ML19030A277
| ML19030A277 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 01/18/2019 |
| From: | James Shea Tennessee Valley Authority |
| To: | Office of New Reactors |
| Fetter A | |
| References | |
| TVACLINCHRIVERESP, TVACLINCHRIVERESP.SUBMISSION.6, CRN.P.PART02, CRN.P.PART02.2 | |
| Download: ML19030A277 (40) | |
Text
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report CHAPTER 1 TABLE OF CONTENTS Section Title Page 1.1 Introduction ................................................................................................... 1.1-1 1.2 General Site Description ............................................................................... 1.2-1 1.2.1 Site Location ................................................................................. 1.2-1 1.2.2 Site Development ......................................................................... 1.2-1 1.3 Comparison With Other Facilities .................................................................. 1.3-1 1.4 Identification of Agents and Contractors ....................................................... 1.4-1 1.4.1 Applicant/Program Manager ......................................................... 1.4-1 1.4.2 Principal Contractors and Participants ........................................ 1.4-1 1.4.2.1 BWX Technologies, Inc. ............................................ 1.4-1 1.4.2.2 Generation mPower LLC .......................................... 1.4-1 1.4.2.3 Bechtel Power Corporation ........................................ 1.4-1 1.4.2.4 Other Contractors and Participants ........................... 1.4-1 1.5 Requirements for Additional Technical Information ...................................... 1.5-1 1.6 Material Referenced ...................................................................................... 1.6-1 1.7 Drawings and Other Detailed Information ..................................................... 1.7-1 1.8 Interfaces with Standard Design ................................................................... 1.8-1 1.9 Conformance with Regulatory Criteria .......................................................... 1.9-1 1.10 Impact of Construction of New Nuclear Power Plant Units on Operating Units at Multi-Unit Sites ............................................................................... 1.10-1 1.11 Overview of Reactor Types ......................................................................... 1.11-1 1.11.1 BWXT mPower' ........................................................................ 1.11-1 1.11.2 NuScale ...................................................................................... 1.11-1 1.11.3 SMR-160 .................................................................................... 1.11-1 1.11.4 Westinghouse SMR .................................................................... 1.11-2 1.11.5 Reference ................................................................................... 1.11-2 1-i Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report CHAPTER 1 LIST OF TABLES Number Title 1.1-1 Acronyms, Abbreviations, and Initialisms 1.9-1 Conformance with Regulatory Guides 1.9-2 Conformance with Standard Review Plan 1-ii Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report CHAPTER 1 LIST OF FIGURES Number Title 1.2-1 Clinch River Nuclear Site Location 1.2-2 Clinch River Nuclear Site Plant Areas 1-iii Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report
1.1 INTRODUCTION
This Site Safety Analysis Report (SSAR) supports Tennessee Valley Authoritys (TVAs) Early Site Permit Application (ESPA) for the Clinch River Nuclear (CRN) Site. The SSAR addresses issues related to suitability of the CRN Site, in compliance with the regulations contained in 10 CFR 52, Subpart A, Early Site Permits. Specifically, the SSAR provides information related to site safety, emergency preparedness, and quality assurance.
The CRN Site is located in the City of Oak Ridge, Tennessee, and is the site of the former Clinch River Breeder Reactor Project. The CRN Site is comprised of approximately 935 acres, which are adjacent to the Clinch River arm of the Watts Bar Reservoir. TVA has not yet selected a reactor design to be constructed at the CRN Site; however, to facilitate the NRCs determination regarding suitability of the site for new nuclear units, TVA has provided a set of bounding plant parameters, referred to as the plant parameter envelope (PPE). The PPE was developed based on four small modular reactor (SMR) designs. An overview of the SMR designs used to develop the PPE is provided in Section 1.11, and Section 2.0 identifies the PPE and site characteristic values, which may be used as the basis for the NRC's determinations.
Where practicable, the SSAR section numbers correspond to those identified in NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition (SRP). Because the scope of an ESPA is reduced as compared to a Combined License Application (COLA), there are gaps in the numbering sequence of the SSAR. Maintaining SSAR section numbering consistent with the SRP facilitates future integration of the ESPA information with reactor design certification information during COLA development.
A summary of the contents of the SSAR is as follows:
Chapter 1, Introduction and General Description of the Plant, provides a general site description, an overview of reactor technologies considered in the development of the PPE, and a summary of SSAR compliance with regulations and conformance with regulatory guidance. A list of acronyms, abbreviations, and initialisms pertinent to the SSAR is included as Table 1.1-1.
Chapter 2, Site Characteristics, outlines the PPE and provides information related to geography and demography; hazards from nearby industrial, transportation, and military facilities (including aircraft hazards); and the meteorological, hydrologic, geologic, and seismic characteristics of the site.
Chapter 3, Design of Structures, Components, Equipment, and Systems, references information on aircraft hazards provided in Section 2.2.
Chapter 11, Radioactive Waste Management, provides the analysis of doses due to liquid and gaseous effluents from normal operations.
Chapter 13, Conduct of Operations, provides emergency planning and industrial security information.
Chapter 15, Accident Analyses, provides accident and dose consequence analyses required by 10 CFR 52.17(a)(1), 50.34(a)(1) and 100.21(c)(2), based on information provided in the PPE.
Chapter 17, Quality Assurance, provides a description of the quality assurance program (QAP) under which the ESPA was prepared and the proposed Quality Assurance Program Description to address the requirements of 10 CFR 52.17(a)(1)(xi).
1.1-1 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.1-1 (Sheet 1 of 8)
Acronyms, Abbreviations, and Initialisms 1D One Dimensional 2D Two Dimensional 3D Three Dimensional ac Acre ac-ft Acre-feet AFDD Accumulated Freezing Degree-Days AGV Appalachian Great Valley AHEX Atlantic Highly Extended Crust ALOHA Areal Locations of Hazardous Atmospheres ALWR Advanced Light Water Reactor AM Ante Meridiem ANS American Nuclear Society ANSI American National Standards Institute ANSS Advanced National Seismic System API Antecedent Precipitation Index APT Aquifer Pumping Test AQS Air Quality System ARF Areal Reduction Factor ASCE American Society of Civil Engineers ASOS Automated Survey Observing System ASTM ASTM International atm Atmospheres ATV Acoustic Televiewer BCF Block-centered Flow BDBE Beyond Design Basis Event BP Before Present bpf blows per foot BPT Brownian Passage Time Btu British Thermal Unit BTP Branch Technical Position BWXT BWX Technologies, Inc.
