ML22200A027
| ML22200A027 | |
| Person / Time | |
|---|---|
| Site: | 07200011 |
| Issue date: | 06/29/2022 |
| From: | Gacke B Sacramento Municipal Utility District (SMUD) |
| To: | Shana Helton Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| DPG 22-085 | |
| Download: ML22200A027 (49) | |
Text
- SMUD June 29, 2022 DPG 22-085 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 Powering forward. Together.
RANCHO SECO ISFSI FINAL SAFETY ANALYSIS REPORT, REVISION 10 Attention: Shana Helton Attached is Revision 10 to the Rancho Seco Independent Spent Fuel Storage Installation (ISFSI) Final Safety Analysis Report (FSAR). The updated ISFSI FSAR includes changes to executive titles that were approved by the Nuclear Regulatory Commission via a Safety Evaluation Report for the Rancho Seco Quality Manual, Revision 5, dated December 12, 2021. Other changes include an update to the nearest population center of 25,000 or more based upon the 2020 Census, correction of a typographical error, and a change in the support organization related to the Quality Assurance Program.
The enc_losed 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 1 O" and "June 2022" 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) 732-4812.
Brad Gacke Manager, Rancho Seco Assets cc w/attachments:
NRC, Region IV William Allen: Program Manager Part 72 RIC lF.099 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 10 REMOVAL/INSERTION INSTRUCTIONS Remove List of Effective Pages (pp.1-21)
Volume 1, Table of Contents (pp. i-xvi)
Volume 1, Page 2.1-1 Volume 1, Page 2.1-2 Volume 1, Page 2.1-3 Volume 1, Page 2.1-4 Volume 1, Page 3.3-15 Volume 1, Page 3.4-1 Volume 1, Page 9.1-1 Volume 1, Page 9.1-2 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 2.1-1 Volume 1, Page 2.1-2 Volume 1, Page 2.1-3 Volume 1, Page 2.1-4 Volume 1, Page 3.3-15 Volume 1, Page 3.4-1 Volume 1, Page 9.1-1 Volume 1, Page 9.1-2 Volume 1, Page 9.1-3 Volume 1, Page 9.1-4
LIST OF EFFECTIVE PAGES Page or Figure Number VOLUME I 1
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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 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 10 June 2022
2.4 2.5 2.6 2.7 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 Front~! 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 Su11>ply. !
2.4.6.3 Quality 2.4.7 Wells I,
Geology and Seismology
. **.,.. i 2.5.1 Geology 2.5.2 Seismology Soils 2.6.1 Rancho Seco Site.
2.6.2 Rancho Seco ISFSI Site References
- 3.
Principal Design Criteria 3.1 3.2 Volume I Purpose of Installation 3.1.1 Material to be Stored 3.1.1.1 Physical Characteristics 3.1.1.2 Thermal Characteristics
- 3. l.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 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 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 10 June 2022
3.3 3.4 Volume I TABLE OF CONTENTS 3.2.2 Water Level (Flood) Design 3.2-2 3.2.2.1 Flood Elevations 3.2-3 3.2.2.2 Phenomena Considered in Design Load Calculations 3.2-3 3.2.2.3 Flood Force Application 3.2-3 3.2.2.4 Flood Protection 3.2-3 3.2.3 Seismic Design 3.2-3 Seismic-System Analyses 3.2-4 3.2.4 Snow and Ice Loadings 3.2-5 3.2.5 Load Combination Criteria 3.2-6 3.2.5.1 Horizontal Storage Module 3.2-6 3.2.5.2 Dry Shielded Canister 3.2-6 3.2.5.3 NUHO~S *d'4P18? rask 3.2-7 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 - Offgas 3.3.3 Protection by Equipment and Instn.upentation ~,ylection 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 3.3-1 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 10 June 2022
- 4.
