ML17033B550
| ML17033B550 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/29/2016 |
| From: | V Sreenivas Plant Licensing Branch II |
| To: | Heacock D Virginia Electric & Power Co (VEPCO) |
| Sreenivas V, NRR/DORL/LPL2-1, 415-2597 | |
| Shared Package | |
| ML17033B477 | List: |
| References | |
| Download: ML17033B550 (362) | |
Text
North Anna Power Station Updated Final Safety Analysis Report Chapter 11 Intentionally Blank
Intentionally Blank Revision 52-09/29/2016 NAPS UFSAR 11-iChapter 11: Radioactive Waste ManagementTable of ContentsSectionTitle Page11.1SOURCE TERMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.1-111.1.1Radioactivity. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.1-111.1.1.1Activities in the Core. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.1-1 11.1.1.2Activities in the Fuel Rod Gap . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.1-1 11.1.1.3Activities in the Reactor Coolant. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.1-311.1.1.4Activities in Secondary Side . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.1-411.1.1.5Activities in the Volume Control Tank. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.1-4 11.1.1.6Activities in the Pressurizer. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.1-411.1.1.7Activities in the Demineralizer Resin . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.1-511.1.2Leakage Rates. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.1-511.1References. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11
.1-511.2LIQUID WASTE DISPOSAL SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.2-111.2.1Design Objectives. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.2-1 11.2.2System Description. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.2-211.2.2.1Condensate Polishing System Resin Waste Dispos al . . . . . . . . . . . . . . . . . . .11.2-211.2.2.2Ion Exchange Filtration System (IEFS). . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.2-211.2.3Operating Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.2-4 11.2.4Performance Tests. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.2-511.2.5Estimated Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.2-5 11.2.5.1Estimated Activities in North Anna Reservoir and Waste Heat Treatment Facility . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.2-711.2.6Release Points. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.2-1 111.2.7Dilution Factors. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.2-1 111.2.8Estimated Doses from Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.2-1211.2Reference Drawings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.2-1411.3GASEOUS WASTE DISPOSAL SYSTEM . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-111.3.1Design Objectives. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-111.3.2System Description. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-111.3.3Operating Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-311.3.3.1Ventilation Vent Subsystem . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.3-411.3.3.2Safety Considerations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-411.3.4Performance Tests. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-411.3.5Estimated Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.3-5 Revision 52-09/29/2016 NAPS UFSAR 11-iiChapter 11: Radioactive Waste ManagementTable of Contents (continued)SectionTitle Page11.3.5.1Waste Gas Decay Tanks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-511.3.5.2Boron Recovery Tanks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-611.3.5.3Boron Recovery Test Tanks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-611.3.5.4Refueling Water Storage Tanks. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.3-711.3.5.5Primary-Grade Water Tanks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-711.3.5.6High-Level Liquid Waste System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-711.3.5.7Containment Purge . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-8 11.3.5.8Auxiliary Building Vent . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-811.3.5.9Steam Generator Blowdown Tank Vent . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-911.3.5.10Secondary Steam Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.3-911.3.6Release Points. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-911.3.7Dilution Factors. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-911.3.8Estimated Doses from Gaseous Effluents. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.3-1011.3Reference Drawings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-1111.4PROCESS AND EFFLUENT RADIATION M ONITORING SYSTEM . . . . . . .11.4-111.4.1Design Objectives. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.4-111.4.2Continuous Monitoring. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.4-111.4.2.1Anticipated Concentrations, Se nsitivities, and Ranges. . . . . . . . . . . . . . . . . .11.4-211.4.2.2Process Vent Particulate Monitor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.4-411.4.2.3Process Vent Gas Monitor. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.4-4 11.4.2.4Ventilation Vent A Particulate Monitor and Ventilation Vent A Gas Monitor11.4-411.4.2.5Ventilation Vent B Particulate Monitor and Ventilation Vent B Gas Monitor11.4-411.4.2.6Ventilation Vent Multiport Sampler Part iculate and Ventilation Vent Multiport Sampler Gas Monitor. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.4-511.4.2.7Component Cooling-Water Monitor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.4-511.4.2.8Component Cooling Heat Exch anger Service-Water Monitor . . . . . . . . . . . .11.4-511.4.2.9Service-Water Discharge to Canal Monitor . . . . . . . . . . . . . . . . . . . . . . . . . .11.4-511.4.2.10Service Water Discharge to Service Water Reservoir Monitor. . . . . . . . . . . .11.4-611.4.2.11Recirculation Spray Cooler-Service Water Ou tlet Monitors . . . . . . . . . . . .11.4-611.4.2.12Liquid Waste Disposal System M onitors . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.4-611.4.2.13Condenser Air Ejector Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.4-611.4.2.14Steam Generator Blowdown Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.4-711.4.2.15Reactor Coolant Letdow n Gross Activity Monitors . . . . . . . . . . . . . . . . . . . .11.4-711.4.2.16Circulating-Water Disc harge Tunnel Monitors. . . . . . . . . . . . . . . . . . . . . . . .
11.4-7 Revision 52-09/29/2016 NAPS UFSAR 11-iiiChapter 11: Radioactive Waste ManagementTable of Contents (continued)SectionTitle Page11.4.2.17Containment Particulate Monitors. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.4-811.4.2.18Containment Gas Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.4-811.4.2.19Spare Channels . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.4-811.4.3Post-Accident Monitoring. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.4-811.4.3.1Normal and High-Range Effluent Gas Monitors. . . . . . . . . . . . . . . . . . . . . . .11.4-911.4.3.2High-Range Effluent Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.4-1211.4.4Sampling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.
4-1311.4.4.1Liquid Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.4-1311.4.4.2Gaseous Systems. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.4-1511.4.5Calibration and Maintenance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.4-16 11.4Reference Drawings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.4-1611.5SOLID WASTE SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.5-111.5.1Design Objectives. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.5-111.5.2System Inputs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.5-111.5.2.1Spent Resins . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.5-1 11.5.2.2Evaporator Bottoms. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.5-211.5.2.3Clarifier Sludge . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.5-211.5.2.4Miscellaneous Solid Waste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.5-2 11.5.3Equipment and Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.5-211.5.3.1Solidification Operation. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.5-211.5.3.2Baling Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.5-211.5.3.3Spent Resin Handling Operation. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.5-211.5.3.4Spent Filter Cartridge Handling Operation . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.5-311.5.4Estimated Volumes. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.5-311.5.5Packaging . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.5
-411.5.6Shipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.
5-511.5Reference Drawings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.5-511.6OFFSITE RADIOLOGICAL MONITORING PROGRAM . . . . . . . . . . . . . . . . .11.6-111.6.1Background. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.6-111.6.2Critical Pathways. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.6-111.6.3Sampling Media, Locations, and Frequency. . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.6-111.6.3.1Air Monitoring - Radiogas and Air Particulate. . . . . . . . . . . . . . . . . . . . . . . .
11.6-111.6.3.2Milk. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.6-2 Revision 52-09/29/2016 NAPS UFSAR 11-ivChapter 11: Radioactive Waste ManagementTable of Contents (continued)SectionTitle Page11.6.3.3Vegetation, Crops, and Feed . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.6-211.6.3.4Soil, Surface Water, and Wells . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.6-211.6.3.5Precipitation. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.6-211.6.3.6Silt and Fish. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.6-311.6.4Analytical Sensitivity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.6-311.6.5Data Analysis and Presentation. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.6-311.6.6Program Statistical Sensitivity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11.6-3 Appendix 11ATritium Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11A-i11A.1SYSTEM SOURCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11A-111A.1.1The Fission Source . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11A-1 11A.1.2Boric Acid Source. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11A-111A.1.3Secondary Source Assemblies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11A-211A.1.4Burnable Poison Rod Source. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11A-211A.1.5Minor Sources. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11A-211A.2DESIGN BASES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11A-211A.3DESIGN EVALUATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11A-211AReferences. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11A
-5 Appendix 11BRadiation Exposure Evaluation for Esti mated Radioactive Effluents. . .11B-i11B.1INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-111B.2
SUMMARY
AND CONCLUSIONS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-111B.2.1Maximum Individual Exposure. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11B-211B.2.2Population Exposure. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-311B.2.3Conclusions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-411B.3RADIATION EXPOSURE FROM GASEOUS EFFL UENTS . . . . . . . . . . . . . . .11B-511B.3.1Projected Gaseous Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11B-511B.3.2External Exposure From Gaseous Effluents. . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-511B.3.2.1Maximum Individual External Exposure. . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11B-511B.3.2.2External Population Exposure. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11B-611B.3.3Internal Exposure From Gaseous Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11B-7 Revision 52-09/29/2016 NAPS UFSAR 11-vChapter 11: Radioactive Waste ManagementTable of Contents (continued)SectionTitle Page11B.3.3.1Internal Exposure From Released Noble Gases . . . . . . . . . . . . . . . . . . . . . . .11B-711B.3.3.2Internal Exposure From Released Radioiodine. . . . . . . . . . . . . . . . . . . . . . . .11B-711B.3.3.3Internal Exposure From Particulates. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-911B.4RADIATION EXPOSURE FROM LIQUID EFFLUE NTS . . . . . . . . . . . . . . . . .11B-911B.4.1Maximum Individual Radiation Exposure From Liquid Effluents. . . . . . . . . . .11B-911B.4.1.1Internal Exposure From Water Ingestion . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-1011B.4.1.2Internal Exposure From Fish I ngestion. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-1011B.4.1.3External Exposure From Swimming or Boating. . . . . . . . . . . . . . . . . . . . . . .
