functions, Responsibilities and Authorities 9.1.3 Personnel Qualification Requirements 9.1.4 Liaison with Other Organizations Pre-Operational Testing and Operation 9.2.1 Administrative Procedures for Conducting Test Program 9.2.2 Test Program Description 9.2.2. l Physical Facilities and Operations 9.2.3 Test Discussion Training Program 9.3.1 Program Description 9.3.1.1 Scope of Training 9.3.1.2 Radiation Protection Technician Training 9.3.1.3 Dry Fuel Storage Equipment Operator Training 9.3.1. 4 Maintenance Training 9.3.1.5 Trainer Qualifications 9.3.2 Administration and Records Normal Operations 9.4.1 Procedures 9.4.1.1 Administrative Procedures 9.4.1.2 Radiation Protection Procedures 9.4.1.3 Maintenance Procedures 9.4.1.4 Operating Procedures 9.4.1. 5 Test Procedures 9.1-2 9.1-2 9.1-2 9.1-4 9.1-4 9.2-1 9.2-1 9.2-1 9.2-1 9.2-2 9.3-1 9.3-1 9.3-1 9.3-2 9.3-2 9.3-3 9.3-3 9.3-3 9.4-1 9.4-1 9.4-1 9.4-1 9.4-1 9.4-1 9.4-2 Rancho Seco ISFSI FSAR vm Revision 11 June 2024

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9.5 9.6 9.7 9.8 TABLE OF CONTENTS 9.4.1.6 Pre-operational Test Procedures 9.4.2 Records Emergency Planning Decommissioning Plan References Aging Management 9.8.1 Scoping Evaluation Methodology 9.8.2 Results of Scoping Evaluation 9.8.3 Aging Management Review 9.8.3.1 Results of Aging Management Review-DSC 9.8.3.2 Results of Aging Management Review-RSM 9.8.3.3 Results of Aging Management Review -

Concrete Basemat 9.8.3.4 Results of Aging Management Review -

Transfer Cask 9.8.3.5 Results of Aging Management Review-Spent Fuel Assemblies 9.8.4 Summary of Time-Limited Aging Analyses 9.8.4.1 DSC Time-Limited Aging Analyses 9.8.4.2 RSM Time-Limited Aging Analyses 9.8.4.3 Transfer Cask Time-Limited Aging Analyses 9.8.4.4 ISFSI Basemat Time-Limited Aging Analyses 9.8.5 Summary of Aging Management Programs 9.8.5.1 DSC Aging Management Program 9.8.5.2 RSM Aging Management Program 9.8.5.3 TC Aging Management Program 9.8.5.4 ISFSI Basemat Aging Management Program 9.8.6 Aging Management Tollgates Operating Controls and Limits 10.1 10.2 Proposed Operating Controls and Limits Development of Operating Controls and Limits 9.4-2 9.4-2 9.5-1 9.6-1 9.7-1 9.8-1 9.8-1 9.8-2 9.8-3 9.8-5 9.8-6 9.8-7 9.8-8 9.8-9 9.8-10 9.8-10 9.8-11 9.8-11 9.8-11 9.8-11 9.8-12 9.8-12 9.8-12 9.8-12 9.8-12 10.1-1 10.1-1 10.2-1 10.2.1 Functional and Operating Limits, Monitoring Instruments, and Limiting Control Settings 10.2-1 10.2-1 10.2-1 Volume I 10.2.2 Limiting Conditions for Operation 10.2.2. lEquipment Rancho Seco ISFSI FSAR IX Revision 11 June 2024

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TABLE OF CONTENTS 10.2.2.2Technical Conditions and Characteristics 10.2.3 Verification Requirements 10.2.4 Design Features 10.2.5 Administrative Controls 10.2.5.1 Qualification of Spent Fuel 10.2.5.2 Spent Fuel Identification 10.3 Operating Control and Limit Specifications 10.3.1 Spent Fuel Specifications 10.3.1.lFO and FC-DSC Fuel Specifications 10.3.l.2FF-DSC Fuel Specifications 10.3.2 DSC Vacuum Pressure During Drying 10.3.3 DSC Helium Backfill Pressure 10.3.4 DSC Helium Leakage Rate oflnner Seal Weld 10.3.5 DSC Dye Penetrant Test of Closure Welds 10.3.6 DSC Surface Contamination 10.3.7 ISFSI Security Area Dose Rate 10.3.8 Cask, DSC, and Fuel Assembly Inspection Following Accidental Cask Drop 10.3.9 Post Fire Recovery Plan 10.3.l0DSC Lifting Heights 10.3.llDSC Top End Dose Rates 10.3.12HSM Dose Rates 10.3.13Transfer Cask Dose Rates 10.3.14 DSC Re-flood Flow Rate 10.3.15 Heatup Duration of a Loaded DSC Filled with Water 10.4 References Quality Assurance 11.1 Sacramento Municipal Utility District Quality Assurance Program 11.2 Quality Assurance Program - Contractors 11.2.1 Architect-Engineer 11.2.2 Storage System Supplier 11.3 References Appendix A ASME Code Exception List Appendix B Standardized SAR References Appendix C Greater than Class C Waste Volume I Rancho Seco ISFSI FSAR 11 Page 10.2-1 10.2-3 10.2-3 10.2-3 10.2-4 10.2-5 10.3-1 10.3-1 10.3-1 10.3-1 10.3-2 10.3-3 10.3-4 10.3-5 10.3-6 10.3-7 10.3-8 10.3-9 10.3-10 10.3-11 10.3-12 10.3-13 10.3.14 10.3.15 10.4-1 11.1-1 11.1-1 11.2-1 11.2-1 11.2-1 11.3-1 Revision 11 June 2024