3.5 TABLE OF CONTENTS 3.4.2.3 Soil Amplification Due to Soil-Structure Interaction Decommissioning Considerations 3.6 Summary oflSFSI Design Criteria
- 3. 7 References Installation Design 4.1 4.2 4.3 4.4 4.5 Summary Description 4.1.1 Location and Layout of Installation 4.1.2 Principal Features Storage Structures 4.2.1 Design Bases and Safety Assurance 4.2.2 Compliance wit4 General Design Criteria 4.2.2.l 10 CFR 72.122 Overall Requirements 4.2.2.2 10 CFR 72.124 - Criteria for Nucle*ar Criticality Safety 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 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 Decontamination System 4.4.1 Equipment Decontamination 4.4.2 Personnel Decontamination Repair and Maintenance 3.4-3 3.5-1 3.6-1 3.7-1 4.1-1 4.1-1 4.1-1 4.1-1 4.2-1 4.2-1 4.2-2 4.2-2 4.2-3 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 Volume I Rancho Seco ISFSI FSAR lV Revision 10 June 2022
4.6 4.7 4.8 TABLE OF CONTENTS 4.5.1 Repair 4.5.2 Maintenance Cathodic Protection 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. '
l 4.7.6 Design Basis and Sa1ety Assurance*
References i, 1 I
- 5.
Operation Systems 5.1 5.2 5.3 5.4 5.5 5.6 Volume I l
\\
Operation Description
~
5.1.1 Narrative Descript_1on.,. :
5.1.2 Process Flow Diagram
- 1 5.1.3 Identification of Subjects' for Safety Analysis 5.1.3.1 Criticality Controi',,,,,,. :
5.1.3.2 Chemical Safety 5.1.3.3 Operation Shutdown Modes :
5.1:3.4 Instrumentation *
- 5. l.3.5 ¥aintenance Techniq1Jes 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 Other Operating Systems 5.3.1 Operating System 5.3.2 Component/Equipment Spares Operation Support System 5.4.1 Instrumentation and Control Systems 5.4.2 System and Component Spares Control Room and/or Control Areas Analytical Sampling 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 10 June 2022
- 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 ofN,orin~l 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 Occupat~pnal Radiation Exposures. Are As Low As Is Reasonably Achievable (ALARAY 7.2 7.3 7.4 7.5 7.6 Volume I 7.1. 1 Policy Co'nsiderations '.
7.1.2 Design Considerations,
7.1.3 Operational Consider~tions Radiation Sources.
1 1
7.2.1 Characterization of Sources 7.2.2 Airbom~ Radioactive Material Sources I
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f I
7.2.3 Sealed Sources Radiation Protection Design Features 7.3.1 Installation Design Features 7.3.2 Shielding
. 7.3.2J 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 7.1-1 7.1-1 7.1-1 7.1-3 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 10 June 2022
- 8.
TABLE OF CONTENTS 7.7 References Analysis of Design Events 8.1 Normal and Off-Normal Operations 8.2 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 Eyaluation 8.1.1.8 Cask Fatigue Eva~uation 8.1.1.9 Thermal Cycling of the Cask 8.1.2 Horizontal Storage Mod~le Accident Analyses for the ISESI 8.2.1 Accidental Cask Drop 8.2.1.1 Postulated Cause of Event.
8.2.1.2 Detection ofBvenf 8.2.1.3 Analysis of Effects and Consequences 8.2.1.4 Corrective Actions 8.2.2 DSC Leakage
- ,. i_,,,
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 Volume I 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 10 June 2022
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 I
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 Organizati~n 9.1.1.1 Corporate Functions, Responsibilities, and Authorities 9.1.1.2 In-House Org:;mization 9.1.1.3 Jp.terrelationship with _Contractors and Suppliers 9.1.1.4 Tec]:inical Staff, l *
~
9.1.2 Operating Organization, Management and I *,
Administi;ative Cor:i,trql,Sy.stem 9.1.2.1 Onsite OrganizatipJ?-
. 9, 1.2.2 Pe~sonnel.F_\\ll),y~iqn_s, Resp,onsibilities and Authorities 9.1. 3 Personnel Qualificatio11 Requirements 9.1.4 Liaison wit)1 Other *orgruiizations
.. ~
~ {
Pre-Operational Testing* and *operation 9.2.l Administrative Procedures for Conducting Test Program 9.2.2 Test *Program Description 9.2,2: 1 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.l Procedures 9.4.1.1 Admini~trative 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 Vlll Revision 10 June 2022
- 10.