11B-1111B.4.1.4External Exposure From Sunbathing. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11B-1211B.4.1.5Radiation Exposure From Other S ources . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-1211B.4.2Population Radiation Exposure Fr om Liquid Effluents . . . . . . . . . . . . . . . . . . .11B-1211B.4.2.1Population Exposure From Water Ingestion . . . . . . . . . . . . . . . . . . . . . . . . . .
11B-1311B.4.2.2Population Exposure From Fish I ngestion . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-1311B.4.2.3Population Exposure From Swimming, Boating, and Sunbathing . . . . . . . . .11B-1411B.5DOSE TOTALS AND COMPARISON WITH FEDERAL REGULATIONS AND NATURAL BACKGROUND . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11B-1411B.6COMPUTATIONAL METHODS FOR DOSES RESULTING FROM GASEOUS EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-1511B.6.1Whole-Body Noble Gas Immersion Do se. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-1511B.6.2Thyroid Inhalation Dose . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-1711B.6.3Child Thyroid Milk Ingestion Dose Model. . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-1711B.7COMPUTATIONAL METHODS FOR DOSES RESULTING FROM LIQUID EFFLUENTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-1811B.7.1Whole-Body and Body-Organ Ex posure From Water Ingestion . . . . . . . . . . . .11B-1811B.7.2Whole-Body and Body-Or gan Exposure From Fish Ingestion. . . . . . . . . . . . . .11B-1811BReferences. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B
-20 Appendix 11CEvaluation of Compliance With Proposed 10 CFR 50, Appendix I. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11C-i Revision 52-09/29/2016 NAPS UFSAR 11-viChapter 11: Radioactive Waste ManagementTable of Contents (continued)SectionTitle Page11C.1
SUMMARY
AND CONCLUSIONS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11C-111C.2DOSES FROM LIQUID EFFLUENTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11C-311C.3DOSES FROM GASEOUS EFFLUENTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11C-411C.4DATA AND METHODOLOGY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11C-611C.4.1Plant Characteristics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11C-611C.4.1.1General. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11 C-611C.4.1.2Primary System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11C-611C.4.1.3Secondary System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11C-711C.4.1.4Liquid Waste Processing System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11C-911C.4.1.5Gaseous Waste Processing System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11C-911C.4.1.6Ventilation and Exhaust Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11C-1011C.4.1.7Solid Waste Processing Systems. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11C-1111C.4.2Distances to Radiologically Si gnificant Locations. . . . . . . . . . . . . . . . . . . . . . .11C-1111C.4.3Atmospheric Dilution (c/Q) a nd Deposition (D/Q) Parameters . . . . . . . . . . . . .11C-1211C.4.4Meteorological Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11C-1411C.4.5Topography. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11C-1 611C.5SOURCE-TERM INFORMATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11C-1711CReferences. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11C-18 Revision 52-09/29/2016 NAPS UFSAR 11-viiChapter 11: Radioactive Waste ManagementList of TablesTableTitle PageTable 11.1-1Core and Gap Activities 15 x 15 Fuel Assembly Array a . . . . . . . . . . .11.1-6Table 11.1-2Core Temperature Distribution 15 x 15 Fuel Assembly Array . . . . . . .11.1-6Table 11.1-3Nuclear Characteristi cs of Highest Rated Discharged Fuel Assembly .11.1-7Table 11.1-4Activities in Highest Rated Discharged Assembly at Time of Reactor Shutdown (Ci). . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.1-8Table 11.1-5Parameters used in the Calc ulation of Reactor Coolant Fission Product Activities (15 x 15 Fuel Assembly) . . . . . . . . . . . . . . . . . . . . .11.1-9Table 11.1-6Concentration of Principal Fission Products in Primary Coolant with 1.0%
Failed Fuel (mCi/cm3)
- a. . . . . . . . . . . .11.1-11Table 11.1-7Concentration of Principal Products in Steam Generator Liquid with 1.0% Failed Fuel (µCi/cm 3) a. . . . . . . . .11.1-12Table 11.1-8Concentration of Princi pal Noble Gases and Halogens in Secondary Side Steam with 1.0% Failed Fuel (mCi/lb) . . . . . . . . . . . .11.1-13Table 11.1-9Parameters Used to Describe the Pressurized Water Reactor with U-Tube Steam Generators (Volatile Chemistry). . . . . . . . . . . . . . . . . .11.1-14Table 11.1-10Source Terms for PWR with U-Tube Steam Generators. . . . . . . . . . . .11.1-15Table 11.1-11Volume Control Tank Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.1-19Table 11.1-12Pressurizer Activities a. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.1-20Table 11.1-13Specific Source Strength . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.1-21Table 11.1-14Leakage Rates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.1-22Table 11.2-1Liquid Waste Disposal Equipment Design Data . . . . . . . . . . . . . . . . . .11.2-15Table 11.2-2Activity from Steam Generator Blowdown - Design Case . . . . . . . . . .11.2-21Table 11.2-3Activity from Laundry Drains - Design Case . . . . . . . . . . . . . . . . . . . .11.2-22Table 11.2-4Activity from Boron Recovery - Design Case. . . . . . . . . . . . . . . . . . . .11.2-23Table 11.2-5Activity from Primary C oolant System Le akage (HLWDT) -
Design Case a . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.2-25Table 11.2-6Activity from Deco ntamination Building Sumps - Design Case. . . . . .11.2-27Table 11.2-7Activity from Steam Generator Blowdown - Expected Case . . . . . . . .11.2-28Table 11.2-8Activity from Laundry Drains - Expected Case. . . . . . . . . . . . . . . . . . .11.2-30Table 11.2-9Activity from Boron Recovery - Expected Case. . . . . . . . . . . . . . . . . .11.2-31Table 11.2-10Activity from Primary Coolant System Leakage (HLWDT) - Expected Case. . . . . . . . . . . . . . . . . . . . . . . . . . .11.2-34 Revision 52-09/29/2016 NAPS UFSAR 11-viiiChapter 11: Radioactive Waste ManagementList of Tables (continued)TableTitle PageTable 11.2-11Activity from D econtamination Building Sumps - Expected Case. . . .11.2-36Table 11.2-12Activity in Waste Disposal System with Steam Generator Leakage - Design Case. . . . . . . . . . . . . . . . . . . .11.2-38Table 11.2-13Activity in Waste Disposal System with Steam Generator Leakage - Expected Case. . . . . . . . . . . . . . . . . .11.2-40Table 11.2-14Activity in Discharge Canal - Design Case. . . . . . . . . . . . . . . . . . . . . .11.2-42Table 11.2-15Activity in Waste H eat Treatment Facilities - Design Case . . . . . . . . .11.2-43Table 11.2-16Activity in North Anna Reservoir - Design Case . . . . . . . . . . . . . . . . .11.2-44Table 11.2-17Activity in Discharge Canal - Expected Case . . . . . . . . . . . . . . . . . . . .11.2-45Table 11.2-18Activity in Waste H eat Treatment Facility - Expected Case. . . . . . . . .11.2-47Table 11.2-19Activity in North Anna Reservoir - Expected Case. . . . . . . . . . . . . . . .11.2-49Table 11.2-20Flow Conditions in North Anna Reservoir and Waste Heat Treatment Facilities. . . . . . . . . . . . . . . . . . . . . . . . . . .11.2-51Table 11.2-21Maximum Individual W hole-Body and Body-Organ Exposure Due to Liquid Radwaste in the North Anna Reservoir . . . . . . . . . . . . .11.2-51Table 11.2-22Maximum Individual W hole-Body and Body-Organ Exposure Due to Liquid Radwaste in the Waste Heat Facility . . . . . . . . . . . . . . .11.2-52Table 11.2-23Whole-Body Population Exposure Due to Liquid Radwaste in the North Anna Cooling Water Storage System. . . . . . . .11.2-52Table 11.3-1Gaseous Waste Disposal Equipment Design Data. . . . . . . . . . . . . . . . .11.3-12 Table 11.3-2Estimated Gaseous Effluents Ci/yr for Two Units Design Case. . . . . .11.3-15Table 11.3-3Estimated Gaseous Ef fluents Ci/yr for Two Units Expected Case . . . .11.3-16Table 11.3-4Waste Gas Decay Tank Maximum Radioactive Gaseous Activity Design Case. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-17Table 11.4-1Process and Efflue nt Radiation Monitoring System a Normal Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.4-17Table 11.4-2Process Radiation Monitoring System Counting Rates of Relevant Isotopes (Cpm/µCi/cc). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.4-20Table 11.4-3Post-Accident Ra diation Monitoring System Normal and High-Range Nobl e Gas Effluent Monitors (Per NUREG-0737,Section II.F.1) . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.4-21Table 11.4-4Post-Accident Radiati on Monitoring System High-Range Effluent Monitors (Per NUREG-0578, Section 2.1.8.B). . . . . . . . . . . .11.4-21 Revision 52-09/29/2016 NAPS UFSAR 11-ixChapter 11: Radioactive Waste ManagementList of Tables (continued)TableTitle PageTable 11.5-1Solid Waste Disposal Equipment Design Data . . . . . . . . . . . . . . . . . . .11.5-6Table 11.5-2Solid Waste Estimates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.5-8Table 11.6-1North Anna Power Station Radiological Monitoring Program (Preoperational) . . . . . . . . . . . . . . .11.6-4Table 11.6-2North Anna Power Station Environmental Radiological Monitoring Program Measuring Equipment, March 1973 to March 1974. . . . . . . .11.6-6Table 11A-1Tritium Source Terms for System Design a . . . . . . . . . . . . . . . . . . . . . .11A-6Table 11B-1Radiation Exposure Pathway Locations . . . . . . . . . . . . . . . . . . . . . . . .11B-22Table 11B-2Estimated Gaseous Effluents and Isotopic Disintegration Energies . . .11B-23Table 11B-3Maximum Expected Radioactivity Concentrations in the North Anna Waste Heat Treatment Facility and Reservoir. . . . .11B-24Table 11B-4Maximum Individual Internal Body-Organ Exposure from Ingestion of Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-25Table 11B-5Concentration Factor for Effluent Radionuclides in Fish . . . . . . . . . . .11B-26Table 11B-6Maximum Individual Internal Body-Organ Exposure from Ingestion of Fish . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-27Table 11B-7Maximum Individual Exposure From Swimming and Boating. . . . . . .11B-28Table 11B-8Population Exposure Totals: Comparison with Federal Regulations and Natural Background . . . . . . . . . . . . . . . . . . . . . . . . . .11B-29Table 11B-9Maximum Individua l Whole-Body and Body-Organ Dose Totals (mrem/yr). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-30Table 11B-10Organs of Interest for Effluent Radionuclides. . . . . . . . . . . . . . . . . . . .11B-31Table 11B-11Dose Conversion Factors for Swimming (mrem/hr per pCi/Liter) . . . .11B-32Table 11.C-1Comparison of Results with Design Objectives Contained in Rm 50-211C-19Table 11.C-2Radioactivity Concen trations Due to Liquid Effluents (mCi/cc). . . . . .11C-20Table 11.C-3Maximum Individual Doses From Liquid Effluents . . . . . . . . . . . . . . .11C-23Table 11.C-4Gaseous Source Terms by Isotope and Release Mode (Ci/yr released)11C-24Table 11.C-5Maximum Doses for Pathways of Exposure to Gaseous Releases . . . .11C-25 Table 11.C-6Maximum Organ Do se from Gaseous Releases