LIST OF TABLES Table 2-1 Permanent Population Distribution Within 13 Miles ofRSNGS Table 2-2 Highest One-Minute Average Windspeeds Table 2-3 Precipitation Climatology Table 2-4 Precipitation Intensity Table 2-5 Mean Number of Days of Thunderstorms Table 3-1 Rancho Seco Fuel Characteristics Table 3-2 Rancho Seco Control Element Characteristics Table 3-3 DSC Loading Summary for Cask Handling Conditions Table 3-4 Cask Loading Summary for Cask Handling Conditions Table 3-5 Summary of Dry Shielded Canister Capacity and Internal Pressure Design Criteria Table 3-6 DSC Load Combinations and Service Levels for Cask Storage and Handling Modes Table 3-7 Structural Design Criteria for DSC Table 3-8 Cask Load Combinations and Service Levels for Cask Handling Modes Table 3-9 Structural Design Criteria for On-Site Transfer Cask Table 3-10 Structural Design Criteria for Bolts Table 3-11 Rancho Seco ISFSI Major Components and Safety Classifications Table 3-12 Summary oflSFSI Design Criteria Table 3-13 Maximum Fuel Loading Parameters Table 3-14 Design Basis Fuel Parameters for Criticality Analysis Table 3-15 KENO Model Atom Densities Table 3-16 KENO Model Moderator Atom Densities Table 3-17 Summary of KENO Parametric Studies Table 3-18 MP187/FO-DSC KENO Results (Guide Sleeve Deformation)

Table 3-19 MP187/FO-DSC KENO Results (Cask Layer Removal)

Table 3-20 MP187/FO-DSC KENO Results Table 3-21 MP187/FF-DSC KENO Results Table 3-22 MP187/FF-DSC KENO Results (Cask Layer Removal)

Table 3-23 Benchmark Calculation Results Volume I Rancho Seco ISFSI FSAR Xl Revision 11 June 2024

LIST OF TABLES Table 5-1 Instrumentation Used During NUHOMS System Loading Operations Table 7-1 Design Basis Neutron Source Per Assembly and Energy Spectrum Table 7-2 Design Basis Gamma-Ray Source per Assembly and Energy Spectrum Table 7-3 Estimated Occupational Exposure for One HSM Load Table 7-4 Rancho Seco ISFSI Area Dose Rates Table 8-1 NUHOMS ISFSI Normal and Off-Normal Operating Loading Summary Table 8-2a FO/FC/FF DSC Cavity Normal, Off-Normal, and Accident Pressures Without Control Components Table 8-2b Pressures in the FC/FF DSC with Control Components Table 8-3 Cask ISFSI Normal and Off-Normal Operating Condition Stresses Table 8-4 FO-DSC ISFSI Normal and Off-Normal Operating Condition Stresses Table 8-5 FC-DSC ISFSI Normal and Off-Normal Condition Stresses Table 8-6 FF-DSC ISFSI Normal and Off-Normal Condition Stresses Table 8-7 Postulated ISFSI Accident Loading Summary Table 8-8 Cask ISFSI Accident Condition Stresses Table 8-9 FO-DSC ISFSI Accident Condition Stresses Table 8-10 FC-DSC ISFSI Accident Condition Stresses Table 8-11 FF-DSC ISFSI Accident Condition Stresses Table 8-12 Cask Enveloping Load Combination Results for Normal and Off-Normal Loads (ASME Service Levels A and B)

Table 8-13 Cask Enveloping Load Combination Results for Accident Loads (ASME Service Level C)

Table 8-14 Cask Enveloping Load Combination Results for Accident Loads (ASME Service Level D)

Table 8-15 FO-DSC Enveloping Load Combination Results for Normal and Off-Normal Loads (ASME Service Levels A and B)