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 Evc1.luation 9.8.3 Aging Management Review 9.8.3.1 Results of Aging M~agement Review - DSC 9.8.3.2 Resuits of Aging Management Review - HSM 9.8.3.3 Results of Aging Management Review -
Concrete Base:rrtat' 9.8.3.4 Results of Aging Management Revifw -
Transfer Cask
- 9.8.3.5 Results of Agihg Management Review -
Spent Fuel Assemblies.
9.8.4 Summary of Time-L.imiteci'Aging Arntlyse*s 9.8.4.1 DSC Time-Limited Aging Analyses
.,, 9.8.4.2 HSM 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 HSM Aging Management Prqgr~
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 Proposed Operating Controls and Limits 10.2 Development.of Qperating 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 Voh.tme I 10.2.2 Limiting Conditions for Operation 10.2.2. lEquipment Rancho Seco ISFSI FSAR IX Revision 10 June 2022
- 11.
TABLE OF CONTENTS 10.2.2.2Technical Conditio~s 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.l 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 Bac\\dill Pressure 10.3.4 DSC Helium Leakage ;R~te ofli:mer 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 Inspecti~ri Followi~g Accidental Cask Drop 10.3.9 Post Fire Recovery Plan ".';,
. 10.3.l0QSC Lifting Heig~ts 10.3.l lDSC Top.End Dose*Rates 10.3.12HSM:Dose Rates 10.3.l 3Transfer 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 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 I 0.3-6 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 Sacramento Municipal Utility District Quality Assurance Program 11.1-1 11.2 Quality Assurance Program - Contractors 11.2-1 11.2.1 Architect-Engineer 11.2-1 11.2.2 Storage System Supplier 11.2-1 11.3 References 11.3-1 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 Revision 10 June 2022
- 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 1Table 2-5 Mean Number of Days ofThundei:stoFII1.s Table 3-1 Rancho Seco Fuel Characteristics l
\\ **l L
Table 3-2 Rancho Seco Control.Element Characteristics,.
Table 3-3 DSC Loading Summary for Cask Handling Co~ditions
)
Table 3-4 Cask Loading SlJ!Ilillary. for, Ca~k HfllldJip.g Con,ditions Table 3-5 Summary of Dry Shielded Canister Capacity and Internal Pressure Design Criteria Table 3-6 DSC Load Combinations and' Service Leyels 'for Cask Storage and Handling Modes Table 3-7 Structural Design Criteria for DSC~.- *
- Tabie 3-8 Cask Load Combinations and ServiGe Leveis fo~ Cask Handling Modes f
'\\
i I. \\*
I Table 3-9 Structural Design Criteria for On-Site Transfer Cask Table 3-10 Structural Design Criteria for Bolts*,i( "'*
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1 f
,Table 3-11 Rancho,Seco ISFSI Major.Compo.µents and,Safety Clas~ifications Table 3-12 Summary ofISFSI 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 Ato:i;n 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 I
Rancho Seco ISFSI FSAR xi Revision 10 June 2022
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 a,nd Off~Normal Operating Loading S.ummary Table 8-2a FO/FC/FF DSC Cavity Normal, Off-Normal, and Accident Pressures Without Control Components Tabl~ 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 L*oading Summary Table 8-8 Cask ISFSI Accident Condition Str~sses*
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 Re~ults 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!