- a. . . . . . . . . . . . . . . . . .11C-26Table 11.C-7Maximum Total Body and Sk in Doses From Gaseous Releases
- a. . . . .11C-26Table 11.C-8Liquid Waste Processing System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11C-27Table 11.C-9Total Liquid Releases. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11C-29 Revision 52-09/29/2016 NAPS UFSAR 11-xChapter 11: Radioactive Waste ManagementList of Tables (continued)TableTitle PageTable 11.C-10Gaseous Releases for North Anna Units 1 and 2. . . . . . . . . . . . . . . . . .11C-31Table 11.C-11Gaseous Releases (Ci/yr/reactor). . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11C-33Table 11.C-12Distances and Elevations for Special Locations
- a. . . . . . . . . . . . . . . . . .11C-41Table 11.C-13Annual Average c/Q (sec/m 3), D/Q (m-2), and Terrain Correction Factor (TCF) at Site Boundaries and Offsite Exposure Locations for Ground-Level Releases at North Anna (May 1, 1974 through April 30, 1975) . . . . . .11C-46Table 11.C-14Annual Average /Q (sec/m 3), D/Q (m-2), and Terrain Correction Factor (TCF) at Site Boundaries and Offsite Ex posure Locations for Mixed Release Modes at North Anna (May 1, 1974 through April 30, 1975). . . . . . . .11C-49Table 11.C-15Monthly and Annual Jo int Frequency Distributions of Wind Speed and Direction by Atmospheric Stability Class . . . . . . . . .11C-52Table 11.C-16Maximum Elevations Within a 10-Mile Radius of the North Anna Unit 1 Containment (1-Mile Increments). . . . . . . . . . .11C-156Table 11.C-17Parameters Used to Descri be the Pressurized Water Reactor with U-Tube Steam Generators (Volatile Chemistry). . . . . . . . . . . . . . . . . .11C-157Table 11.C-18Source Terms for PWR with U-Tube Steam Generators. . . . . . . . . . . .11C-158 Revision 52-09/29/2016 NAPS UFSAR 11-xiChapter 11: Radioactive Waste ManagementList of Figures FigureTitle PageFigure 11.2-1Liquid Waste Dis posal System-Design Conditions
- a. . . . . . . . . . . . .11.2-53Figure 11.2-2Liquid Waste Dispos al System-Expected Conditions
- a. . . . . . . . . . .11.2-54Figure 11.2-3Flow Chart-Estimated Quantities Liquid Waste Disposal-Design Case
- a. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.2-55Figure 11.2-4Flow Chart-Estimated Quantities Liquid Waste Disposal-Expected Case a . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.2-56Figure 11.3-1Gaseous Waste System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.3-18Figure 11.5-1Flow Chart-Estimated Quantities Solid Waste Disposal System-Expected . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.5-9Figure 11.5-2Flow Chart-Estimated Quantities Solid Waste Disposal System-Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11.5-10Figure 11.6-1Preoperational Radiological Environmental Sampling Program Sample Station Locations. . . . . . . . . . . . . . . . . . .11.6-7Figure 11B-1Exposure Pathways . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11B-33Figure 11C-1Flow Chart for Liquid Waste System . . . . . . . . . . . . . . . . . . . . . . . . .11C-162 Revision 52-09/29/2016 NAPS UFSAR 11-xii Intentionally Blank Revision 52-09/29/2016 NAPS UFSAR 11-1CHAPTER 11RADIOACTIVE WASTE MANAGEMENT Note: As required by th e Renewed Operating Licenses for North Anna Units 1 and 2, issued March 20, 2003, various systems, struct ures, and components discusse d within this chapter are subject to aging management. The programs and activities necessary to manage the aging of these systems, structures, and co mponents are discussed in Chapter 18.The waste disposal systems sepa rate, treat, hold for decay , a nd dispose of radioactive liquid, gaseous, and solid waste materials.
Each of the liquid, solid, and gaseous waste disposal systems is designed to serve both reactor units. These systems incorporat e one or more of the following basic processes:1.Demineralization, for removal of dissolved ionized material.2.Dilution, for reduction of concentration.3.Filtration, for removal of su spended particulate matter
.4.Natural decay of radioactive isotopes.
5.Packaging for shipment to an offsite vendor, for volume reduction.Waste originating in the reactor coolant system is collected via the vent and drain system and processed in the waste dis posal system. Other waste include s laundry and sample waste and solid waste generated duri ng operation and maintenance.
Adequate sampling, analysis, and monitoring of the waste disposal systems are provided to comply with the operation requirements. Radiation monito ring and volumetric measuring equipment are provided for surveill ance of gaseous waste and proce ss stream ef fluent to ensure compliance with applicable regulations and to provide early indication of possible malfunctions or out-of-specification conditions.Sufficient shielding is provided to reduce pe rsonnel exposure to acceptable levels as discussed in Chapter 12.Area radiation monitoring equipm ent, portable radiation survey instruments, health physics facilities, environmental programs, and administrative controls are provided for surveillance and control of radiation and personnel exposure le vels to ensure complia nce with applicable regulations.
Soon after the plant began op eration, it became evident that the 6 gpm capacity of the evaporator was seriously inadequate. Consequently, in July of 1978, a portable filter demineralizer unit was adde
- d. This is described in Section 11.2. The original evap orator, clarifier, and flatbed filter are not used. The limits given by the discharge activity tables will not be exceeded.
Revision 52-09/29/2016 NAPS UFSAR 11-2Similarly, as numerous plan ts obtained experience with the urea formaldehyde solidification system, various system shortcomings became evident, particularly the unexpectedly large amount of free liquid. Consequently, the North Anna plant no longer uses that system but now uses contractor supplied waste solidificatio n and/or dewater systems. This change is discussed in Section 11.5.For both of these system change s, written operating procedures were prepared and approved to assure safe and reliable processing of all radioactive waste.
Revision 52-09/29/2016 NAPS UFSAR 11.1-111.1 SOURCE TERMS The fission product inventory in the reactor core and the diffusion to the fuel pellet cladding gap for a core using 15 x 15 fuel assemblies are presented in Table 11.1-1. Source term data is based on NRC models and assump tions described in NUREG-0017.11.1.1 Radioactivity This section presents the quantities of radioact ive isotopes present in the core, fuel rod gap, coolant, and volume contro l tank for a core with 15 x 15 fuel assemblies. A br ief discussion of the derivation is also provided.11.1.1.1 Activities in the CoreThe total core activity calcul ation is consistent with TID 14844 (Reference 1) and data from APED-5398 (Reference 2). Numerical values for isotopes that are important as health hazards are given in Table 11.1-1. The source term used in design basis accident analysis is based on the Alternative Source Term as described in Section 15.4.11.1.1.2 Activities in the Fuel Rod Gap The computed gap activities are given for both the 15 x 15 (Table 11.1-1) and 17 x 17 (Table 15.1-5) fuel assemblies. A comparison of the gap activities for these two fuel assemblies shows that the gap activities for the 17 x 17 fuel assembly are only about one-half of those of the 15 x 15 fuel assembly. This is a result of the lo wer operating temperatures and therefore the slower diffusion rate in the 17 x 17 fuel. For this reason, the calculations in Chapter 11 have not been recalculated for the 17 x 17 fuel assembly, since the results would have only been less.The computed ga p activities (15 x 15) are based on buildup in the fuel from the fission process and diffusion to the fuel rod gap at rates de pendent on the operating temperature. For the purposes of this analysis, the fuel pellets were divided into five concentric rings each with release rate dependent on the mean fuel temperature within that ring. The diffusing isotope is assumed present in the gas gap when it has diffused to the boundary of its ring.The diffusion coefficient, D', for Xe and Kr in UO 2,varies with temper ature through the following expression:(11.1-1)where:E = activation energy D' (1673) = diffusion coefficient at 1673 K = 1 x 10-11 sec-1 T = temperature, K R = gas constantD'T ()D'1673 ()E R----1 T---1 1673
---exp=
Revision 52-09/29/2016 NAPS UFSAR 11.1-2 The above expression is vali d for temperatures above 1 100°C. Below 1100°C fission gas release occurs mainly by two te mperature-independent phenomena, recoil and knock-out, and is predicted by using D' at 1100°C.
