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Category:Site Safety Analysis Report (SSAR)
MONTHYEARML19029A5322019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.01 - Geography and Demography ML19029A5772019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.12C - Groundwater Flow Model ML19029A5222019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Table of Contents ML19029A5262019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 01 - General and Administrative Information - Introduction and General Description ML19029A5292019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.00 - Plant Parameter Envelope ML19029A5342019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.02 - Nearby Industrial, Transportation, and Military Facilities ML19029A5372019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.03 - Meteorology ML19029A5392019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.00 - Hydrology Review ML19029A5412019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.01 - Hydrologic Description ML19029A5432019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.02 - Floods ML19029A5472019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.03 - Probable Maximum Flood on Streams and Rivers ML19029A5492019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.04 - Potential Dam Failures ML19029A5512019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.05 - Probable Maximum Surge and Seiche Flooding ML19029A5542019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.06 - Probable Maximum Tsunami Hazards ML19029A5562019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.07 - Ice Effects ML19029A5582019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.08 - Cooling Water Canals and Reservoirs ML19029A5612019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.09 - Channel Diversions ML19029A5632019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.10 - Flooding Protection Requirements ML19029A5652019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.11 - LOW Water Considerations ML19029A5682019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.12 - Groundwater ML19029A5702019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.12A - List of Water Systems in EPA Safe Drinking Water Information System ML19029A5732019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.12B - Aquifer Pumping Test Results ML19029A5792019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.13 - Accidental Releases of Liquid Effluents to Ground and Surface Waters ML19029A5812019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.14 - Technical Specifications and Emergency Operation Requirements ML19029A5832019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.05.01 - Geologic Characterization Information ML19029A5862019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.05.01 - Geologic Characterization Information - Figures 01-35 ML19029A5892019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.05.01 - Geologic Characterization Information - Figures 36-63 ML19029A5952019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.05.01 - Geologic Characterization Information - Figures 64-92 ML19029A5982019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.05.02 - Vibratory Ground Motion ML19029A6012019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.05.03 - Surface Deformation ML19029A6032019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.05.04 - Stability of Subsurface Materials and Foundations ML19029A6072019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.05.05 - Stability of Slopes ML19029A6132019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 03 - Design of Structures, Systems, Components, and Equipment ML19029A6172019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 11 - Radioactive Waste Management ML19029A6192019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 13 - Conduct of Operations ML19029A6232019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 15 - Accident Analysis ML19029A6272019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 17 - Quality Assurance ML19030A2752019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Table of Contents ML19030A3422019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.05.03 - Surface Deformation ML19030A3172019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.12B - Aquifer Pumping Test Results ML19030A3202019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.12C - Groundwater Flow Model ML19030A3232019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.13 - Accidental Releases of Liquid Effluents to Ground and Surface Waters ML19030A3252019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.04.14 - Technical Specifications and Emergency Operation Requirements ML19030A3272019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.05.01 - Geologic Characterization Information ML19030A3302019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.05.01 - Geologic Characterization Information - Figures 01-35 ML19030A3332019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.05.01 - Geologic Characterization Information - Figures 36-63 ML19030A3362019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.05.01 - Geologic Characterization Information - Figures 64-92 ML19030A3392019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 02 - Site Characteristics - Section 02.05.02 - Vibratory Ground Motion ML19030A3502019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 11 - Radioactive Waste Management ML19030A3552019-01-18018 January 2019 Part 02 Ssar (Rev. 2) - Part 02 - Ssar - Chapter 17 - Quality Assurance 2019-01-18
[Table view] Category:License-Application for Early Site Permit (ESP)