. Rancho Seco ISFSI FSAR Xll Revision 10 June 2022
LIST OF TABLES Table 8-20 Fc~osc Enveloping Load Combination Results for Accident Loads (ASME Service Level.D)
Table 8-21 FF-DSC Enveloping Load Combination Results for Normal &nd Off-~orml¥ Loads (ASME Service Levels A and B)
Table 8-22 FF-DSC Enveloping Load Combination Results for Accident Loa~s (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 Ev:aluatioJJ. ofRanchq,Seco ISFSI SSCs Table 9.8-2 Scoping Evaluation Results for SF As Table 9.8-3 Rancho Secq FO-DSC IQ.tended ;Functions and AMR Results Table 9.8-4 Rancho Seco FC-DSC In,tended Functions. and AMR Result$
Table 9.8-5 Rancho Seco FF-DSC Intende,d_ FUilctions and AMR.Results Table 9.8-6 Rancho Seco GTCC-DSC Intended F,unctions and AMR Results Table 9.8-7 Rancho Seco HSM Intended Functions and AMR.Results Table 9.8-8 MP187 TC Intended Functions and AMR1R~sults 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 Tabl~ 10-1 Area Where Controls and Limi_ts Are Specified Volume I Rancho Seco ISFSI FSAR Xlll Revision 10 June 2022
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/FO-DSC Criticality Results Figure 3-10NUHOMS-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 10 June 2022
Figure 5-4 Primary Operations for DSC Closure Figure 7-1 Occupational Exposure Contribution from Each DSC Load4lg Operation.
Figure 7-2 Rancho Seco ISFSI On-Site Dose Rates Figure 7-3 Dose Versus Distance fron;i the Ranc4o Se90 ISF~I L
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Volume I Rancho Seco ISFSI FSAR xv*
Revision 10 June 2022
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.
Americ~ National Standards Institute American Society *of Mechanical Engineers American Society for Testing and Materials Babcock. & Wilcox U.S. Departme_nt of pnerny RSNGS Defuel~d Safety Analysis Report.
Dry Shield~d Canist~r Fuel/Control CompqneQ.t DSC
' "Failed" Fuel DSC.
Fuel Only DSC General Manager Horizontal Storage M~dule Interim Onsite,Storage Building Independent_ Spent F~el Storage Installation NUHOMS Mult(,.I)1rpose (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 XVl Revision 10 June 2022
- 2. SITE AND ENVIRONMENT 2.1 Geography and Demography 2.1.1 Site Location i
The Rancho Seco site is located in th~ south~ast part of Sacramento County, California. It occupies all or parts of Sections 27, 28, 29,, 32, ~3, and 34 of Township 6 Nortli, Range 8 East. The site is approximately 26 miles north-northeast of Stockton and 25 miles southeast of Sacramento, as shown in Figure 2-1..' The J.lari.cho Seco Nuclear Generating Station and Rancho Seco ISFSI are shown in Figure 2-2.
More generally, the site is located between the Sierra Nevada's to the east and the Coast Range along the Pacific Ocean to the west in an area of'flat to lightly rolling terrain at an elevation of approximately 200 above feet meari. sea leveL To the east of the site the land becomes more rolling, rising to an elevation_ of 600 feet at a distance of about seven miles, and increasing in elevation thereafter approaching _the Sierra Nevada foothills.
The approximate coordinates of the site are 38°-20'-40"_North Latitude and 121 °-07'-10" West longitude, or 4245500 Mn and 664400 M~ Universal Transverse Mercator coordinates.
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I As shown in Figure 2-3, the Rancho-Seco ISFSI is iocated west of the site's Industrial Area, approximately 600 feet west of the Interim On-~ite Storage Building. The Rancho Seco ISFSI is approximately 225 feet X 170 feet 'iii si~~.' *
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j 2.1.2 Site Description The entire Rancho Seco site is approximately 2480 acres with all acreage being owned by SMUD. The nearest population center of 25,000 or more is Galt, about 10 miles west-southwest of the site. The area around the site is almost exclusively agricultural or is used as grazing land.
The climatology of the Rancho Seco site is typical of the Great Central Valley of California.
Cloudless skies prevail during summer and much of the spring and fall seasons due to the pacific anticyclone off the California coast which prevents Pacific storms from entering inland. The rainy season usually extends from October through May. Atmospheric dispersion factors for the site are considered favorable.
Groundwater in the site area occurs under free or semi-confined conditions. It is stored chiefly in the alluvium, the older alluvial type deposits, and the Mehrten Formation.
Groundwater movement in the area is to the southwest with a slope of about ten feet/mile.