CAMP Central Atlantic Magmatic Province CAV Cumulative Absolute Velocity CDF Core Damage Frequency CEMP Comprehensive Emergency Management Plan CENA Central and Eastern North America CERI Center for Earthquake Research and Information CEUS Central and Eastern United States CFR Code of Federal Regulations cfs Cubic Feet per Second 1.1-2 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.1-1 (Sheet 2 of 8)
Acronyms, Abbreviations, and Initialisms CH High Plasticity Ci Curies cm Centimeter CNO Chief Nuclear Officer COCORP Consortium for Continental Reflection Profiling COL Combined License COLA Combined License Application COV Coefficient of Variation CPA Construction Permit Application CPG Comprehensive Preparedness Guide CRBRP Clinch River Breeder Reactor Project CRF Chestnut Ridge Fault CRM Clinch River Mile CRN Clinch River Nuclear CU Consolidated Undrained CVSZ Central Virginia Seismic Zone DBA Design Basis Accident DBT Design Basis Tornado DCF Dose Conversion Factor DEM Digital Elevation Model DO Dissolved Oxygen DOE U.S. Department of Energy DOT U.S. Department of Transportation DSF Day-second-feet DTM Digital Terrain Model EAB Exclusion Area Boundary EAL Emergency Action Level ECC-AM Extended Continental Crust - Atlantic Margin ECC-GC Extended Continental Crust - Gulf Coast ECL Effluent Concentration Limit ECMA East Coast Magnetic Anomaly EDS Environmental Data Station EIS Environmental Impact Statement El Elevation ELF Estimated Local Flow EP Emergency Preparedness EPA U.S. Environmental Protection Agency EPFS Eastern Piedmont Fault System EPRI Electric Power Research Institute EPRI-SOG Electric Power Research Institute - Seismicity Owners Group EPZ Emergency Planning Zone 1.1-3 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.1-1 (Sheet 3 of 8)
Acronyms, Abbreviations, and Initialisms EQNO Earthquake Number ERB Effluent Release Boundary ERH Estimated Horizontal Location Uncertainty ERM-N Eastern Rift Margin - North ERM-S Eastern Rift Margin - South ESP Early Site Permit ESPA Early Site Permit Application ETE Evacuation Time Estimate ETR Energy Transfer Ratio ETSZ Eastern Tennessee Seismic Zone ETTP East Tennessee Technology Park FAA Federal Aviation Administration FAS Fourier Amplitude Spectrum FDD Freezing Degree Day FE Finite Element FEMA Federal Emergency Management Agency FOSID First Onset of Significant Inelastic Deformation FP Fossil Plant fps Feet per Second FS Factor of Safety FSAR Final Safety Analysis Report ft Foot or Feet ftbgs Feet Below Ground Surface ftbtc Feet Below Top of Casing Ga Giga Annum GCVSZ Giles County, Virginia, Seismic Zone GHEX Gulf Coast Highly Extended Crust GI-LLI Gastrointestinal Tract - Lower Large Intestine GIS Geographic Information Systems GL Generic Letter GMH Great Meteor Hotspot GmP Generation mPower, LLC GMPE Ground Motion Prediction Equations GMRS Ground Motion Response Spectrum GMM Ground Motion Models gpm Gallons per Minute GPS Global Positioning System GS Ground Surface GSC Geological Survey of Canada GSI Geological Strength Index HCI Hydrochloric Acid 1.1-4 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.1-1 (Sheet 4 of 8)
Acronyms, Abbreviations, and Initialisms HEC-HMS Hydrologic Engineering Centers Hydrologic Monitoring System HEC-RAS Hydrologic Engineering Centers River Analysis System HF High-frequency HHA Hierarchical Hazard Assessment HiRAT High Resolution Acoustic Televiewer HI-SMUR' Holtec Inherently-Safe Modular Underground Reactor HMR NOAA Hydro-Meteorological Report HP Hydro Plant hr Hour Hz Hertz IBEB Illinois Basin Extended Basement IDLH Immediately Dangerous to Life or Health IEEE Institute of Electrical and Electronics Engineers in. Inch iPWR Integral Pressurized Water Reactor IRM Iapetan Rifted Margin ISG Interim Staff Guidance ITAAC Inspections, Tests, Analyses, and Acceptance Criteria JFD Joint Frequency Distribution ka Kilo Annum kg Kilogram km Kilometer K-S-B Kijko-Sellevoll-Bayes ksf Kilopound per Square Foot LCD Local Climatological Data LDO Lamont-Doherty Cooperative Seismographic Network Catalog LEL Lower Explosive Limit LF Low-frequency LFL Lower Flammability Limit LiDAR Light Detection and Ranging LIP Local Intense Precipitation LMDCT Linear Mechanical Draft Cooling Tower LOA Letter of Agreement LOCA Loss-of-Coolant Accident LPZ Low Population Zone m Meter M Moment Magnitude Ma Mega Annum MAFE Mean Annual Frequency of Exceedance MBDBE Mitigation of Beyond Design Basis Events MEI Maximally Exposed Individual 1.1-5 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.1-1 (Sheet 5 of 8)
Acronyms, Abbreviations, and Initialisms MESE Mesozoic and Younger Extension MESE-N Narrow Mesozoic and Younger Extension MESE-W Wide Mesozoic and Younger Extension mgd Million Gallons per Day mg/L Milligrams per Liter mi Mile MidC Midcontinent-Craton ML Local Magnitude Mmax Maximum Magnitude mmHg Millimeters of Mercury MMI Modified Mercalli Intensities MOA Military Operations Area MPa Megapascal mph Miles per Hour msl Mean Sea Level MWe Megawatt Electric MWt Megawatt Thermal NAAQS National Ambient Air Quality Standards NAD83 North American Datum of 1983 NAMT North America Moment Tensor NAP Northern Appalachian NAVD88 North American Vertical Datum of 1988 NAWQA National Water-Quality Assessment Program NBI National Bridge Inventory NCDC National Climatological Data Center NEDB National Earthquake Database (of Canada)
NEI Nuclear Energy Institute NEIC National Earthquake Information Center NGVD29 National Geodetic Vertical Datum of 1929 NID National Inventory of Dams NIOSH National Institute of Occupational Safety and Health NIRMA Nuclear Information and Records Management Association NMESE Not Experienced Mesozoic and Younger Extension NMFS New Madrid Fault System NMN New Madrid North NMS New Madrid South NOAA National Oceanic and Atmospheric Administration NP Nuclear Plant NQAP Nuclear Quality Assurance Plan NRC Nuclear Regulatory Commission NRCS Natural Resources Conservation Service 1.1-6 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.1-1 (Sheet 6 of 8)