The value used for D' (1673 K), based on data at burnups greater than 10 19 fission/cc, accounts for possible fission gas release by other mechanisms and pellet cracking during irradiation.The diffusion coefficient for iodine isotopes is assumed to be the same as for Xe and Kr. Toner and Scott (Reference 3) observed that iodine di ffused in UO at about the same rate as Xe and Kr and has about the same activation energy.
Data surveyed and reported by Belle (Reference 4) indicate that iodine diffuses at slightly slower rates than do Xe and Kr.
For a full core cycle at 2900 MWt core power, the above analysis results in a pellet-clad gap activity of less than 3% of th e dose equivalent equilibrium core iodine inventory. The noble gas activity present in the pellet-clad gap is about 2.5% of the core inventory.
The percentage of the total core activity present in the gap for each isotope is also listed in Table 11.1-1.The core temperature distribution used in this analysis is presented in Table 11.1-2.The inventory of fission products in a fuel assembly is dependent on the rating of the assembly. The parameters used for the calculations of the highest rated assemb ly in the core to be discharged are summarized in Table 11.1-3, while the associated activiti es at the time of shutdown are given in Table 11.1-4.The expected end-of-life temperature and power di stributions were calculated by using radial and axial power peaking factors of 1.27 and 1.37 respectively. The conservative end-of-life temperature and power distributions were calcu lated by using the same radial power peaking factor as in the expect ed case, but with a higher axial power peaking factor of 1.72. Thus, the temperature/volume distribution in the fuel is changed and the maximum temperature is increased (Table 11.1-3), resulting in an increased fraction of fission products in the fuel-cladding gap (Table 11.1-4).While the full core cy cle was based on 2900 MWt, the gap activity of 15 x 15 fuel is approximately twice that of the 17 x 17 fuel used in the North Anna cores given the same operating conditions. This source term is normalized to the Technical Specifications dose equivalent I-131 limit in the primary coolant, wh ich essentially removes the power dependence from the analyses. For the measurement uncertainty recapture power uprate to 2940 MWt, the existing fuel rod gap activities were determined to be conservative.
Revision 52-09/29/2016 NAPS UFSAR 11.1-311.1.1.3 Activities in the Reactor CoolantThe parameters used in the calculation of the design case reactor coolant fission product inventories, together with the pertinent information c oncerning the expected coolant cleanup flow rate and demineralizer effec tiveness, are summarized in Table 11.1-5. The results of the calculations are presented in Table 11.1-6. In these calculations the defective fuel rods were assumed to be present at the in itial core loading and were uniformly distri buted throughout the core. Thus, the fission product escape rate coefficients were based upon the average fuel temperature. The calculations were performed for the average temp erature of the reactor coolant system. The coolant density correct ion of 1.35 was made in order to obtain the correct activities downstream of the regenerative heat exchanger.
The expected case activities ar e those calculated for the 10 CFR 50 Appendix I analysis using NUREG-0017 methodo logy. The Appendix I evaluation presented in Section 11C.1 is based on radioactive release rates for Units 1 and 2 expected at the time of initial licensing of the units. The following discussion pertains to the calculation of new expected source terms for Units 1 and 2 based on revised calculational models and related guidance as contained in NUREG-0017. The source terms (primary co olant and secondary-side liquid and steam radioactivities) and the resulting radioactive rel eases are calculated using the basic assumptions and approaches contained in NUREG-0017.The PWR-GALE code used by the NRC staff is not used in these analyses. However, the procedures that are used provide essentially the same mathematical treatments. Values of parameters, such as flow rates, are based on the North Anna Units 1 and 2 design. In some instances, standard NRC staff assumptions are used in lieu of the de sign values in order to fit the NUREG-0017 analysis for North Anna Units 1 and 2 as closely as possible to the NRC staff's analytical approach. The staff's model is inflexible in some respects and is expe cted to lead necessarily to slightly different results than those from this anal ysis. The data de scribed herein represent an attempt to analyze the releases us ing the NRC model and assumptions as closely as Virginia Power could configure them.Table 11.1-9 contains the parameters used in determining source terms. Table 11.1-10 lists the source terms.
For fuel failure and burnup experience see Chapter 4.The fission product activ ities in the reactor coolant dur ing operation with small cladding defects (fuel rods containing pinholes or fine cracks) are computed using the following differential equations:
For parent nuclides in the coolant:(11.1-2)dN wi dt-----------Dj N cii Ri B'B otB'--------------------
++N wi-=
Revision 52-09/29/2016 NAPS UFSAR 11.1-4 For daughter nuclides in the coolant:(11.1-3)where: N = nuclide concentration D = clad effects, as a fraction of rated core thermal power being generated by rods with clad defectsR = purification flow, coolant system volumes per sec B = initial boron concentration, ppm
B' = boron concentration reducti on rate by feed and bleed, ppm/sec = removal ef ficiency of purification cycle for nuclide = radioactive decay constant
= escape rate coefficient for diffusion into coolant t = time c = core w = coolant i = parent nuclide j = daughter nuclide11.1.1.4 Activities in Secondary SideThe concentrations of principa l fission products in the second ary side liquid of the steam generator are given for both design and expected failed fuel conditions in Tables 11.1-7 and 11.1-10, respectively. Concentrations of principa l noble gases and halogens in the secondary side steam are given in Tables 11.1-8 and 11.1-10.11.1.1.5 Activities in the Volume Control Tank The 300-ft 3 volume control tank is assumed to contain 96 ft 3 of liquid and 204 ft 3 of vapor, for dose analysis. Table 11.1-11 lists the activities in the volume control tank with clad defects in 1% of the fuel rods.11.1.1.6 Activities in the PressurizerThe activities in the pressurizer are separate d between the liquid a nd the steam pha se and the results obtained are given in Table 11.1-12 using the assumptions summarized in Table 11.1-5.dN wj dt------------Dj N cjj Rj B'B otB'--------------------
++N wj-i N wi+=
Revision 52-09/29/2016 NAPS UFSAR 11.1-511.1.1.7 Activities in the Demineralizer Resin Saturation activities for demine ralizer resins (specific sour ce strength) are given in Table 11.1-13 using the assumptions summarized in Table 11.1-5.11.1.2 Leakage RatesAs a necessary part of the effort to re duce effluent of radioactive liquid wastes, Westinghouse has been surveying various pressuri zed water reactor (PWR) facilities that are in operation, to identify design and operating problems influencing reactor coolant and nonreactor-grade leakage and hence the load on the waste disposal system.
Leakage sources have been identified as pump shaft seals and valve stem leakage.Where packed glands are provided, a leak age problem may be anticipated, while mechanical shaft seals provide essentially zero leakage. Valve st em leakage has been experienced, however. A combination of a grap hite filament yarn packing sa ndwiched with asbestos sheet packing is used with improved results.The station waste dispos al systems, as design ed, w ill accommodate the leakages listed in Table 11.1-14. The values given assume cl adding defects in fuel rods that generated 1% of the rated core thermal power.Section 11.3.5 gives conservatively es timated leakages from th e gaseous waste system with corresponding activity discharges.
11.1 REFERENCES
1.J. J. Di Nunno et al., Calculation of Distance Factors for Power and Test Reactor Sites , TID 14844, March 1962.2.M. E. Meek and B. F. Rider, Summary of Fission Product Yi elds for U235, U238, Pu239 and Pu241 at Thermal Fission Spectrum and 14 MeV Neutron Energies , APED-5398, General Electric Company, March 1, 19683.D. F. Toner and J. L. Sco tt, "Fission Produc t Release for UO 2 ," Nuclear Safety, Vol. III, No. 2, December 1961.4.J. Belle, Uranium Dioxide: Pr operties and Nuclear Application , Naval Reactors Division of Reactor Development, USAEC, 1961.
Revision 52-09/29/2016 NAPS UFSAR 11.1-6Table 11.1-1CORE AND GAP ACTIVITIES 15 X 15 FUEL ASSEMBLY ARRAY a IsotopeCuries in the Core, (x 10 7)Percent of Core Activity in the GapCuries in the Gap (x 10 5)I-131 7.17 1.88 13.5 I-132 10.9 0.21 2.29 I-133 16.1 0.63 10.1 I-134 18.9 0.13 2.46 I-135 14.6 0.36 5.26 Xe-133 16.6 1.53 25.4 Xe-133m 0.422 1.01 0.426 Xe-135 4.54 0.42 1.91 Xe-135m 4.45 0.071 0.316Kr-85 0.0814 25.5 2.08Kr-85m 3.22 0.29 0.935Kr-87 6.19 0.16 0.990Kr-88 8.82 0.23 2.03a.Assume operation at 2900 MWt for 650 days. Temperature distribution is specified in Table 11.1-2.Table 11.1-2CORE TEMPERATURE DISTRIBUTION 15 X 15 FUEL ASSEMBLY ARRAYCore Fuel Volume Above theGiven Temperature, %
aPower (MWt)Local Temperature (°F)0041000.26.837001.8 903300 7.0317290015.57042500a.Remainder of core fuel volume is assumed at or below 2,500°F.