MONTHYEARML19030A5012019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Subsurface Data Report - Appendix B.1 - Pages 70-77 ML19030A4152019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 02 - Section 02.08 - Noise ML19030A4172019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 02 - Section 02.09 - Related Federal Project Activities ML19030A4202019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 03 - Plant Description ML19030A4222019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 04 - Environmental Impacts of Construction ML19030A4242019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 05 - Section 05.01 - Environmental Impacts of Station Operation ML19030A4262019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 05 - Section 05.02 - WATER-RELATED Impacts ML19030A4282019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 05 - Section 05.03 - Cooling System Impacts ML19030A4302019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 05 - Section 05.04 - Radiological Impacts of Normal Operation ML19030A4322019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 05 - Section 05.05 - Environmental Impacts of Waste ML19030A4342019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 05 - Section 05.06 - Transmission System Impacts ML19030A4362019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 05 - Section 05.07 - Uranium Fuel Cycle and Transportation Impacts ML19030A4392019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 05 - Section 05.08 - Socioeconomic Impacts ML19030A4412019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 05 - Section 05.09 - Decommissioning Impacts ML19030A4422019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 05 - Section 05.10 - Measures and Controls to Limit Adverse Impacts During Operation ML19030A4442019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 05 - Section 05.11 - Cumulative Impacts Related to Station Operation ML19030A4472019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 06 - Environmental Measurements and Monitoring Programs ML19030A4492019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 07 - Environmental Impacts of Postulated Accidents Involving Radioactive Materials ML19030A4502019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 08 - Need for Power ML19030A4532019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 09 - Alternatives ML19030A4552019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 10 - Environmental Consequences of the Proposed Action ML19030A4582019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Appendix a - Consultation - Pages 0-A6 ML19030A4602019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Appendix a - Consultation - Pages A7-A11 ML19030A4632019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Appendix a - Consultation - Pages A12-A34 ML19030A4662019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Appendix a - Consultation - Pages A35-A46 ML19030A4692019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Appendix a - Consultation - Pages A47-A52 ML19030A4712019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Appendix a - Consultation - Pages A53-A54 ML19030A4742019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Appendix a - Consultation - Pages A55-A64 ML19030A4762019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Appendix a - Consultation - Pages A65-A91 ML19030A4772019-01-18018 January 2019 Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Appendix B - Environmental Protection Plan ML19030A4812019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Site Vicinity Geologic Map Plates - Plate 1 ML19030A4822019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Site Vicinity Geologic Map Plates - Plate 2A ML19030A4832019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Site Vicinity Geologic Map Plates - Plate 2B ML19030A4842019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Site Vicinity Geologic Map Plates - Plate 2C CNL-19-018, Resubmittal of Clinch River Nuclear Site Early Permit Application, Revision 22019-01-18018 January 2019 Resubmittal of Clinch River Nuclear Site Early Permit Application, Revision 2 ML19030A4862019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Site Vicinity Geologic Map Plates - Plate 2D ML19030A4872019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Index ML19030A4882019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - TVA Quality Assurance Program - Nuclear Quality Assurance Plan ML19030A4892019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Subsurface Data Report - Pages 1-46 ML19030A4902019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Subsurface Data Report - Pages 47-82 ML19030A4912019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Subsurface Data Report - Appendix a - Pages 1-9 ML19030A4922019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Subsurface Data Report - Appendix a - Pages 10-18 ML19030A4932019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Subsurface Data Report - Appendix B.1 - Pages 1-22 ML19030A4942019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Subsurface Data Report - Appendix B.1 - Pages 23-28 ML19030A4952019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Subsurface Data Report - Appendix B.1 - Pages 29-40 ML19030A4962019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Subsurface Data Report - Appendix B.1 - Pages 41-44 ML19030A4982019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Subsurface Data Report - Appendix B.1 - Pages 45-52 ML19030A4992019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Subsurface Data Report - Appendix B.1 - Pages 53-60 ML19030A5002019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Subsurface Data Report - Appendix B.1 - Pages 61-69 ML19030A5352019-01-18018 January 2019 Part 08 Enclosures (Rev. 2) - Part 08 - Enclosures - Subsurface Data Report - Appendix B.1 - Pages 353-361 2019-01-18
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Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report CHAPTER 15 TABLE OF CONTENTS Section Title Page CHAPTER 15 ACCIDENT ANALYSIS ................................................................................. 15-1 15.1 Accident Selection .......................................................................................... 15-1 15.2 Source Term ................................................................................................... 15-2 15.3 Evaluation Methodology and Conclusions ...................................................... 15-2 15.4 References...................................................................................................... 15-3 15-i Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report CHAPTER 15 LIST OF TABLES Number Title 15-1 Clinch River Nuclear Site Loss of Coolant Accident Doses 15-ii Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report CHAPTER 15 ACCIDENT ANALYSIS 15.1 ACCIDENT SELECTION The evaluation of nuclear power plant safety includes analysis of the plant response to a spectrum of postulated disturbances in process variables and postulated equipment failures.