Acronyms, Abbreviations, and Initialisms NSHMP National Seismic Hazards Mapping Program NTU Nephelometric Turbidity Unit NWS National Weather Service NY-AL New York-Alabama ODUSD Office of the Deputy Under Secretary of Defense OKA Oklahoma Aulacogen OKO Oklahoma Geological Survey Catalog OMG Operations Management Group ORNL Oak Ridge National Laboratory ORO Offsite Response Organization ORR Oak Ridge Reservation OSHA Occupational Safety and Health Administration OSL Optically Stimulated Luminescence OW Observation Well OYO OYO Corporation PAC Protective Action Criteria PAG Protective Action Guide pcf Pounds per Cubic Foot PDE Preliminary Determination of Epicenters PEP Plume Exposure Pathway PEZ Paleozoic Extended Crust PEZ-N Paleozoic Extended Crust Narrow PEZ-W Paleozoic Extended Crust Wide PGA Peak Ground Acceleration PGV Peak Ground Velocity PI Plasticity Index PM Post Meridiem PMC Project Management Corporation PMF Probable Maximum Flood PMP Probable Maximum Precipitation PMWP Probable Maximum Winter Precipitation PPE Plant Parameter Envelope PPRP Participatory Peer Review Panel PRA Probabilistic Risk Assessment PSA Pseudo-Spectral Acceleration PSAR Preliminary Safety Analysis Report PSEG Public Service Enterprise Group psf Pounds per Square Foot PSHA Probabilistic Seismic Hazard Analysis psi Pounds per Square Inch psia Pound per Square Inch Absolute 1.1-7 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.1-1 (Sheet 7 of 8)
Acronyms, Abbreviations, and Initialisms psig Pounds per Square Inch Gage Pt Point PW Pumping Well PWR Pressurized Water Reactor QA Quality Assurance QAP Quality Assurance Program QC Quality Control Qc Colluvium or Colluvial Qha Holocene Alluvium Qhaf Holocene Alluvial Fan Qht Holocene Qpt Pleistocene rem Roentgen Equivalent in Man RFT Reelfoot Thrust RG Regulatory Guide RLME Repeated Large Magnitude Earthquake RMP Risk Management Program RMR Rock Mass Rating RMSE Root Mean Square Error ROS Reservoir Operations Study RQD Rock Quality Designation RR Reelfoot Rift RR-RCG Reelfoot Rift Rough Creek Graben RSB Reactor Service Building RTD Resistance Temperature Detector RVT Random Vibration Theory SACTI Seasonal/Annual Cooling Tower Impacts SARA Superfund Amendments and Reorganization Act SASW Spectral Analysis of Surface Wave SCCW Supplemental Condenser Cooling Water SCR Stable Continental Regions SCSN South Carolina Seismic Network SDWIS Safe Drinking Water Information System SEI Structural Engineering Institute SI Subsurface Investigation SLR Saint Lawrence Rift Zone SLU St. Louis University SMR Small Modular Reactor SNR Signal to Noise Ratio sq mi Square Mile SPID Screening, Prioritization, and Implementation Details 1.1-8 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.1-1 (Sheet 8 of 8)
Acronyms, Abbreviations, and Initialisms SPT Standard Penetration Test SRP Standard Review Plan SSAR Site Safety Analysis Report SSC Seismic Source Characterization SSCs Structures, Systems, and Components SSE Safe-Shutdown Earthquake SSHAC Senior Seismic Hazards Analysis Committee STEL Short Term Exposure Limit SUSN Southeastern United States Network TAF Terminal Area Forecast TDEC Tennessee Department of Environment and Conservation TDOT Tennessee Department of Transportation TDS Total Dissolved Solids TEDE Total Effective Dose Equivalent TI Technical Integration TIN Triangulated Irregular Network TLV Threshold Limit Value TN Tennessee TNT Trinitrotoluene TRM Tennessee River Mile TVA Tennessee Valley Authority TWA Time-weighted Average S Microsiemens UFL Upper Flammability Limit UH Unit Hydrograph UHRS Uniform Hazard Response Spectra UHS Ultimate Heat Sink URD Utility Requirements Document USACE U.S. Army Corps of Engineers USCB U.S. Census Bureau USCS Unified Soil Classification System USGS U.S. Geological Survey UT Uncorrelated Terraces UU Unconsolidated Undrained V/H Vertical to Horizontal Vs Shear Wave Velocity WBN Watts Bar Nuclear Plant WTP Water Treatment Plant WUS Western United States X/Q Atmospheric Dispersion yr or yrs Year or Years 1.1-9 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report 1.2 GENERAL SITE DESCRIPTION 1.2.1 Site Location The Clinch River Nuclear (CRN) Site is located in Oak Ridge, Tennessee, and comprises approximately 935 acres of land adjacent to the Clinch River arm of the Watts Bar Reservoir. The CRN Site is the location of the former Clinch River Breeder Reactor Project. A more detailed description of the site location is provided in Section 2.1.
The site is bounded on the east, south, and west by the Clinch River arm of the Watts Bar Reservoir and on the north by the Grassy Creek Habitat Protection Area. Communities located near the site include Kingston (approximately 6.8 miles [mi] west), Harriman (9.2 mi west-northwest), Lenoir City (approximately 8.8 mi southeast), and Knoxville (approximately 25.6 mi east-northeast).
Figures 2.1-3 and 2.1-4 show the CRN Site location and the surrounding 5-mi vicinity and 50-mi region, respectively.
1.2.2 Site Development TVA has not selected a reactor technology to be constructed at the CRN Site. Instead, a set of bounding plant parameter values has been identified, based upon the available information from various light-water-cooled, small modular reactor (SMR) designs. This set of bounding values, referred to as the plant parameter envelope (PPE), is presented in Section 2.0 and provides the basis for future site development at the CRN Site. The PPE is based on construction and operation at the CRN Site of two or more SMRs with a maximum rated thermal power for a single unit of 800 MWt. The combined nuclear generating capacity from the site is not to exceed 2420 MWt (800 MWe). Because a specific reactor technology has not been selected, an area, referred to as the power block area, has been proposed as the location of the reactor modules on the site. The CRN Site location is shown in Figure 1.2-1, while the general plant areas, including the power block area, are illustrated in Figure 1.2-2.