Revision 52-09/29/2016 NAPS UFSAR 11.1-7Table 11.1-3 NUCLEAR CHARACTERISTICS OF HIGHEST RATED DISCHARGED FUEL ASSEMBLY Reactor Expected Case Conservative Case Power Rating 2900 MWt 2900 MWt Number of assemblies 157 157 Array 15 x 15 15 x 15Core average assembly power 18.5 18.5Discharged assembly (highest power)Axial peak to average ratio 1.37 1.72 Peak power 13.4 kW/ft 13.4 kW/ft Maximum temperature 3500°F 3900°F Radial peak to average ratio 1.27 1.27Temperature/Power Distribution Local TemperatureFuel Volume
(%)Power inVolume(MWt)Fuel Volume
(%)Power inVolume (MWt)> 390000003700 - 3900001.330.32 3500 - 3700002.670.64 3300 - 35001.33 0.324.000.96 3100 - 33002.670.645.331.28 2900 - 3100 4.00 0.96 6.67 1.60 2700 - 29005.331.288.00 1.92 2500 - 27006.67 1.609.33 2.24< 250080.0019.18 62.6715.02Total100.0023.98100.0023.98 Revision 52-09/29/2016 NAPS UFSAR 11.1-8Table 11.1-4 ACTIVITIES IN HIGHEST RATED DISCHARGED ASSEMBLYAT TIME OF REACTOR SHUTDOWN (Ci)
IsotopeTotal Curies I-131 5.91 x 10 5 I-132 8.98 x 10 5 I-133 1.32 x 10 6 I-134 1.55 x 10 6 I-135 1.21 x 10 6 Kr-85m 2.66 x 10 5Kr-85 6.53 x 10 3Kr-87 5.10 x 10 5Kr-88 7.27 x 10 5 Xe-133m 3.47 x 10 4 Xe-133 1.36 x 10 6 Xe-135 3.74 x 10 5 Revision 52-09/29/2016 NAPS UFSAR 11.1-9Table 11.1-5 PARAMETERS USED IN THE CALCULAT ION OF REACTOR COOLANT FISSION PRODUCT ACTIVITIES (15 x 15 FUEL ASSEMBLY)ParameterValueCore thermal power, max. calculated 2900 MWtFraction of fuel containing clad defects design 0.01 Reactor coolant liquid volum e, including pressurizer 9380 ft 3Reactor coolant av erage temperature 577°F Purification flow rate (normal/maximum design) 60 gpm/120 gpmEffective cation demineralizer flow 6.0 gpmVolume control tank volumesVapor 204 ft 3 Liquid 96 ft 3Fission product escape rate coefficients Noble gas isotopes 6.5 x 10-8 sec-1Br, I, and Cs isotopes 1.3 x 10-8 sec-1Te isotopes 1.0 x 10-9 sec-1 Mo isotopes 2.0 x 10-9 sec-1 Sr and Ba isotopes 1.0 x 10-11 sec-1Y, La, Ce, and Pr isotopes 1.6 x 10-12 sec-1 Mixed bed demineralizer decontamination factors Noble gases and Cs-134, Cs-136, Cs-137, Y-90, Y-91, and Mo-99 1.0 All other isotopes 10.0 Cation bed demineralizer decontamination factor for Cs-134, Cs-136, Cs-127, Y-90, Y-91, and Mo-99 10.0 Revision 52-09/29/2016 NAPS UFSAR 11.1-10Table 11.1-5 (continued)
PARAMETERS USED IN THE CALCULATION OF REACTOR COOLANT FISSION PRODUCT ACTIVITIES (15 x 15 FUEL ASSEMBLY)Volume control tank noble gas stripping fraction (closed system)
IsotopeStripping FractionKr-85 2.3 x 10-5Kr-85m 2.7 x 10-1Kr-87 6.0 x 10-1Kr-88 4.3 x 10-1 Xe-133 1.6 x 10-2 Xe-133m 3.7 x 10-2 Xe-135 1.8 x 10-1 Xe-135m 8.0 x 10-1 Xe-138 1.0 x 10 0 Revision 52-09/29/2016 NAPS UFSAR 11.1-11Table 11.1-6 CONCENTRATION OF PRINCIPAL FISSION PRODUCTS IN PRIMARY COOLANT WITH 1.0% FAILED FUEL (µCi/c m 3) a Isotope Activity IsotopeActivityBr-84 3.18 x 10-2 Cs-136 1.10 x 10-1 Rb-88 2.77 x 10 0 Cs-137 9.92 x 10-1 Rb-89 7.55 x 10-2 Cs-138 6.99 x 10-1Sr-89 2.82 x 10-3 Ba-140 3.19 x 10-3Sr-90 1.04 x 10-4 La-140 1.10 x 10-3Sr-91 1.44 x 10-3 Ce-144 2.42 x 10-4Sr-92 5.52 x 10-4Pr-144 2.41 x 10-4Y-90 1.26 x 10-4Kr-85 3.86 (peak)Y-91 4.55 x 10-3Kr-85m 1.59 x 10 0Y-92 5.38 x 10-4Kr-87 9.20 x 10-1Zr-95 5.24 x 10-4Kr-88 2.78 x 10 0 Nb-95 5.18 x 10-4 Xe-133 2.13 x 10+2 Mo-99 4.01 x 10 0 Xe-133m 2.36 x 10 0 I-131 1.85 x 10 0 Xe-135 4.62 x 10 0 I-132 6.74 x 10-1 Xe-135m 1.43 x 10-1 I-133 2.99 x 10 0 Xe-138 5.08 x 10-1 I-134 4.17 x 10-1 Mn-54 5.6 x 10-4 I-135 1.61 x 10 0 Mn-56 2.1 x 10-2Te-132 1.97 x 10-1 Co-58 1.8 x 10-2Te-134 2.18 x 10-2 Co-60 5.4 x 10-4 Cs-134 1.98 x 10-1 Fe-59 7.5 x 10-4Cr-51 6.8 x 10-4a.Based on parameters of Table 11.1-5.
Revision 52-09/29/2016 NAPS UFSAR 11.1-12Table 11.1-7CONCENTRATION OF PRINCIPAL PRODUCTS IN S TEAM GENERATOR LIQUID WITH 1.0% FAILED FUEL (µCi/cm 3) a Isotope Activity Isotope Activity I-131 4.44 x 10-3Mo-99 8.71 x 10-3 I-132 6.47 x 10-4Tc-99m 7.59 x 10-3 I-133 4.89 x 10-3Te-132 4.36 x 10-4 I-134 7.73 x 10-5Te-134 3.28 x 10-6 I-135 1.15 x 10-5 Cs-134 5.03 x 10-4Br-84 3.65 x 10-6 Cs-136 2.04 x 10-4 Rb-88 1.77 x 10-4 Cs-137 2.52 x 10-3 Rb-89 4.04 x 10-6 Cs-138 7.79 x 10-5Sr-89 7.14 x 10-6 Ba-137m 2.31 x 10-3Sr-90 2.64 x 10-7 Ba-140 7.81 x 10-6Sr-91 1.67 x 10-6 La-140 3.92 x 10-6Sr-92 2.64 x 10-7 Ce-144 6.14 x 10-7Y-90 3.12 x 10-7Pr-144 6.14 x 10-7Y-91m 6.22 x 10-7Cr-51 1.70 x 10-6Y-91 1.15 x 10-5Mn-54 1.42 x 10-6Y-92 5.25 x 10-7Mn-56 9.70 x 10-6Zr-95 1.32 x 10-6 Fe-59 1.89 x 10-6 Nb-95m 3.03 x 10-9 Co-58 4.54 x 10-5 Nb 1.32 x 10-6 Co-60 1.37 x 10-6a. Based on a 100 gallon/day primary/secondary leak rate and a 37.5 gpm total steam generator blowdown per unit.
Revision 52-09/29/2016 NAPS UFSAR 11.1-13Table 11.1-8CONCENTRATION OF PRINCIPAL NOBLE GASES AND HALOGENS IN SECONDARY SIDE STEAM WITH 1.0% FAILED FUEL (µCi/lb) IsotopeSteam Generator Steam ActivityKr-85m 8.86 x 10-3Kr-85 2.16 x 10-2Kr-87 5.15 x 10-3Kr-88 1.56 x 10-2 Xe-133m 1.32 x 10-2 Xe-133 1.20 x 10 0 Xe-135m 8.01 x 10-4 Xe-135 2.59 x 10-2 Xe-138 2.84 x 10-3 I-131 2.51 x 10-1 I-132 3.66 x 10-2 I-133 2.77 x 10-1 I-134 4.38 x 10-3 I-135 8.49 x 10-2 Revision 52-09/29/2016 NAPS UFSAR 11.1-14Table 11.1-9 PARAMETERS USED TO DESCRIBE TH E PRESSURIZED WATER REACTOR WITHU-TUBE STEAM GENERATORS (VOLATILE CHEMISTRY)ParametersValueThermal power 2.9E+03 MWtSteam flow rate 1.22E+07 lb/hrWeight of water in reactor coolant system 4.34E+05 lbWeight of water in all steam generators 5.02E+05 lbReactor coolant letdow n flow (purification) 2.23E+04 lb/hr Reactor coolant letdown flow (y early average for boron control) 3.40+03 lb/hrSteam generator blowdown flow (total) 4.50E+04 lb/hr Fraction of radioactivity in blowdown stream which is not returned to the secondary coolant system Halogens 1.00 Cs, Rb 1.00 Others 1.00Flow through the purification system cation demineralizer 2.23E+03 lb/hr Ratio of condensate demineralizer flow rate to the total steam flow rate 0.0Ratio of the total amount of noble gases routed to gaseous radwaste from the purification system to the total amount of noble gases routed from the primary coolant system to the purifi cation system (not including the boron recovery system) 0.0 Notes:1.The reactor coolant concentrat ions given are for re actor coolant entering the letdown line.2.The secondary coolant concentrations are based on a primary-to-secondary leakage of 100 lb/day.3.The steam generator steam concentrations gi ven are for steam leaving the steam generator.4.Values used in determining cool ant activities are given in Section 2.2.3 of NUREG-0017.5.These coolant activities are calculated according to NUREG-0017 (April 1976) methods.