However, it is neither practical nor necessary to analyze all historically postulated design basis accidents (DBAs) associated with the small modular reactor (SMR) types under consideration for the Clinch River Nuclear (CRN) Site in the early site permit application (ESPA), as discussed below.
As noted in NEI 10-01, Industry Guidance for Developing a Plant Parameter Envelope in Support of an Early Site Permit (Reference 15-1), accident analyses model the time-dependent transport of radionuclides out of the reactor core through several pathways, each with different time-dependent removal mechanisms for radionuclides. Different reactor designs have different release pathways, and each pathway has different release rates and different radionuclide removal mechanisms. Given these differences, it is not possible to develop a bounding analysis for use in a plant-parameter-envelope-based ESPA, and accordingly, for the purposes of evaluating offsite post-accident doses, the vendor analysis with the highest resultant post-accident dose was selected for use in the CRN Site-specific dose analysis presented here.
At this time, the site layout and building configuration for each proposed reactor design for the CRN Site has yet to be determined, making it impractical to model near-field atmospheric dispersion around buildings in order to determine doses in the main control room and other areas where habitability is required post-accident. Thus, these types of detailed accident analyses are more appropriately performed at the Combined License Application (COLA) stage, when a technology is selected and the orientation of the plant on the site is known.
Experience with other pressurized water reactor (PWR) designs, as documented in ESPAs to date, has shown that offsite doses due to a postulated loss of coolant accident (LOCA) are expected to more closely approach 10 CFR 52.17 limits than other DBAs that may have a greater probability of occurrence but a lesser magnitude of activity release, as evidenced by the following:
Clinton ESP Site, ESPA, Site Safety Analysis Report (SSAR), Table 3.3-2 (Reference 15-2)
Grand Gulf ESP Site, ESPA, SSAR, Table 3.3-1 (Reference 15-3)
North Anna ESP Site, ESPA, SSAR, Table 15.4-1 (Reference 15-4)
PSEG Site, ESPA, SSAR, Tables 15.4-2, 15.4-10 and 15.4-19 (Reference 15-5)
Victoria County Station, ESPA, SSAR, Table 15.1-5 (Reference 15-6)
Vogtle ESP Site, ESPA, SSAR, Table 15-12 (Reference 15-7)
Each of the four small modular PWR designs under consideration for the CRN Site is expected to include advanced design features that would further minimize accident consequences (see Section 1.11). In particular, based on initial design feedback, TVA anticipates that the consequences of a LOCA will be less than those for large PWR designs and that no events of greater consequence will be identified.
Thus, analysis of postulated DBAs other than a LOCA is not necessary for the ESPA, because the maximum potential offsite doses have been evaluated, demonstrating the ability of the site to 15-1 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report comply with the dose limits in 10 CFR 52.17. The COLA verifies that the accident doses provided in this ESPA are bounded or provides an evaluation of accident radiological consequences.
15.2 SOURCE TERM The bounding design basis accident (LOCA) source term is provided in Table 2.0-3.
The LOCA source term (radionuclide activity released to the environment) selected for inclusion in the plant parameter envelope (PPE) is based upon vendor input and represents the design with the highest resulting doses at the exclusion area boundary (EAB) and the low population zone (LPZ) boundary from the four SMR designs under consideration. Key input parameters associated with the accident source term in the PPE have been evaluated to assess their reasonableness for and representativeness of SMR designs.
The PPE LOCA source term is based on a design that uses standard light-water reactor fuel, which is representative of the SMR designs under consideration, and assumes a core power level for a single unit at 800 MW thermal. The methodology and analytical techniques used for development of the source term are similar to those used for large light water reactors, and TVA anticipates that comparable methodologies and techniques will be used in the development of the SMR accident source terms to be presented in the SMR design control documents.
To assess reasonableness, a comparison of the PPE LOCA source term to that of the AP1000 design (as provided in the Vogtle 3 and 4 ESPA, Reference 15-7) was performed, scaling the source term presented in the Vogtle ESPA by a factor of 0.235 (800 MWt/3400 MWt) to account for the smaller core thermal power of the SMR designs being considered for the CRN Site. The activity release associated with the worst 2-hour time period of the scaled-down AP1000 is approximately 25 percent greater than that for the surrogate plant (as provided in the PPE). This difference is reasonable given that SMR designs contain additional safety features that will result in general improvements over the AP1000 design. The activity release for the 30-day duration of the LOCA is approximately equivalent to that of the surrogate plant and is also considered reasonable.