1.2-1 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Figure 1.2-1. Clinch River Nuclear Site Location 1.2-2 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Figure 1.2-2. Clinch River Nuclear Site Plant Areas 1.2-3 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report 1.3 COMPARISON WITH OTHER FACILITIES This section is not applicable to an Early Site Permit Application using the plant parameter envelope approach.
1.3-1 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report 1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS 1.4.1 Applicant/Program Manager The Tennessee Valley Authority (TVA) is the Applicant for an Early Site Permit (ESP) at the Clinch River Nuclear (CRN) Site. TVA is the United States largest public power provider. It was established by Congress in 1933, among other things, to improve navigation on the Tennessee River, reduce the damage from destructive floodwaters within the Tennessee River system and downstream on the lower Ohio and Mississippi Rivers, further the economic development of TVAs service area, and sell the electricity generated at the facilities TVA operates. TVAs service territory, which includes most of Tennessee and parts of Alabama, Georgia, Kentucky, Mississippi, North Carolina, and Virginia, serves more than nine million people. TVA sells electricity to 155 local power company customers and directly serves approximately 52 large industrial facilities and 8 Federal facilities.
1.4.2 Principal Contractors and Participants 1.4.2.1 BWX Technologies, Inc.
TVA has a contract with BWX Technologies (BWXT) to provide technical information to TVA in support of the ESP Application (ESPA).
1.4.2.2 Generation mPower LLC BWXT has contracted Generation mPower (GmP) to manage development of portions of the ESPA.
1.4.2.3 Bechtel Power Corporation Bechtel Power Corporation assisted in developing portions of the Site Safety Analysis Report (SSAR) and conducted various analyses and investigations, including:
Geotechnical field investigations, with contracted support from Amec Foster Wheeler Identification and characterization of seismic source zones, with contracted support from Lettis Consultants International Determination of site-specific distribution coefficients, with contracted support from Argonne National Laboratory 1.4.2.4 Other Contractors and Participants Contractual relationships were established between TVA and specialized consulting firms to assist in preparation of the ESPA for the CRN Site, as discussed in the following subsections.
1.4.2.4.1 Barge Waggoner Sumner & Cannon, Inc.
TVA contracted Barge Waggoner Sumner & Cannon, Inc., to perform evaluations and studies in the area of hydrology.
1.4.2.4.2 Enercon Services, Inc.
TVA contracted Enercon Services, Inc., to prepare portions of the SSAR related to demography and meteorology and to develop the Emergency Plans.
1.4-1 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report 1.4.2.4.3 AECOM Technical Services Inc.
TVA contracted AECOM Technical Services, Inc., to perform a portion of the seismic analyses.
1.4-2 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report 1.5 REQUIREMENTS FOR ADDITIONAL TECHNICAL INFORMATION No technical development programs remain to be performed to support this application.
1.5-1 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report 1.6 MATERIAL REFERENCED No material has been incorporated by reference in this application.
1.6-1 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report 1.7 DRAWINGS AND OTHER DETAILED INFORMATION No such information has been submitted separately as part of this application.
1.7-1 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report 1.8 INTERFACES WITH STANDARD DESIGN This topic is not applicable to an Early Site Permit Application using the plant parameter envelope approach and is addressed at the combined license application stage.
1.8-1 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report 1.9 CONFORMANCE WITH REGULATORY CRITERIA This section addresses the conformance of the Site Safety Analysis Report (SSAR) with applicable NRC guidance contained in NRC Regulatory Guides (RGs) and NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition (SRP).
NRC RGs evaluated for conformance were identified through a review of the applicable SRP sections. Table 1.9-1 provides a listing of applicable RGs by number and title with the associated SSAR section number statements of conformance. Exceptions to conformance with a RG are noted with an explanation. RGs included are those identified in the applicable SRP sections.
Table 1.9-2 provides a listing of the SRP sections, applicable to an Early Site Permit Application (ESPA), with statements of conformance. An exception to conformance is noted when the SSAR does not meet regulatory guidance as stated but the intent or objective is met using an acceptable alternative. Exceptions to conformance with the SRP are noted with an explanation.
Exemptions to NRC regulations required to support this ESPA are identified and described in ESPA Part 6.
1.9-1 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.9-1 (Sheet 1 of 8)
Conformance with Regulatory Guides Regulatory Applicable Guide Rev. Title SSAR Section Conformance(a) Comments 1.23 1 Meteorological Monitoring Programs for Nuclear 2.3.1 Conforms Power Plants 2.3.2 Conforms 2.3.3 Conforms 2.3.4 Conforms 2.3.5 Conforms 1.26 4 Quality Group Classifications and Standards for 17.5 Conforms Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants 1.27 3 Ultimate Heat Sink for Nuclear Power Plants 2.3.1 NA The small modular reactor (SMR) designs being considered for use at the Clinch River Nuclear (CRN)
Site use passive containment cooling for the ultimate heat sink (UHS). As indicated in RG 1.27, Rev. 3, the guidance provided therein does not apply for those designs.
2.4.1 NA The SMR designs being considered for use at the CRN Site use passive containment cooling for the UHS. As indicated in RG 1.27, Rev. 3, the guidance provided therein does not apply for those designs.
2.4.2 NA The SMR designs being considered for use at the CRN Site use passive containment cooling for the UHS. As indicated in RG 1.27, Rev. 3, the guidance provided therein does not apply for those designs.
2.4.3 NA The SMR designs being considered for use at the CRN Site use passive containment cooling for the UHS. As indicated in RG 1.27, Rev. 3, the guidance provided therein does not apply for those designs.
2.4.4 NA The SMR designs being considered for use at the CRN Site use passive containment cooling for the UHS. As indicated in RG 1.27, Rev. 3, the guidance provided therein does not apply for those designs.
1.9-2 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.9-1 (Sheet 2 of 8)
Conformance with Regulatory Guides Regulatory Applicable Guide Rev. Title SSAR Section Conformance(a) Comments 2.4.5 NA The SMR designs being considered for use at the CRN Site use passive containment cooling for the UHS. As indicated in RG 1.27, Rev. 3, the guidance provided therein does not apply for those designs.
2.4.6 NA The SMR designs being considered for use at the CRN Site use passive containment cooling for the UHS. As indicated in RG 1.27, Rev. 3, the guidance provided therein does not apply for those designs.
2.4.7 NA The SMR designs being considered for use at the CRN Site use passive containment cooling for the UHS. As indicated in RG 1.27, Rev. 3, the guidance provided therein does not apply for those designs.