Table 8-16 FO-DSC Enveloping Load Combination Results for Accident Loads (ASME Service Level C)

Table 8-17 FO-DSC Enveloping Load Combination Results for Accident Loads (ASME Service Level D)

Table 8-18 FC-DSC Enveloping Load Combination Results for Normal and Off-Normal Loads (ASME Service Levels A and B)

Table 8-19 FC-DSC Enveloping Load Combination Results for Accident Loads (ASME Service Level C)

Volume I Rancho Seco ISFSI FSAR Xll Revision 11 June 2024

LIST OF TABLES Table 8-20 FC-DSC Enveloping Load Combination Results for Accident Loads (ASME Service Level D)

Table 8-21 FF-DSC Enveloping Load Combination Results for Normal and Off-Normal Loads (ASME Service Levels A and B)

Table 8-22 FF-DSC Enveloping Load Combination Results for Accident Loads (ASME Service Level C)

Table 8-23 FF-DSC Enveloping Load Combination Results for Accident Loads (ASME Service Level D)

Table 8-24 Maximum Pressure Differential Across DSC Shell Table 8-25 Cask Cavity Pressure Assuming DSC Leakage After Placement in Storage (Deleted)

Table 9.8-1 Scoping Evaluation of Rancho Seco ISFSI SSCs Table 9.8-2 Scoping Evaluation Results for SF As Table 9.8-3 Rancho Seco FO-DSC Intended Functions and AMR Results Table 9.8-4 Rancho Seco FC-DSC Intended Functions and AMR Results Table 9.8-5 Rancho Seco FF-DSC Intended Functions and AMR Results Table 9.8-6 Rancho Seco GTCC-DSC Intended Functions and AMR Results Table 9.8-7 Rancho Seco HSM Intended Functions and AMR Results Table 9.8-8 MP187 TC Intended Functions and AMR Results Table 9.8-9 DSC External Surfaces Aging Management Program Table 9.8-10 HSM Aging Management Program for External and Internal Surfaces Table 9.8-11 TC Aging Management Program Table 9.8-12 ISFSI Basemat Aging Management Program Table 9.8-13 Rancho Seco ISFSI Tollgates Table 10-1 Area Where Controls and Limits Are Specified Volume I Rancho Seco ISFSI FSAR xm Revision 11 June 2024

LIST OF FIGURES Figure 1-1 Rancho Seco ISFSI Location Figure 1-2 ISFSI Layout Figure 1-3 Overview of the Horizontal Storage Module Figure 1-4 Overview of the Dry Shielded Canister Figure 1-5 Overview of the Cask Figure 1-6 Rancho Seco ISFSI Storage System Flowchart Figure 1-7 General Arrangement of the Transfer System Figure 2-1 Regional Map ofRSNGS Figure 2-2 RSNGS Site Figure 2-3 Rancho Seco ISFSI Site Figure 2-4 Permanent Population Surrounding RSNGS ( deleted)

Figure 2-5 Wind Trajectories for RSNGS Figure 2-6 Wind Trajectories at RSNGS Figure 2-7 Boring Location Map Figure 2-8 Subsurface Exploration Log B-1 Figure 2-9 Subsurface Exploration Log B-2 Figure 3-1 KENO Model and DSC Basket Figure 3-2 Exploded View of KENO Model Figure 3-3 Structure of KENO Model UNITS 33 and 34 Figure 3-4 Keno Model UNITS 1-8 Figure 3-5 KENO Model of a Design Basis Fuel Assembly Figure 3-6 K vs. Guide Sleeve Deformation Figure 3-7 FF-DSC Broken Fuel Rod Models Figure 3-8 FF-DSC Double-Ended Rod Break Models Figure 3-9 NUHOMS-MP 187 Cask/PO-DSC Criticality Results Figure 3-10 NUHOMS-MP187 Cask/FF-DSC Criticality Results Figure 3-11 Critical Benchmark Results Figure 5-1 DSC Loading Operations Flow Chart Figure 5-2 DSC Sealing, Draining and Drying Operations Flow Chart Figure 5-3 Primary Operations for DSC Fuel Handling Volume I Rancho Seco ISFSI FSAR XIV Revision 11 June 2024

Figure 5-4 Primary Operations for DSC Closure Figure 7-1 Occupational Exposure Contribution from Each DSC Loading Operation Figure 7-2 Rancho Seco ISFSI On-Site Dose Rates Figure 7-3 Dose Versus Distance from the Rancho Seco ISFSI Volume I Rancho Seco ISFSI FSAR xv Revision 11 June 2024