Revision 52-09/29/2016 NAPS UFSAR 11.1-15Table 11.1-10 SOURCE TERMS FOR PWR WITH U-TUBE STEAM GENERATORS IsotopeReactor CoolantSteam Generator LiquidsSteamGenerator SteamDecay Constant
(µCi/g)(Ci)(µCi/g)(Ci)(µCi/g)(1/sec)Noble GasesKR-83M2.3E-024.5E+000.00.07.7E-091.04E-04KR-85M1.2E-012.3E+010.00.04.0E-084.30E-05 KR-851.9E-0238.E+000.00.06.6E-092.05E-09 KR-876.5E-021.3E+010.00.02.1E-081.52E-04 KR-882.1E-014.2E+010.00.07.3E-086.88E-05 KR-895.5E-031.1E+000.00.01.9E-093.66E-03 XE-131M3.9E-027.7E+000.00.01.4E-086.69E-07 XE-133M1.6E-013.2E+010.00.05.6E-083.60E-06 XE-1339.5E+001.9E+030.00.03.3E-061.52E-06 XE-135M1.4E-022.8E+000.00.04.9E-097.55E-04 XE-1353.5E-017.0E+010.00.01.2E-072.10E-05 XE-1379.9E-032.0E+000.00.03.4E-093.01E-03 XE-1384.8E-029.5E+000.00.01.6E-088.14E-04 HalogensBR-835.5E-031.1E+001.2E-072.8E-051.2E-098.02E-05 BR-842.9E-035.7E-011.8E-084.1E-061.8E-103.66E-04 BR-853.3E-046.5E-022.0E-104.6E-082.0E-124.03E-03 I-1302.6E-035.1E-011.5E-073.3E-051.5E-091.55E-05 I-1313.7E-017.4E+013.3E-057.5E-033.3E-079.98E-07 Revision 52-09/29/2016 NAPS UFSAR 11.1-16 Halogens (continued)I-1321.1E-012.3E+013.3E-067.5E-043.3E-088.43E-05I-1334.9E-019.6E+013.3E-057.5E-033.3E-099.26E-06 I-1345.3E-021.0E+015.0E-071.1E-045.0E-092.20E-04 I-1352.3E-014.5E+019.7E-062.2E-039.7E-082.92E-05 Cs, RbRb-861.1E-042.1E-021.0E-082.3E-061.0E-114.30E-07 Rb-882.2E-014.4E+017.6E-071.7E-047.6E-106.53E-04 Cs-1343.2E-026.3E+003.0E-066.8E-043.0E-091.07E-08 Cs-1361.6E-023.2E+001.5E-063.4E-041.5E-096.17E-07 Cs-1372.3E-024.5E+002.2E-064.9E-042.2E-097.30E-10Water Activation ProductsN-164.0E+017.9E+039.0E-072.0E-049.0E-089.75E-02TritiumH-31.0E+002.0E+021.0E-032.3E-011.0E-031.79E-09 Other NuclidesCr-512.6E-035.2E-012.4E-075.4E-052.4E-102.88E-07 MN-544.3E-048.5E-025.3E-081.2E-055.3E-112.56E-08 FE-552.2E-034.4E-012.1E-074.8E-052.1E-108.14E-09Table 11.1-10 (continued)SOURCE TERMS FOR PWR WITH U-TUBE STEAM GENERATORS IsotopeReactor CoolantSteam Generator LiquidsSteamGenerator SteamDecay Constant
(µCi/g)(Ci)(µCi/g)(Ci)(µCi/g)(1/sec)
Revision 52-09/29/2016 NAPS UFSAR 11.1-17 Other Nuclides (continued)FE-591.4E-032.7E-011.6E-073.6E-051.6E-101.78E-07CO-582.2E-024.4E+002.1E-064.8E-042.1E-091.12E-07 CO-602.8E-035.5E-012.4E-075.4E-052.4E-104.18E-09 SR-894.9E-049.6E-025.3E-081.2E-055.3E-121.59E-07 SR-901.4E-052.7E-021.1E-092.4E-071.1E-127.58E-10 SR-917.9E-041.6E-013.5E-088.1E-043.5E-112.03E-05 Y-901.6E-063.2E-041.9E-104.4E-081.9E-133.1E-06 Y-91M4.0E-047.9E-021.1E-082.5E-061.1E-112.32E-04 Y-918.9E-051.8E-027.9E-091.8E-067.9E-121.37E-07 Y-934.2E-058.2E-031.8E-094.1E-071.8E-121.89E-05 ZR-958.4E-051.6E-021.1E-082.4E-061.1E-111.23E-07 NB-957.0E-051.4E-021.1E-082.4E-061.1E-112.29E-07 MO-991.1E-012.2E+019.6E-062.2E-039.6E-092.92E-06 TC-99M5.7E-021.1E+014.8E-061.1E-034.8E-093.20E-05 RU-1036.3E-051.2E-025.3E-091.2E-065.3E-122.03E-07 RU-1061.4E-052.7E-031.1E-092.4E-071.1E-122.17E-08 RH-103M5.0E-059.9E-032.3E-095.1E-072.3E-122.06E-04 RH-1061.1E-052.2E-034.0E-109.0E-074.0E-132.32E-02 TE-125M4.0E-058.0E-032.6E-096.0E-072.6E-121.38E-07 TE-127M3.9E-047.7E-022.6E-086.0E-062.6E-112.36E-08Table 11.1-10 (continued)SOURCE TERMS FOR PWR WITH U-TUBE STEAM GENERATORS IsotopeReactor CoolantSteam Generator LiquidsSteamGenerator SteamDecay Constant
(µCi/g)(Ci)(µCi/g)(Ci)(µCi/g)(1/sec)
Revision 52-09/29/2016 NAPS UFSAR 11.1-18 Other Nuclides (continued)TE-1271.0E-032.0E-015.3E-081.2E-055.3E-112.05E-05TE-129M1.9E-033.8E-011.6E-073.6E-051.6E-102.40E-07 TE-1291.8E-033.5E-016.9E-081.6E-056.9E-111.65E-04 TE-131M3.2E-036.4E-012.2E-075.0E-052.2E-106.42E-06 TE-1311.2E-032.4E-012.1E-084.8E-062.1E-114.62E-04 TE-1323.6E-027.2E+002.4E-065.6E-042.4E-092.47E-06 BA-1371.8E-023.5E+009.0E-072.0E-049.0E-104.53E-03 BA-1403.0E-046.0E-022.6E-085.9E-062.6E-116.27E-07 LA-1402.0E-043.9E-021.6E-083.7E-061.6E-114.79E-06 CE-1419.7E-051.9E-021.1E-082.4E-061.1E-112.47E-07 CE-1435.2E-051.0E-022.2E-095.1E-072.2E-125.83E-06 CE-1444.6E-059.1E-035.3E-091.2E-065.3E-122.82E-08 PR-1436.9E-051.4E-025.3E-091.2E-065.2E-125.91E-07 PR-1443.1E-057.2E-032.1E-094.7E-072.1E-126.69E-04 NP-2391.6E-033.2E-011.4E-073.2E-051.4E-103.41E-06Table 11.1-10 (continued)SOURCE TERMS FOR PWR WITH U-TUBE STEAM GENERATORS IsotopeReactor CoolantSteam Generator LiquidsSteamGenerator SteamDecay Constant
(µCi/g)(Ci)(µCi/g)(Ci)(µCi/g)(1/sec)
Revision 52-09/29/2016 NAPS UFSAR 11.1-19Table 11.1-11VOLUME CONTROL TANK ACTIVITIES IsotopeVapor Activity (µCi/cc)Kr-851.11 x 10 2Kr-85m 2.72 x 10 1Kr-87 4.22 x 10 0Kr-88 3.54 x 10 1 Xe-133 4.09 x 10 3 Xe-133m 4.45 x 10 1 Xe-135 7.54 x 10 1 Xe-135m 6.15 x 10-3 Xe-138 1.15 x 10-2 Revision 52-09/29/2016 NAPS UFSAR 11.1-20Table 11.1-12 PRESSURIZER ACTIVITIES a IsotopeVapor Activity (µCi/cm 3)Kr-85 6.2 x 10-1Kr-85m 1.4 x 10-1Kr-87 2.3 x 10-2Kr-88 1.5 x 10-1 Xe-131m 1.2 x 10-1 Xe-133 5.3 x 10 1 Xe-133m 2.5 x 10 0 Xe-135 8.4 x 10-1 Xe-135m 7.2 x 10-4 Xe-138 2.9 x 10-3 Isotope Liquid Activity (µCi/gm)N-16 (max) 1.5 x 10 0 Rb-88 1.6 x 10-2Mo-99 0.50 x 10 0 I-131 1.7 x 10 0 I-132 2.9 x 10-2 I-133 0.90 x 10 0 I-134 7.2 x 10-3 I-135 0.17 x 10 0 Cs-137 1.3 x 10 0 Cs-138 7.4 x 10-3a.Based on parameters of Table 11.1-5 with 1% clad defects.