2.4.8 NA The SMR designs being considered for use at the CRN Site use passive containment cooling for the UHS. As indicated in RG 1.27, Rev. 3, the guidance provided therein does not apply for those designs.
2.4.9 NA The SMR designs being considered for use at the CRN Site use passive containment cooling for the UHS. As indicated in RG 1.27, Rev. 3, the guidance provided therein does not apply for those designs.
2.4.11 NA The SMR designs being considered for use at the CRN Site use passive containment cooling for the UHS. As indicated in RG 1.27, Rev. 3, the guidance provided therein does not apply for those designs.
2.4.12 NA The SMR designs being considered for use at the CRN Site use passive containment cooling for the UHS. As indicated in RG 1.27, Rev. 3, the guidance provided therein does not apply for those designs.
2.5.4 NA The SMR designs being considered for use at the CRN Site use passive containment cooling for the UHS. As indicated in RG 1.27, Rev. 3, the guidance provided therein does not apply for those designs.
1.9-3 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.9-1 (Sheet 3 of 8)
Conformance with Regulatory Guides Regulatory Applicable Guide Rev. Title SSAR Section Conformance(a) Comments 1.28 4 Quality Assurance Program Criteria (Design and 2.5.4 Conforms With equivalents, as discussed in Section 17.5.
Construction) 2.5.5 Conforms With equivalents, as discussed in Section 17.5.
17.5 Exception With equivalents and alternatives, as discussed in Section 17.5.
1.29 5 Seismic Design Classification 2.4.1 Conforms 2.4.2 Conforms 2.4.3 Conforms 2.4.4 Conforms 2.4.5 Conforms 2.4.6 Conforms 2.4.7 Conforms 2.4.8 Conforms 2.4.9 Conforms 2.4.10 Conforms 2.4.11 Conforms 2.4.14 NA The site grade is above the maximum flood height (the site is considered to be dry). Thus, no flooding protection for structures, systems, and components (SSCs) important to safety is required.
17.5 Conforms 1.37 1 Quality Assurance Requirements for Cleaning of 17.5 Exception With equivalents and alternatives, as discussed in Fluid Systems and Associated Components of Section 17.5.
Water-Cooled Nuclear Power Plants 1.9-4 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.9-1 (Sheet 4 of 8)
Conformance with Regulatory Guides Regulatory Applicable Guide Rev. Title SSAR Section Conformance(a) Comments 1.59 2 Design Basis Floods for Nuclear Power Plant 2.4.1 Conforms 2.4.2 Conforms 2.4.3 Conforms 2.4.4 Conforms 2.4.5 Conforms 2.4.6 Conforms No tsunami-induced flooding hazards are expected at the site. Operating procedures are addressed in the COLA.
2.4.7 Conforms 2.4.8 NA The CRN Site does not include cooling water canals or reservoirs.
2.4.9 Conforms Channel diversions as a result of changes to the river basin, associated with the CRN Site, are not expected to cause flooding hazards at the CRN Site.
2.4.10 Conforms The CRN Site is a dry site.
2.4.14 Conforms The CRN Site is a dry site.
1.60 2 Design Response Spectra for Seismic Design of 2.5.2 NA Site-specific vertical Ground Motion Response Spectra Nuclear Power Plants (GMRS) was developed using the guidance in RG 1.208.
1.76 1 Design-Basis Tornado and Tornado Missiles for 2.3.1 Conforms Nuclear Power Plants 1.78 1 Evaluating the Habitability of a Nuclear Power 2.2.1-2.2.2 Conforms Plant Control Room During a Postulated 2.2.3 Conforms Hazardous Chemical Release 1.91 2 Evaluations of Explosions Postulated to Occur at 2.2.1-2.2.2 Conforms Nearby Facilities and on Transportation Routes 2.2.3 Conforms Near Nuclear Power Plants 1.101 5 Emergency Response Planning and 13.3 NA An emergency action-level scheme will be adopted Preparedness for Nuclear Power Reactors consistent with industry standards developed to address SMR technology.
1.9-5 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.9-1 (Sheet 5 of 8)
Conformance with Regulatory Guides Regulatory Applicable Guide Rev. Title SSAR Section Conformance(a) Comments 1.102 1 Flood Protection for Nuclear Power Plants 2.4.1 Conforms The CRN Site is a dry site. Design and operational considerations are addressed in the COLA.
2.4.2 Conforms The CRN Site is a dry site. Design and operational considerations are addressed in the COLA.
2.4.3 Conforms The CRN Site is a dry site. Design and operational considerations are addressed in the COLA.
2.4.4 Conforms The CRN Site is a dry site. Design and operational considerations are addressed in the COLA.
2.4.5 Conforms The CRN Site is a dry site. Design and operational considerations are addressed in the COLA.
2.4.6 Conforms There are no tsunami-induced flood hazards at the CRN Site. Design and operational considerations are addressed in the COLA.
2.4.7 Conforms There are no ice-induced flooding hazards at the CRN Site. Design and operational considerations are addressed in the COLA.
2.4.8 Conforms The CRN Site layout does not include cooling water canals or reservoirs. The CRN Site is a dry site.
Design and operational considerations are addressed in the COLA.
2.4.9 Conforms Channel diversions are not expected to cause flooding at the CRN Site. Design and operational considerations are addressed in the COLA.
2.4.10 Conforms The CRN Site is a dry site. Design and operational considerations are addressed in the COLA.
2.4.14 Conforms The CRN Site is a dry site. Design and operational considerations are addressed in the COLA.
1.109 1 Calculation of Annual Doses to Man from Routine 2.4.13 Conforms Releases of Reactor Effluents for the Purpose of 11.2.3 Conforms Evaluating Compliance with 10 CFR 50, Appendix I 11.3.3 Conforms 1.9-6 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.9-1 (Sheet 6 of 8)
Conformance with Regulatory Guides Regulatory Applicable Guide Rev. Title SSAR Section Conformance(a) Comments 1.111 1 Methods for Estimating Atmospheric Transport 2.3.4 Conforms and Dispersion of Gaseous Effluents in Routine 2.3.5 Conforms Releases from Light-Water-Cooled Reactors 11.3.3 Conforms 1.112 1 Calculation of Releases of Radioactive Materials 11.2.3 NA Information related to the effluent source term is based in Gaseous and Liquid Effluents from upon vendor-provided information in the plant Light-Water-Cooled Nuclear Power Reactors parameter (PPE) approach. In-plant controls are addressed in the COLA.