There is no indication of faulting beneath the site. The nearest fault system, the Foothill Fault System, is about ten miles east of the site and has been inactive since the Jurassic Volume I Rancho Seco ISFSI FSAR 2.1-1 Revision 10 June 2022
Period, some 135 million years ago. Ground accelerations.of no greater than 0.05g are anticipated at the site during the life of the plant.
The soils at the Rancho Seco site are sufficiently strong to safely support the Rancho Seco ISFSI structure and appurtenant facilities. The_se soils c~ be categorized as hard to very hard silts and silty clays with dense to very dense sands and gravels.
2.1.2.1 Other Activities Within the Site Boundary The Ran~ho Seco ISFSI lies wholly withii:i the 2,480 acre Rancho Seco Nuclear' Qenerating Station site. This site is owned and co.ntrolled by SMUD, who has full authority to d~termine all activities within the site including the exch.i,sion and removal of individuals and property.
The Rancho Seco ISFSI Protected Area is approximately 225 feet X 170 feet in size. The Protected Area is located within licensed boundary deI?,oted. py the 100 meter fence.
surrounding the Protected Area. Also _within the licensed bo-qndary of the ISFSI li~s the Fuel Transfer.Equipment Storage Building (FTESB), a 40 foot X 100 foot enclosure to store cont~1nated fuel handling and _transpoftati,;m s~pport ~quipment while* the spent nuclear fuel remains in stor3:ge.
SMUD has completed con;tructio~ of~ $00-M.W natural gas fired power plant located approximately1/2 m'ile south.of the Industrihl Area boundary.
I Access for transmission lines and water lines is from the west and south sides of the property.
2.1.2.2 Boundaries for Establishing Effluent Release Limits There are no radioactive effluent.releases associated with the Rancho Seco ISFSI.
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2.1.3 Population Distribution and Trends I
The land surrounding the site 'is presently undeveloped and is used primarily for grazing beef cattle and other agricultural activities. The most recent population distribution estimates are contained in the "Evacuation Time Estimate for the Rancho Seco Plume Exposure Pathway Emergency Planning Zone'.' [2.2.2].
There are five counties (Amador, San Joaquin, Sacramento, El Dorado, and Calaveras) within a 15-mile radius of Rancho Seco. Only very small portions of'El Dorado and Calaveras counties are within the 15-mile radius of Rancho Seco. There is no significant projected growth within these portions of these two counties. The projected development within Amador, Sacramento, and San Joaquin counties is discussed in Section 4.2 of the Rancho Seco ISFSI Environmental Report, Revision 1 [2.2)]. A five-r:µile radius area
. surrounding the Rancho Seco facility is defined as the low population zo0:e. This area is primarily farm land and vineyards, with few tourist attractions and littie seasonal variation in the population.
Volume I Rancho Seco ISFSI FSAR 2.1-2 Revision 10 June 2022
The Rancho Seco Reservoir and Recreation Area (Rancho Seco Park) attracts a number of day visitors to the area. The average annual number ofvisitor'days at the park for the last four years is 114,860 visitor days.
Additionally, a wildlife sanctuary has been built at Rancho Seco Park. It is estimated that an additional 625 cars could visit the pru-k during special functions at this fadlity.*
A survey of the area beyond the 5-mile radius shows that the nearest population concentration is approximately 6.5 miles from the plant site. The nearest population center of25,000 or niore is Galt, about 10 miles west-southwest of the site. Other population centers of greater than 25,000 people *include Lodi at 17 miles, Sacramento at 25 miles, Stockton at' 26 miles, and Modesto at 50 miles..
There are 16 special facilities in Amadot and s*acramento Counti_es within a 1 O1/2 mile radius of Rancho Seco. They consist of five public schools ( one high school and four elementary schools), one 'private elementary school, one treatment center for TB and alcoholic patients, four residential care homes, ah adult training center for developmentally disabled, a California Department of Forestry Fire Academy, the Preston School oflndustry, a nudist ranch, and Mule Creek State Prison. A summary of these facilities is shown in Table 2.2-3 of Rancho Seco Defueled Safety Analysis Re~or~ (pS~R), Amenament ~ [2.2.4] 1.