Revision 52-09/29/2016 NAPS UFSAR 11.1-21Table 11.1-13SPECIFIC SOURCE STRENGTH MeVSpecific Activity (MeV/cm 3-sec)Mixed Bed De mineralizer 0.4 1.1 x 10 8 0.8 6.0 x 10 8 1.3 1.5 x 10 7 1.7 1.7 x 10 7 2.5 5.1 x 10 7 Cation Bed Demineralizer 0.4 9.6 x 10 5 0.8 8.4 x 10 8 1.3 1.5 x 10 7 1.7 1.9 x 10 4 2.5 1.6 x 10 4 Spent Fuel Pit Ion Exchanger 0.4 1.3 x 10 4 0.8 1.4 x 10 6 1.3 1.5 x 10 4 1.7 6.0 x 10 2 2.5 3.2 x 10 3 Revision 52-09/29/2016 NAPS UFSAR 11.1-22Table 11.1-14 LEAKAGE RATES Primary To Secondary LeakageDesign - Shall be limited to:a.Total leakage from all steam generators of 300 gpd.b.Leakage from an individua l steam generator of 100 gpd.c.Total leakage increase of 60 gpd between surveillance intervals.d.An increasing trend based on the latest surveillance that indicates 100 gpd would not be exceeded on an individual steam generator within 90 minutes.Primary Coolant Leakage Design - 0.024 gpm per unit in the containment and 0.006 gpm per unit in the auxiliary building.Condensate Leakage to Turbine Building Sumps Design - 1,670,000 gallon per year for two uni ts. This number was developed from manufacturers' data on the pump seals for th e condensate and heater drain pumps plus es timated valve leakage.Steam Leakage to the Turbine and Auxiliary Buildings Main steam leakage to the turbine bu ilding (design) - 100 lb/hr per unit.
Reflashed auxiliary steam Building heating drain receivers - 300 lb/hr fo r two units over the 6-month heating season.
Auxiliary steam drain receive r - 4000 lb/hr for two units.
Auxiliary steam Main condenser air ejector - 12.5 scfm per unit of air and noncondensables and 41.5 lb/hr per unit of steam.
Gland steam condenser air ejector - 2200 lb/h r per unit of air and noncondensables and 230 lb/hr per unit of steam.
Chilled water unit air ejecto r condenser - 2.5 scfm per unit of air and noncondensables and 8.3 lb/hr per unit of steam.
Revision 52-09/29/2016 NAPS UFSAR 11.2-111.2 LIQUID WASTE DISPOSAL SYSTEM11.2.1 Design Objectives The liquid waste disposal system was designed to satisfy the applicable sections of the general design criteria of Section 3.1. In addition, this system was de signed to meet the criteria of 10 CFR 20, 10 CFR 50, and 10 CFR 100 so as not to endanger th e health of station operating personnel or the general public. T ransportation of radioactive materials from the station will be carried out in a manner that will conform with all applicable Federal, stat e, and local ordinances.
Liquid radioactive waste system components have been designed according to Section VIII of the ASME Boiler and Pressure Vessel Code.
The liquid waste disposal system is common to both reactor units and accommodates the radioactive wastes produced during simu ltaneous operation of the two units.
Section 11.2.5 presents design and expected liquid activity releases by nuclide from North Anna Units 1 and 2. These estimated liquid releases are based on a set of assumptions, discussed in Sections 11.1 and 11.2.2 , regarding the operation of the plant, various process system radioactive liquid flowrates, and the liquid waste disposal system.
These assumptions and original estimates of design and expected releases re presented the basis for compliance to the NRC requirements in the original licensing basis. These assumptions were intended to be representative of the plant operation. In some instances, this is not the case since various system process parameters have proven to be different from the initial estimated values. Ultimately, adherence to the liquid waste effluent requireme nts is monitored by procedures in accordance with the Offsite Dose Calculation Manual (ODCM), as discussed in Section 11.4.4.1.Monitoring liquid effluent re leases in accordan ce with the ODCM ensures that the composite results of the variati ons in the liquid waste inputs and processing on the actual releases are within the accepted current li censing basis for the liquid waste disposal system as specified in the acceptance criteria of the ODCM. In addition, this mon itoring has demonstrated that the released liquid waste activities are typically significantly less than the expected case releases from Section 11.2.5.Virginia Power implemented the revised 10 CFR 20 January 1, 1994. The occupational MPC values are replaced by Derived Air Concen tration (DAC) values and the non-occupational MPC values are replaced by Effluent Concentration Values. The calculationa l methodology for the design and expected liquid activity releases, which are based on th e criteria of the old 10 CFR 20, are valid design analyses and does not need to be redone under the revised 10 CFR 20. (
Reference:
Seventh Set of NRC Q/A, #456.) Th e exposures received by the general public as a result of these releases are presented in Section 11.2.8.
Revision 52-09/29/2016 NAPS UFSAR 11.2-211.2.2 System Description The liquid waste disposal sy stem was designed to receiv e, process, and discharge potentially radioactive liquids from a variety of sources, including the Chemical and Volume Control System, the boron recovery system, the steam generator blowdown system, the vent and drain system sumps described in Section 9.3.3 , laboratory drains, personne l decontamination area (PDA) drains, the decontaminati on system, the sampling system, laundry drains, and spent resin flush water. The system design considers potential personnel exposure and ensures that radioactive releases to the e nvironment are as low as reasona bly achievable (ALARA). During normal plant operation, th e total activity from radionuclides leaving the discharge canal does not exceed the limits of applicable regulations. Sources of radioactivity are identified in Section 11.1. Flow diagrams indicating principal flow path s and bypasses are given in Reference Drawings 1 through 4. Design data for permanently installed equipment are given in Table 11.2-1. Several components have been abandoned in place and are identified as su ch. Their description is for reference only. Dilution factors used in evaluating the release of radioactive effluents are given in Section 11.2.7. Section 11.2.5 and Figure 11.2-1 and Figure 11.2-2 describe the expected average volumes and activities of outlet streams.
Section 11.2.5 also gives the plan t releases by isotope and concentration.
All pipes containing signi ficant radioactivity are routed with in appropriately shielded areas, as specified on design drawings.
Pipes are field run only to the extent that the pipe lengths necessary to allow the pipes to fit in the appropr iate shielded areas are determined in the field.With the exception of the ion exchanger filt ration system (IEFS), wa ste disposal building, demineralizer , and spent resin transfer equipment, liquid waste processing equipment is located below grade in the auxiliary build ing or decontamination building.
These portions of the auxiliary building and decontamination building are designed according to Seismic Class I criteria.Offsite dose calculations consider only li quid waste treatment by ion exchange and filtration. NUREG-0017 was used to estimate equipment performance.11.2.2.1 Condensate Polishing Syst em Resin Waste Disposal The condensate polishers could generate radio active waste in the form of spent powdered resin in a slurry with water. The slurry is accumulated in the secondary phase separator in the turbine building. If the resin slur ry in the secondary phase separa tor is nonradioactive, the resin slurry is treated as non-hazardous chemical wa ste. If the slurry is radioa ctive, it is pumped to an appropriate container and dispos ed of as radioactive waste.11.2.2.2 Ion Exchange Filtration System (IEFS)
Liquid radioactive waste may be treated prior to release by the ion exchange filtration system (IEFS) as the sole met hod of treatment, or by using the IEFS in c onjunction with other components of the liquid waste disposal system (typically the demineralizers in the Waste Revision 52-09/29/2016 NAPS UFSAR 11.2-3 Disposal Bldg.). The IEFS consists of filtration and demineralizer vessels each of which have a volume of 30 ft 3.The IEFS processes up to 35 gpm of liquid waste.
The demineralization system is hose-connected into the in-plant source of waste water (Reference Drawing 2, 2"-LW-372-152), while the effluent side of the system is hose-connected into the in-plant systems for hold-up, mo nitoring and discharge (Reference Drawing 2 , 2"-LW-373-152). Influent and effluent lines are hard-piped.
The piping, which leads from th e basement of the decontamin ation building to level 271, is the same size and grade as existi ng piping (NAS-28). Pipe runs use existing pipe chases and lead to an area adjacent to the waste solidification cubi cle. Hose attachment will be secure and tight, and will have appropriate isolation valves.
The Ion Exchange Filtra tion system is a portabl e unit containing the sl uicable filtration and demineralizer pressure vessels.Waste water is pumped to the IEFS by the hi gh-level waste drain tank pumps 1-LW-P-2A and 1-LW-P-2B. A self-priming booster pump is provi ded at the inlet to pr ovide satisfactory flow rates through the filtration and demin eralizer pressure vessels. Als o, a pressure relief valve is mounted on the inlet header to prevent overpressur ization of the system.
The relief valve complies with ASME,Section I and paragraph 67 through 72 of the ASME Boiler and Pressure Vessel Codes. The relief valve is vented to the radwaste collection floor drain.
The filtration and deminer alizer vessels are desi gned, fabricated and tested in accordance with ASME,Section VIII. Each filter vessel contains media for removal of suspended solids and activated corrosion products. The demineralizer vessels are loaded with ion-exchange media for removal of dissolved impurities.The treated water is discharged through control and monitoring de vices. The ef fluent of the system is transferred to the low level waste tanks for hold up and monito ring. The contents of the low level waste tanks can receive additional treatment by the demineralizers in the Waste Disposal Bldg., can be transferred back to the High Level Waste Tanks, or can be discharged into the Circulating Water System.