11.3.3 NA Information related to the effluent source term is based upon vendor-provided information in the PPE approach. In-plant controls are addressed in the COLA.
1.113 1 Estimating Aquatic Dispersion of Effluents from 2.4.13 NA Information is applicable only when calculating Accidental and Routine Reactor Releases for the re-concentration in surface waters.
Purpose of Implementing Appendix I 11.2.3 Conforms 1.125 2 Physical Models for Design and Operation of 2.4.8 NA The site does not include cooling water canals or Hydraulic Structures and Systems for reservoirs.
Nuclear Power Plants 1.132 2 Site Investigations for Foundations of Nuclear 2.5.2 Conforms Investigation of borrow materials and materials suitable Power Plants for foundations is addressed in COLA.
2.5.3 NA Regulatory Guide 1.132 is no longer referenced in SRP Section 2.5.3.
2.5.4 Conforms Construction mapping is addressed in COLA.
2.5.5 Conforms 1.138 2(b) Laboratory Investigations of Soils and Rocks for 2.5.2 Conforms ASTM D7012-10 was used for testing related to Engineering Analysis and Design of Nuclear unconfined compression, as ASTM D2938 was Power Plants withdrawn and replaced by ASTM D7012.
2.5.4 Conforms ASTM D7012-10 was used for testing related to unconfined compression, as ASTM D2938 was withdrawn and replaced by ASTM D7012.
2.5.5 Conforms ASTM D7012-10 was used for testing related to unconfined compression, as ASTM D2938 was withdrawn and replaced by ASTM D7012.
1.9-7 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.9-1 (Sheet 7 of 8)
Conformance with Regulatory Guides Regulatory Applicable Guide Rev. Title SSAR Section Conformance(a) Comments 1.138 3(b) Laboratory Investigations of Soils and Rocks for 2.5.2 Exception This revision was issued after the completion of the Engineering Analysis and Design of Nuclear subsurface investigation. The following standards were Power Plants used that reflect revisions later than those identified in RG 1.138, Rev. 3: ASTM D3080/3080M-11, ASTM D2435/2435M-11, and ASTM D1557-12.
2.5.4 Exception This revision was issued after the completion of the subsurface investigation. The following standards were used that reflect revisions later than those identified in RG 1.138, Rev. 3: ASTM D3080/3080M-11, ASTM D2435/2435M-11, and ASTM D1557-12.
2.5.5 Exception This revision was issued after the completion of the subsurface investigation. The following standards were used that reflect revisions later than those identified in RG 1.138, Rev. 3: ASTM D3080/3080M-11, ASTM D2435/2435M-11, and ASTM D1557-12.
1.145 1 Atmospheric Dispersion Models for Potential 2.3.4 Conforms Accident Consequence Assessments at Nuclear 2.3.5 Conforms Power Plants 1.183 0 Alternative Radiological Source Terms for 15 NA Accident source term is defined in the PPE.
Evaluating Design Basis Accidents at Nuclear Vendor-specific source terms are addressed in the Power Reactors COLA.
1.198 0 Procedures and Criteria for Assessing Seismic 2.5.2 Conforms Soil Liquefaction At Nuclear Power Plant Sites 2.5.3 NA Regulatory Guide 1.198 is no longer referenced in SRP Section 2.5.3.
2.5.4 Conforms 2.5.5 Conforms 1.208 0 A Performance-Based Approach to Define the 2.5.1 Conforms Site-Specific Earthquake Ground Motion 2.5.2 Conforms 2.5.3 Conforms 1.221 0 Design-Basis Hurricane and Hurricane Missiles for 2.3.1 Conforms Nuclear Power Plants 1.9-8 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.9-1 (Sheet 8 of 8)
Conformance with Regulatory Guides Regulatory Applicable Guide Rev. Title SSAR Section Conformance(a) Comments 4.7 3 General Site Suitability Criteria for Nuclear Power 2.1.2 Conforms Stations 2.1.3 Conforms 2.2.1-2.2.2 Conforms 2.2.3 Conforms 2.3.4 Conforms 2.3.5 Conforms 2.5.1 Conforms 2.5.2 Conforms 2.5.3 Conforms 13.3 Exception Part 5A: TVA is requesting an exemption from certain elements of 10 CFR 50.33(g) and 10 CFR 50.47(c)(2) as they relate to the size of the Plume Exposure Pathway Emergency Planning Zone (EPZ). The Plume Exposure Pathway EPZ for the CRN Site described in Part 5A is at the site boundary.
Part 5B: TVA is requesting an exemption from certain elements of 10 CFR 50.33(g) and 10 CFR 50.47(c)(2) as they relate to the size of the Plume Exposure Pathway EPZ. The Plume Exposure Pathway EPZ for the CRN Site described in Part 5B is about 2 miles.
13.3.3.2 NA The ingestion exposure pathway EPZ for the CRN Site will be described in the COLA.
5.62 1 Reporting of Safeguards Events 13.3 Conforms (a) NA = Not applicable (b) Revision 3 of Regulatory Guide 1.138 was issued in December of 2014; however, the subsurface investigation for the CRN Site was conducted between June 2013 and March 2014, using the information in Regulatory Guide 1.138 in effect at that time (Revision 2).
1.9-9 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.9-2 (Sheet 1 of 6)
Conformance with Standard Review Plan Section of Applicable SSAR NUREG-0800 Rev. Title Section(s) Conformance(a) Comments 1.0 2 Introduction and Interfaces 1.1-1.11 Conforms Supplementary information related to reactor design and construction is addressed in the COLA, when a vendor has been selected.
2.0 0 Site Characteristics and Site Parameters 2.0 Conforms 2.1.1 3 Site Location and Description 2.1.1 Conforms 2.1.2 3 Exclusion Area Authority and Control 2.1.2 Conforms 2.1.3 3 Population Distribution 2.1.3 Conforms 2.2.1-2.2.2 3 Identification of Potential Hazards in Site 2.2.1-2.2.2 Conforms Vicinity 2.2.3 3 Evaluation of Potential Accidents 2.2.3 Conforms The locations, quantities, and effects of chemicals to be stored onsite are addressed in the COLA. Evaluations of the impacts of toxic gases on main control room habitability are addressed in the COLA.
2.3.1 3 Regional Climatology 2.3.1 Conforms 2.3.2 3 Local Meteorology 2.3.2 Conforms 2.3.3 3 Onsite Meteorological Measurements 2.3.3 Conforms Programs 2.3.4 3 Short Term Dispersion Estimates for Accident 2.3.4 Conforms Control room dispersion estimates are addressed in the Releases COLA.