2.1.4 Uses of Nearby Land and Waters 2.1.4.1 Land Use The site area is almost exclusively agricul~al. DSAR, Amendment 4 Figure 2.2-41 provides a description of agriculture and residential activities within *a 5~mile radius of the site. There are no commercial dairy farms within this 5-mile radius.
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There are at present three large-scale commercial dairies in the vicinity, each with over 200 cows. The clos_est dairy is approximately 8 miles northwest of the site. A ranch 1 mile* east of the site has dairy cows for domestic use only.
Proposed land use for the southeast section of Sacramento County as adopted by the Sacramento ~lanning Department is predominantly (70 percent) agricultural and is expected to remain agricultural. Approximately 2000 acres of vineyards are being developed on land in proximity to the Rancho Seco site.
1 Current licerise environmental information is contained in Environmental Assessment for the Proposed Renewal of the U.S. Nuclear Regulatory Commission License Number SNM-25 IO for the Rancho Seco Independent Spent Fuel Storage Installation in Sacramento County, California (ADAMS, ML19241A378). References to the Defueled Safety Analysis Report (DSAR) retained for historical licensing basis context.
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Rancho Seco ISFSI FSAR 2.1-3 Revision 10 June 2022
2.1.4.2 Access and Egress As shown in Figure 2-2, State Route 104 runs just north of the site in a general east-west direction and connects with State Route 99 to the west and State Route 88 to the east.
The Twin Cities Access Road, identified in Figure-2-2, is the main access road to the plant and to nearby lecreational facilities. The access road to the plant is not a.through road and is designed to handle* heavy construction vehic_les.
Rail access to the site is available via a rail spur from the existing Southern Pacific Railroad line that runs roughiy parallel to State Route 104 adjacent to the site. The routing of the rail spur is shown in Figure 2-2. * '
2.1.4.3 Water Supply Potable water for the Ranch~ *seco site is obtained from the site well. Water for RSNGS is from the Folsom South Canal. The Bureau of Reclamation constructed the canal as part of the Central Valley Project. A pipeline and pumping station are located between the plant and the Fol~om South.Canal...
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Volume I Rancho Seco ISFSI FSAR It
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2.1-4 Revision 6 August 2016
ISFSI initiated explosions are not considered credible since no explosive materials are present. The effects of externally initiated explosions are bounded by the design basis tornado generated missile load analysis presented in Volume II, Section 8.3.1.
- 3. 3. 7 Materials Handling and Storage
- 3. 3. 7.1 Spent Fuel Handling and Storage The handling of intact and damaged spent fuel ~ssemblies within the RSNGS is addressed as part of the facility license under 10 CFR 50. This includes handling DSCs and casks using the Turbine Building Gantry Crane (inside and outside of the Fuel Storage Building), and loading the DSCs with irradiated SF As using *the'fuel handling bridge.
The DSC heat removal, onsite criticality control during transport, and contamination.control requirements for the Rancho Seco ISFSI are as discussed in Section 3.3.7 of the Standardized NUHOMS-24P System SAR [3.3.2].
See Appendix B for Standardized_SAR, S~ction 3.3.7 (pages 3.3-31 to 3.3-33).
3.3.7.2 Radioactive Waste Treatment The Rancho Seco ISFSI does not generate radioactive waste. Any secondary waste
- generated during cask loading and decontamination operations in the Fuel Storage Building will be disposed of in accordance with existing RSNGS radioactive waste handling procedures under the 10 CPR 50 license.
3.3.7.3 Waste Storage Facilities Waste storage facilities are neither required nor provided for at the Rancho Seco ISFSI. The requirements for on-site waste storage are satisfied by existing RSNGS facilities for handling and storage of waste from the spent fuel pool and dry active wastes as described in Chapter 6.
3.3.8 Industrial and Chemical Safety No hazardous chemicals or chemical reactions are involved in the operation of the Rancho Seco ISFSI. Industrial safety relating to handling of the cask and DSC are addressed by procedures which meet Occupational Safety and Health Administration (OSHA) requirements.