The source terms developed for the surrogate plant are representative of the potential SMR designs considering core power and average burnup. The surrogate plant assumes a core power that is bounding but representative of the remaining SMR designs being considered. Core burnup was also reviewed. The maximum average burnup assumed for the surrogate plant is 51 GWD/MTU, while the maximum average burnup for the remaining SMR designs is less than 41 GWD/MTU. Although it is recognized that core power and burnup do not necessarily result in one-to-one ratios to activity releases, it is anticipated the larger core power and burnup would result in larger activity releases than those associated with the remaining SMR designs.
15.3 EVALUATION METHODOLOGY AND CONCLUSIONS Doses for a LOCA are evaluated at the EAB and LPZ boundary.
The evaluation uses the following parameters, as shown in Table 15-1:
Short-term 95th percentile accident atmospheric dispersion factors (/Qs) for the CRN Site.
Bounding vendor-provided LOCA doses.
/Q values associated with the bounding vendor-provided LOCA doses.
15-2 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Doses are calculated based on the amount of activity released to the environment, the dispersion of activity during transport to the receptor (/Q), the breathing rate at the receptor, and the applicable dose conversion factors. The only parameters that are site-specific are the /Qs.
Hence, it is reasonable to adjust the vendor LOCA doses for site-specific /Qs values.
For a given time step, the vendor dose is multiplied by the ratio of the site-specific /Q to the vendor /Q, as shown in the following equation:
DoseSite = DoseVendor [(/Q)Site/(/Q)Vendor] Equation 15-1 The resulting accident doses are expressed as total effective dose equivalent (TEDE), consistent with 10 CFR 52.17. All site LOCA doses meet the 25 rem TEDE limit specified in 10 CFR 52.17 as shown in Table 15-1.
15.4 REFERENCES
15-1. NEI 10-01, Industry Guideline for Developing a Plant Parameter Envelope in Support of an Early Site Permit, Nuclear Energy Institute, Rev. 1, May 2012.
15-2. Exelon Nuclear, Early Site Permit (ESP) Application for the Clinton ESP Site, Rev. 4, April 14, 2006.
15-3. Entergy, System Energy Resources, Inc., Grand Gulf Early Site Permit Application, Rev. 2, October 3, 2005.
15-4. Dominion, Dominion Nuclear North Anna, LLC, North Anna Early Site Permit Application, Rev. 9, September 12, 2006.
15-5. PSEG Power, LLC, Application for Early Site Permit for the PSEG Site, Rev. 3, March 31, 2014.
15-6. Exelon Generation, Exelon Nuclear Texas Holdings, LLC, Application for Early Site Permit for Victoria County Station, Rev. 1, May 1, 2012.
15-7. Southern Company, Southern Nuclear Operating Company, Inc., Vogtle Early Site Permit Application, Rev. 5, December 23, 2008.
15-3 Revision 1
Clinch River Nuclear Site Early Site Permit Application Part 2, Site Safety Analysis Report Table 15-1 Clinch River Nuclear Site Loss of Coolant Accident Doses
/Q (s/m3) Dose (rem TEDE)
/Q Ratio Location Time (hr) Site (95th %) Vendor (Site/Vendor) Vendor Site EAB 0-2 4.96x10-3 1.0x10-3 4.96 4.35 21.6(a)
LPZ 0-8 3.10x10-4 5.0x10-4 0.620 4.44 2.75 8-24 2.26x10-4 3.0x10-4 0.753 0.20 0.15 24-96 1.14x10-4 1.5x10-4 0.760 0.05 0.038 96-720 4.30x10-5 8.0x10-5 0.538 0.06 0.032 LPZ Total 4.75 2.97(a),(b)
(a) As compared to the 25 rem Total Effective Dose Equivalent (TEDE) limit specified in 10 CFR 52.17.
(b) Column total does not equal sum of individual values due to rounding.
Notes:
LPZ = Low Population Zone 15-4 Revision 1