2.3.5 3 Long-Term Atmospheric Dispersion Estimates 2.3.5 Conforms for Routine Releases 2.4.1 3 Hydrologic Description 2.4.1 Conforms The Tennessee River System, including the Clinch River arm of the Watts Bar Reservoir, is a regulated and fully developed system. Surges, seiches, tsunami, flooding caused by landslides and effects of ice formation are not credible for the CRN Site.
2.4.2 4 Floods 2.4.2 Conforms The Tennessee River System, including the Clinch River arm of the Watts Bar Reservoir, is a regulated and fully developed system. Surges, seiches, tsunami, flooding caused by landslides and effects of ice formation are not credible for the CRN Site.
2.4.3 4 Probable Maximum Flood (PMF) on Streams 2.4.3 Conforms and Rivers 1.9-10 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.9-2 (Sheet 2 of 6)
Conformance with Standard Review Plan Section of Applicable SSAR NUREG-0800 Rev. Title Section(s) Conformance(a) Comments 2.4.4 3 Potential Dam Failures 2.4.4 Conforms Design of structures is addressed in the COLA.
2.4.5 3 Probable Maximum Surge and Seiche Flooding 2.4.5 Conforms These events are not credible for the site because of its location, reservoir characteristics, and site history.
2.4.6 3 Probable Maximum Tsunami Hazards 2.4.6 Conforms There are no tsunami-induced flooding hazards expected at the CRN Site. Because the conditions at the site are not conducive to the creation of a tsunami, no propagation model has been developed and wave runup, inundation, and drawdown are not separately addressed.
2.4.7 3 Ice Effects 2.4.7 Conforms No safety-related SSCs are subject to ice-induced forces or blockages from sheet or frazil ice.
2.4.8 3 Cooling Water Canals and Reservoirs 2.4.8 Conforms The CRN Site does not include cooling water canals or reservoirs.
2.4.9 3 Channel Diversions 2.4.9 Conforms Requirements for alternative water sources are addressed in the COLA, when a reactor technology has been selected.
2.4.10 3 Flooding Protection Requirements 2.4.10 Conforms Based upon grade elevation and maximum flooding height, the site is considered to be dry; however, the need for flood protections is addressed in the COLA when detailed grading and reactor design are available.
Local PMP is addressed in the COLA, when detailed grading and reactor design are available.
2.4.11 3 Low Water Considerations 2.4.11 Conforms 2.4.12 3 Groundwater 2.4.12 Conforms Groundwater is not used for safety-related purposes.
The need for dewatering systems is addressed in the COLA.
2.4.13 3 Accidental Releases of Radioactive Liquid 2.4.13 Conforms Effluents in Ground and Surface Waters 2.4.14 3 Technical Specifications and Emergency 2.4.14 Conforms The site is considered to be dry and does not require Operation Requirements a safety-related source of water. By design, no emergency actions or Technical Specifications are required. Conformance with the general design criteria is not applicable to ESPAs.
2.5.1 5 Basic Geologic and Seismic Information 2.5.1 Conforms 1.9-11 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.9-2 (Sheet 3 of 6)
Conformance with Standard Review Plan Section of Applicable SSAR NUREG-0800 Rev. Title Section(s) Conformance(a) Comments 2.5.2 5 Vibratory Ground Motion 2.5.2 Conforms A sensitivity analysis was performed to evaluate the impact of the consideration of overburden on GMRS.
2.5.3 5 Surface Faulting 2.5.3 Conforms 2.5.4 5 Stability of Subsurface Materials and 2.5.4 Conforms Profiles illustrating the detailed relationship between Foundations the foundation and subsurface materials is provided in the COLA. While the foundation depth is provided, remaining information (e.g., information related to backfill and borrow) are provided in the COLA.
2.5.5 5 Stability of Slopes 2.5.5 Conforms Site grading are developed and stability of any safety-related slopes are addressed in the COLA.
3.5.1.6 4 Aircraft Hazards 3.5.1.6 Conforms 11.2 4 Liquid Waste Management System 11.2.3 Conforms Information related to design is addressed in the COLA.
11.3 3 Gaseous Waste Management System 11.3.3 Conforms Information related to design is addressed in the COLA.
13.3 3 Emergency Planning 13.3 Exception SRP Criterion 1:
Part 5A: TVA is requesting exemptions from certain elements of 10 CFR 50.47(b)(4)-(6), (9) and (10) and 10 CFR 50, Appendix E F.2, F.2.a, F.2.a(i)-(iii), and F.2.b-d as they relate to offsite emergency planning.
SRP Criterion 2:
Part 5A: TVA is requesting exemptions from certain elements of 10 CFR 50.47(b)(4)-(6), (9) and (10) and 10 CFR 50, Appendix E F.2, F.2.a, F.2.a(i)-(iii), and F.2.b-d as they relate to offsite emergency planning.
SRP Criterion 3:
Certain aspects of the technology-specific Emergency Action Levels (EALs) required by 10 CFR 50.47(b)(4) and 10 CFR 50 Appendix E Section IV.B are addressed in the COLA. An EAL scheme consistent with industry standards developed to address SMR technology will be adopted.
1.9-12 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.9-2 (Sheet 4 of 6)
Conformance with Standard Review Plan Section of Applicable SSAR NUREG-0800 Rev. Title Section(s) Conformance(a) Comments SRP Criteria 4-6:
Not applicable SRP Criterion 7:
Due to the Site Boundary EPZ, onsite and offsite protective measures are being implemented in an ad hoc manner.
Protective Action Recommendation (PAR) logic and PAR logic diagrams for the CRN Site are addressed and added to the Emergency Plan in the COLA.
SRP Criterion 9:
FEMA evaluations are beyond the scope of the Emergency Plan.
SRP Criterion 10:
TVA is requesting exemptions from certain elements of 10 CFR 50.33(g) and 10 CFR 50.47(c)(2) as they relate to EPZ sizing. The EPZ for the CRN Site described in Part 5A is at the site boundary.
The EPZ for the CRN Site described in Part 5B is about 2 miles.
SRP Criterion 11:
Part A: TVA is requesting exemptions from certain elements of 10 CFR 50, Appendix E, IV.2-IV.7 as they relate to Evacuation Time Estimates (ETEs). Due to the Site Boundary EPZ, an ETE is not being performed.
Part B: In Part 6 of the ESPA, TVA is requesting exemptions from certain elements of 10 CFR 50.33(g) and 10 CFR 50.47(c)(2) as they relate to EPZ sizing.