Volume I Rancho Seco ISFSI FSAR 3.3-15 Revision 0 November 2000
3.4 Classification of Structures, Components, and Systems 3.4.1 Major ISFSI Components Th~ classifications of the Rancho Seco ISFSI structures, systems, and components are similar to those of the Standardized NUHOMS-24P System and are discussed in Section 3.4 of the Standardized NUHOMS-24P SAR [3.3.2].. Thesei classifications are summarized in Table 3-11 for convenience, See Appendix B for Standardized SAR/ Section 3.4 (page*s 3.4-1 to 3.4-4).
3.4.2 Geological and Seismological Characteristics _
3.4.2.l Soil Characteristics at the ISFSI Pad The HSM and apron slabs w~re analyzed in acc~rdance with the Uniform Building Code (1991). The soil characteristics s1lch as allowable bearing pressure and vertical subgrade modulus were used in various ways: The bearing pressure.is used as a maximum value of pressure the soil is allowed to take from the structure due to vertical loads or overturning loads. A calculated bearing pressure comes from a finite element model analysis and is compared to the allowable bearing pressure. The.allowable bearing pressure is given for load applications that are not wind or seismic related;* however, a one third stress increase is allowed for those particular cases per the soils report. The vertical modulu*s of subgrade reaction is used to eftablish a spring c~n.s~~t representing the soil in t]:ie finite element model.
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.., 1 The slab analysis was performed using two finite-element models; one for the HSM slab and one for the apron*slab. The HSM slab supports only the HSMs and is not subject to tr~sporter loads or,crane loads... The design of the HSM slab considered the dead load and seismic loads associated with all HSMs being in place as well as the potential case where only a few of the modules were in place. The intent of these loading cases being to identify the maximum moments reasonably possible in the slab. The design of the apron slab took into account the movements of the transporter load over various parts of the apron slab, the '
cask load, and the crane load as~ociated with mov~ment of the ~ask.
' Soil properties were modeled as springs and variations of properties were not considered other than those embedded in the allowable bearing pressure and vertical modulus of subgrade reaction. This is consistent with relatively simple designs using the Uniform Building Code as its design basis.
The soils report (Reference 2.8 in SAR Vol.
- 1) indicated that settlement could be expected.
The total settlement.was given at 1.5" and differential.settlement was given as 1/2 to 2/3 of the total settlement. The differential settlement, therefore, would amount to 3/4" to l " over the length or width of the slabs. The smallest dimension of a slab is the HSM slab with a width Volume I Rancho Seco ISFSI FSAR 3.4-1 Revision 10 June 2022
- 9. CONDUCT OF OPERATIONS This chapter describes the organization and general plans for operating the Rancho Seco ISFSI. The organization section includes a brief description of the responsibilities of managers, supervisors, and other-key personnel. The training program for the.plant staffis described, along with a more general discussion of replacement and retraining plans.
Standards and procedures that govern daily operations and the records developed as a result of these operations are also discussed, as are the controls used to promote safety and ensure compliance with the license and the fegulations under which the facility operates.
Initially, the managerial and administrative controls for the conduct of operations at the Rancho Seco ISFSI will be built upon the existing organization under the 10 CPR' 50 license1* The Superintendent, Rancho Seco Assets is currently responsible for oversight of the Rancho Seco facility and for ensuring the s*afe' storage of the spent nuclear fuel and irradiated core components. This individual will continue to l?e responsible for safe storage of the fuel and will be responsible for the sla~e m1;U1agement of t~e Rancho Seco I°S}:~I.- '
The c;1.dmiQ.istrativ~ and procedural-controls,applicable to the 10 CFR 50 license1 have been expanded to include the requirements of the 10 CFR 72 license. Programs such as radiation protection, environmental monitoring, emergency preparedness, quality assurance, and
- training will be adapted as necessary. to ensure the safe,management of the ISFSI. SMUD has submitted and the NRC has approved the ISFSI security program which addresses the specific requirements for ISFSI security., _
Upon termination of the 10 CFR 50 license1,'tno~e fi.cense require~ents will be removed from the procedures. Appropriate 10 CFR 72.48 reviews will be conducted to ensure continued compliance with ISFSI license requirements. This process will result in stand-'
alone ISFSI programs that implement the 10 CFR,72 license. SMUD willtnaintain the
- appropriate admini:strative and managerial controls at the Rancho Seco ISFSI until the DOE takes title to the fuel.