ACI AGM AISC ALARA ANS ANSI ASME ASTM B&W DOE DSAR DSC FC-DSC FF-DSC FO-DSC GM HSM IOSB ISFSI MP187 NDRC NFPA NRC NUHOMS NUREG OSHA PWR RSNGS SAR SFA SMUD VDS Volume I LIST OF ACRONYMS American Concrete Institute Assistant General Manager American Institute of Steel Construction As Low As Reasonably Achievable American Nuclear Society American National Standards Institute American Society of Mechanical Engineers American Society for Testing and Materials Babcock & Wilcox U.S. Department of Energy RSNGS Defueled Safety Analysis Report Dry Shielded Canister Fuel/Control Component DSC "Failed" Fuel DSC Fuel Only DSC General Manager Horizontal Storage Module Interim Onsite Storage Building Independent Spent Fuel Storage Installation NUHOMS Multi-Purpose (Transfer and Transportation) Cask National Defense Research Committee National Fire Protection Association U.S. Nuclear Regulatory Commission NUTECH Horizontal Modular Storage Nuclear Regulatory Guide Occupational Safety and Health Administration Pressurized Water Reactor Rancho Seco Nuclear Generating Station Safety Analysis Report Spent Fuel Assembly Sacramento Municipal Utility District Vacuum Drying System Rancho Seco ISFSI FSAR XVI Revision 11 June 2024

Manager, Rancho Seco Assets The Manager, Rancho Seco Assets (MRSA) is the lead SMUD representative at the Rancho Seco site and is responsible for all facets of day-to-day management of the licensed facilities.

The MRSA is responsible for site security during routine, emergency, and contingency operations. The MRSA is also responsible for the implementation and maintenance of the Physical Protection Plan.

The MRSA typically meets all qualifications for and is the Radiation Protection Manager and implements the Radiation Protection program. However, this may be delegated to an individual meeting the requirements of section 9.1-3, including contractors. The MRSA is responsible for health physics surveillance, personnel monitoring and record keeping, radwas.te management, emergency preparedness and environmental monitoring. The MRSA utilizes available SMUD and contract personnel to resolve engineering, design, and other technical issues required to support the 10 CFR 72 ISFSI licensing process in accordance with applicable regulations as well as similar issues conducted under the 10 CFR 50 license1.

The MRSA is responsible for ensuring that management of the Rancho Seco ISFSI.is conducted in accordance with Technical Specifications, federal and state regulations, Physical Protection Plan, and plant procedures and has the primary responsibility for cask and canister handling operations.

Staff under the direction of the MRSA is engaged in a continual retraining program, as described in Section 9.3, to ensure that ISFSI operations are conducted in a safe and efficient manner.

  • Personnel under the direction of the MRSA as designated by site procedures check, analyze, and log system parameters, and initiate corrective actions when abnormal conditions exist.

These personnel perform initial fire response and notifications in accordance with the fire protection program.

Individuals on shift are trained and qualified to implement appropriate radiation protection procedures.

Supporting Organizations outside Zero Carbon Energy Solutions Program Manager, Regulatory Compliance-Power Generation is responsible for ensuring that the quality assurance program is implemented in accordance with regulatory requirements, and has the authority to take any issue regarding the quality of program management at Rancho Seco to the General Manager and the Chief Zero Carbon Officer.

Emergency Preparedness is responsible for maintaining and administering the Emergency Plan under the direction of the Manager, Rancho Seco Assets. The Emergency Preparedness staff trains all personnel implementing the Emergency Plan as well as directing drills and other activities necessary to maintain regulatory compliance.

1 References to the 10CFR Part 50 license and Defueled Safety Analysis Report (DSAR) retained for historical licensing basis context. Current nuclear organization and responsibilities are contained in RSNAP-010.

Volume I Rancho Seco ISFSI FSAR 9.1-3 Revision 11 June 2024

Security is responsible for providing personnel as required to implement the Physical Protection Plan. Security is also responsible for staffing the security functions as required during routine, emergency and contingency conditions at the facility. Any or all of the Security function may be staffed by contracted personnel in the future: all contracted work will be under the direction of the Manager, Rancho Seco Assets.

9.1.3 Personnel Qualification Requirements Each member of the Rancho Seco staff meets or exceeds the minimum qualifications of ANSI N18.l-1971 for comparable positions, except the Radiation Protection Manager position which meets or exceeds the qualifications of Regulatory Guide 1. 8, September 1975.

Facility personnel are selected and trained for their assigned duties to ensure safe and efficient Rancho Seco ISFSI management.

Training, retraining, and replacement training programs for the maintenance staff and security force are maintained and conducted in accordance with approved procedures.

9.1.4 Liaison with Other Organizations Interface with DOE, Transnuclear West, and other outside organizations is performed in accordance with contractual agreements.

Volume I Rancho Seco ISFSI FSAR 9.1~4 Revision 11 June 2024

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