The EPZ for the CRN Site described in Part 5B is 2 miles. An ETE has been performed for the 2-mile EPZ.
1.9-13 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.9-2 (Sheet 5 of 6)
Conformance with Standard Review Plan Section of Applicable SSAR NUREG-0800 Rev. Title Section(s) Conformance(a) Comments SRP Criterion 12:
Not applicable SRP Criterion 13:
TVA is submitting an ESPA. The requirements of 10 CFR 50.47(b) and 10 CFR 50.47(d) are satisfied in the COLA.
SRP Criterion 14:
Not applicable SRP Criterion 16:
Part A: TVA is requesting exemptions from certain elements of 10 CFR 50, Appendix E, IV.2-IV.7 as they relate to ETEs. Due to the Site Boundary EPZ, an ETE is not being performed.
Part B: In Part 6 of the ESPA, TVA is requesting exemptions from certain elements of 10 CFR 50.33(g) and 10 CFR 50.47(c)(2) as they relate to EPZ sizing.
The EPZ for the CRN Site described in Part 5B is 2 miles. An ETE has been performed for the 2-mile EPZ.
SRP Criterion 19:
Part A: TVA is requesting exemptions from certain elements of 10 CFR 50.47(b)(5) and 10 CFR 50, Appendix E, D, D.3, and D.4 as they relate to notification measures and procedures regarding notifications to the public.
Part B: The CRN Site Alert and Notification System is being developed and implemented consistent with a Federal Emergency Management Agency (FEMA) approved design.
1.9-14 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 1.9-2 (Sheet 6 of 6)
Conformance with Standard Review Plan Section of Applicable SSAR NUREG-0800 Rev. Title Section(s) Conformance(a) Comments SRP Criterion 20:
For the ESPA, Parts 5A and 5B are being submitted as major features Emergency Plans in accordance with 10 CFR 52.17(b)(2)(i).
SRP Criteria 21-24:
Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) are developed and submitted in the COLA.
SRP Criteria 25-29:
Not applicable SRP Criterion 31:
Emergency Plans Parts 5A and 5B are being submitted as part of an ESPA.
13.6.3 1 Physical Security - Early Site Permit 13.6 Conforms 15.0.3 0 Design Basis Accident Radiological 15 Conforms Consequences of Analyses for Advanced Light Water Reactors 17.5 1 Quality Assurance Program Description - 17.5 Exception The CRN ESP Quality Assurance Program utilizes the Design Certification, Early Site Permit and New TVA Nuclear Quality Assurance Program License Applicants (TVA-NQA-PLN89-A), as supplemented by Appendices K, L, and M, to provide equivalents and alternatives to the implementing documents endorsed in RG 1.28, Revision 4. As discussed in Section 17.5, this approach provides an acceptable alternative to conforming to the guidance in NUREG-0800, Section 17.5, for compliance with the requirements of 10 CFR 50, Appendix B.
(a) NA = Not applicable 1.9-15 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report 1.10 IMPACT OF CONSTRUCTION OF NEW NUCLEAR POWER PLANT UNITS ON OPERATING UNITS AT MULTI-UNIT SITES This topic is not applicable to this Early Site Permit Application and is addressed at the combined license application stage.
1.10-1 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report 1.11 OVERVIEW OF REACTOR TYPES Four conceptual, light-water cooled, small modular reactor (SMR) designs were used to create a surrogate plant as defined in NEI 10-01, Industry Guideline for Developing a Plant Parameter Envelope in Support of an Early Site Permit (Reference 1.11-1) and to develop the site-related design parameter values listed in Table 2.0-2 of Chapter 2. A basis summary for each plant parameter is typically provided in the SSAR section indicated in Table 2.0-2 for that plant parameter. The reactor designs are:
BWXT mPower' (Generation mPower LLC design)
NuScale (NuScale Power, LLC, design)
SMR-160 (Holtec SMR, LLC, design)
Westinghouse SMR (Westinghouse Electric Company, LLC, design)
All four designs are described as passively safe with minimal or no reliance on offsite power, offsite water, or operator action for safety. Based on design features, these designs eliminate various conventional design basis events (e.g., large-break LOCAs precluded by elimination of large bore piping). All four designs are integral pressurized water reactors (iPWRs); that is, pressurized water reactor (PWR) designs in which the primary coolant system and all (or most) of its components (i.e., pressurizer, steam generators, and reactor coolant pumps, where applicable) are enclosed in one pressure vessel.
1.11.1 BWXT mPower' The BWXT mPower' SMR is an advanced iPWR that generates 530 MWt, with an estimated power output of 180 MWe. The mPower reactor uses standard PWR fuel with a shorter fuel assembly length. The iPWR is located in a below-grade containment.
The mPower SMR is designed to be built in multiples of two reactors per plant, and up to two plants (four reactors) would be placed on the CRN Site.
1.11.2 NuScale The NuScale SMR is an advanced iPWR that generates 160 MWt, with an estimated power output of 50 MWe. The NuScale SMR uses standard light water reactor fuel with a shorter fuel assembly length. The reactor sits within a containment vessel, and up to 12 reactors can be housed in one below-grade shared pool.
The NuScale SMR is a multi-unit configuration that is designed to include up to 12 reactors per plant, and up to 12 reactors would be placed on the CRN Site.
1.11.3 SMR-160 The Holtec Inherently-Safe Modular Underground Reactor (HI-SMURTM) SMR-160 is an iPWR that generates 525 MWt, with an estimated power output of 160 MWe. This reactor design does not use standard fuel. Instead, it uses a unitary cartridge containing all fuel that is replaced entirely each refueling. The reactor, steam generator, and spent fuel pool are located inside the containment structure. The reactor core is located below grade.
Each unit is built as a stand alone plant, and up to four SMR-160 reactors would be placed on the CRN Site.
1.11-1 Revision 2
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report 1.11.4 Westinghouse SMR The Westinghouse SMR is an advanced iPWR that generates 800 MWt, with an estimated power output of 225 MWe. The Westinghouse SMR uses standard PWR fuel, with a shorter fuel assembly length. The iPWR vessel is housed in a containment located below grade.
Each unit is built as a stand-alone plant, and up to three Westinghouse SMRs would be placed on the CRN Site.
1.11.5 Reference 1.11-1. NEI 10-01, Industry Guidance for Developing a Plant Parameter Envelope in Support of an Early Site Permit, Rev. 1, May 2012.
1.11-2 Revision 2