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- 9. i.1 Corporate Organization Organizational Stn.{ctu!r'.e SMUD's organization and its relationship to the nuclear organization is"presented in: 'the Rancho Seco Defueled Safety Analysis Report (DSAR) [9. 7.1] 1* Both Rancho Seco licensed facilitie_s (ISFSI and Interim Onsite Storage Building) are managed under the same organization.
9.1.1.1 Corporate Functions, Responsibilities, and Authorities SMUD's Board of Directors is the policy-making body which has ultimate responsibility for the Rancho Seco ISFSI license: The Chief Executive Officer & General Manager (GM) reports directly to the Board of Directors.
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 9.1-1 Revision 9 June 2020
The GM, through the Chief Zero Carbon Officer, and Director, Power Generation has corporate responsibility for overall safety and management of the facility and shall take any
' measures needed to ensure acceptable performance of the staff in managing, maintaining, and providing technical support to the facility to ensure nuclear safety.
9.1.1.2 In-House Organization The facility organization is described in the DSAR[9. 7.1] 1*
9.1.1.3 Interrelationship with Contractors and Suppliers The prime contractor for design and analysis of the Rancho Seco ISFSI dry shielded canisters, *horizontal storage modules, auxiliary and transfer equipment and casks is
- Transnuclear West, Inc. of Fremont, California. The prime contractor for the design of the Rancho Seco ISFSI civil facilities, including,the storage pad, f~ncing and lighting system, etc. was Impell Corporation of San Ramon, California., Construction of the Rancho Seco ISFSi was the responsibility of BRCO Constructors, Inc. of Loomis, California. The Rancho Seco ISFSI is owned and operated by SMUD.
9.1.1.4 Technical Staff The Corporate technical staff supporting the Ran:cho Seco* ISFSI is described-in the DSAR
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9.1.2 Operating Organization, Management and Administrative Control. System 9.1.2.1 Onsite Org~iz~tion The RSNGS organization is responsible for management of the Rancho Seco ISFSI. This organization is described in J?SAR [9. 7.1] 1*
9.1.2.2 Personnel Functions, Responsibilities and Authorities The responsibilities and authority of major RSNGS positions or departments are summarized below. RSNGS personnel are selected and trained for their assigned duties, with particular emphasis on the supervisory and technical staffs to assure safe and efficient management of the Rancho Seco facilities.
Chief Zero Carbon Officer The Chief Zero Carbon Officer i~ responsible for the overall Rancho Seco facility and the Rancho Seco organization. This includes ensuring the safe storage of irradiated core components, ensuring effective day-to-day management, and maximizing the effectiveness of nuclear policies and procedures.
Director, Power Generation The Director, Power Generation is responsible for ensuring effective management of the licensed facilities and ensuring the safe storage of irradiated core components.
1 References to the I 0CFR 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 9.1-2 Revision 10 June 2022
Manager, Rancho Seed Assets J~e Manager, Rancho ~ec~ Assets (MRSA) i~ the le.ad 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 meets all qualifications for and.is the Radiation Protection-Manager and implements the Radiation Protection program.
- The MRSA is responsible for health physics surveillance, personnel monitorit1g and record keeping, r~dwaste management,.emergency preparedness and environmental monitoring,.
The MRSA utilizes available SMUD and 9ontract 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 Te~hnical Specifications, federal and state regulations; Physical Protection Plan, and plant procedures and has the primary responsibility for cask and canister handling operations.
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- 4 Staff under the direction of the MRSA is engaged in a continual retraini_ng program, as described in Section 9.3, to ensure that ISFSI operations are conducted in a safe and efficient manner.
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These personnel p~rforrn initial fire response and notifications it)..accordanc~ 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 directi9n of the Manager, R~cho 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.
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 N 18.1-1971 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.