Local control and moni toring devices are provided for pre ssure indicating flow monitoring, and conductivity monitoring within the demineralizer unit. Grab samples are taken for chemical and isotopic analysis. Low dischar ge pressure on the upstream booster pump to the IEFS stops the pump to reduce flow through the IEFS.The influent and effluent connections necessa ry for the connection of the ion exchange filtration system, along w ith all supplemental service connecti ons necessary for the operation of the system (i.e., service air, el ectrical, primary grade water suppl y and contaminated drains), are Revision 52-09/29/2016 NAPS UFSAR 11.2-4provided by Virginia Power, with in this area so that any unne cessary penetrations into this potentially contaminat ed area are minimized.
The initial setup, installation, an d testing of the ion exchange filtration system was done by qualified personnel under the di rection of Virginia Power.
The replacement of the expended filtration and demineralizer media and preparation of the expended media for transport and burial wi ll be performed by qualified personnel.
The installation and operation of the liquid wast e demineralizer system complies fully with Appendix I of 10 CFR 50.The spent resin shipping liner, demineralizers, and charcoal vessels are located behind the shield walls in the waste solidi fication area. The pump and controls are located outside the s hield walls. Health Physics provides radiological controls for the de contamination building where the system is located.
The Ion Exchange Filtration Sy stem (IEFS) has no adverse ef fect on station operations or the operation of safety-related equipment. The desi gn specifications meet the specifications of the previously existing system and a ll additional piping is located in areas previously designated for liquid waste processing.
Limitation of personnel exposure is achieved by the site locati on and installed shielding of the demineralizer s ystem. The system is designated to be located within a protected, shielded area normally used for the handling and so lidification of ra dioactive waste.The control panel, with all the functions and indications necessary for the safe operation or shutdown of the system, is located outside the walled-in area. Personnel entry into the walled-in area will be for short duration for minor ma nual adjustment and control of the system.11.2.3 Operating ProceduresSystem influents from the vent and drain syst em, which include the ef fluent from various building sumps, are directed by valve lineup to either the high-level or low-level waste drain tanks, according to influent activity level.
Laundry waste and cold laborat ory drainage, personnel de contamination area (PDA) shower drainage, and PDA sink drainage are di scharge into the contaminated drain tanks.Hot laboratory drainage and spent resin flus h water are discharged directly into the high-level waste drain tanks.
High-level liquid waste from the vent and dr ain, liquid waste disposal, chemical and volume control, and boron recovery systems is discharged to the high-level waste drain tanks. The contents of the high-level wast e drain tanks, which may have activity levels of up to 10
-1 µCi/ml, Revision 52-09/29/2016 NAPS UFSAR 11.2-5 are processed by the io n exchanger filtration system. The contents of these tanks may be transferred to the low-level wast e drain tanks by means of a line under administrative control in the event that the high-level waste drain tank contents do not require further treatment. The decontamination system fl uid waste treating tank (Section 9.5.9) in the deconta mination building can be used for additional storag e of high-level wastes. The influe nt to the high-level drain tanks also may include the contents of the low-leve l drain tanks and the contaminated drain tanks should the activity level of the liquids in these tanks require further processing. The high-level tanks afford a holdup period for sampling the liquid before it is processed.
The low-level waste drain tanks accumulate low-level waste li quid from the IEFS, vent and drain, and boron recovery systems as well as from the fl uid waste treating tank, and boron recovery test tanks. The conten ts of the low level waste drain tanks are pumped to the waste header, through the clarifier, and are discharged to the circulati ng water system or are processed through the Liquid Waste Demineralizer, if needed prior to discharge.The demineralizers in the Waste Disposal Bl dg. also could receive liquids from the contaminated drain tank, the steam generator bl owdown tank, and the blow down from the Service Water Reservoir. These liquids are monitored pr ior to release to ensu re that the limits of 10 CFR 20 will not be exceeded. Offsite dose calculations, based on ef fluent samples obtained at this release point, are performed to ensure the limits of 10 CFR 50, Appendix I are not exceeded.All liquid waste discharges to the circulati ng water s ystem are moni tored as described in Section 11.4.2.12 to ensure radiological control. Periodic sampling of the liquid waste ef fluent is conducted as described in Section 11.4.4.1. Liquid waste discharges are automatically isolated downstream of the clarifie r demineralizer filter on a signal from the radiation monitor. This valve is also operated remotely from th e main control room or automa tically by a signal from the clarifier surge tank level switches. High activity detected by the radiatio n monitor overrides the valve control and stops all discharge flow. The discharge flow from the liquid waste disposal system is combined and mixed with the water in the circulating-water discharge tunne l so that the concentration of activity of the combined effl uent is maintained AL ARA and well within the limits established by a pplicable regulations.11.2.4 Performance TestsAll effluent is monitored for radioactivity prior to release, a sample is taken for detailed radiological analysis, and a record of flow rate and total is made.
Periodic testing is performed to ensure function and calibration of the final radiation moni tor and the flow reco rder on the ef fluent line.11.2.5 Estimated Releases The design objective of the liqui d waste disposal system is to maintain releases ALARA and within the limits of 10 CFR 20, 10 CFR 50, and 10 CFR 100. Releases due to accidents are Revision 52-09/29/2016 NAPS UFSAR 11.2-6 discussed in Chapter 15. To demonstrate how this objective is accomplished in other cases, this section presents estimate s of liquid releases for two cases, expected and desi gn. These estimated releases are based on the original plant configur ation and liquid wast e processing options assumed at the time of initial plant licensing. The expected releases are base d on circumstances and equipment parameters that could occur duri ng normal station opera tion and anticipated operational occurrences. The design releases are representative only of short-term releases that could occur only if all systems in both units degrad ed to the conditions stated in the assumptions. Such degradation is extremely unrealistic. Even wi th the high degree of c onservatism inherent in the analysis for the design case, the results indicate that operation of Units 1 and 2 and the associ ated radioactive liquid waste re leased does not exceed the limits of 10 CFR 20 and therefore does not represent a hazard to the heal th and safety of the general public. The doses associated with the expected releases are discussed in Section 11.2.8.Flow charts of the liquid wa ste disposal system (Units 1 and 2) are shown in Figure 11.2-3 (design) and Figure 11.2-4 (expected). The liquid waste disposal system is designed to minimize the discharge of radioactivity contained in liquid ef fluent from the station. To accomplish this, extensive use is made of de mineralization and filtration.
These estimated activities are based upon th e conservative assumptions listed in Section 11.1 , an operating time of 365 days (100% capacity facto r) in the design case and 300 days in the expected cas e (80% capacity factor).
Figure 11.2-3 lists, for the design case, the estimated qu antities and activit ies of radioactive waste liquid from various sources and the waste treatment that each undergoes before being released from Units 1 and 2. Figure 11.2-4 does the same for the expected case. Tables 11.2-2 through 11.2-6 and Tables 11.2-7 through 11.2-11 expanded this information on a nuclide-by-nuclide basis for the design and expected cases, respectively. Tables 11.2-12 and 11.2-13 list the estimated activity and discharge rate of each radionuclide at the point of discharge for the design and expected cases, respectively.The concentrations by nuclide in the liquid waste disposal syst em, the discharge canal, the Waste Heat Treatment Facility, and the North Anna Reservoir are presented in Tables 11.2-12 and 11.2-14 through 11.2-16 for the design case and Tables 11.2-13 and 11.2-17 through 11.2-19 for the expected case.
The activities in Table 11.2-7 are considered an extremely conservative upper bound for short-term releases. The total nont ritium activity discharged from Units 1 and 2, assuming that Units 1 and 2 operate continuously at full power with system degradations expressed in the assumptions for the design case, is 332 Ci/yr.A significant amount of tritium may be accumula ted in the reactor coolant system. Tritium is considered separately because it is relatively insensitive to waste treatment. It is usually in the form of tritiated water and during normal opera tion is found in the reactor cool ant, boron Revision 52-09/29/2016 NAPS UFSAR 11.2-7recovery, sampling, vent and drain, liquid waste, and refueling water storage systems. Tritiated water behaves in the liquid waste disposal system essentially the same as ordinary water.
Assuming one unit on its equilibrium fuel cycle, one unit on its initial fuel cycle and 1% ternary fission release, it is estimated that 1183 Ci/yr. of tritium are availabl e for release from the station for both the design and expected cases.
Appendix 11A discusses tritium control by us e of Zircaloy clad fuel and silver-indium-cadmium control r ods. The appendix details possible tritium sources, and evaluates plant design factors and potential for discharge.
The fraction of the primary coolant tritium that actually is discharged from the station depends upon the primary-grade water management at the station. However, the conservative assumption is made for this analysis that all of the 1183 Ci are discharged from the station.11.2.5.1 Estimated Activities in North Anna Reservoir and Waste Heat Treatment FacilityEffluent from the liquid waste disposal syst em is the source of radionuclides in the North Anna Reservoir and Waste Heat Treatment Faci lity. This effluent is discharged from the station into the discharge canal, where it is d iluted by the circulating water supplied from the reservoir and is then discharged into the Waste Heat Treatment Facility.
Radionuclides that enter the Waste Heat Treatment Facility via this route can eventually pass into the reservoir at the skimmer wall structure, which is the outlet from the Waste Heat Treatment Facility to the reservoir. From the reservoir, the radionuclides either flow over the dam and spillway or are recirculated to the circulating-water intake. The following model and differential equations were developed to calculate the concentration of any ra dionuclide in the reservoir and in the Waste Heat Treatment Facility:(11.2-1)Circulating waterdischarge canal P R IL R EL R LR R LR R ER R RL R RL R ORNorthAnna ReservoirWaste Heat Treatment Facility R IR dN R dt----------
R LR V L----------N L R ER R OR R RL++V R-------------------------------------------
-+N R-=
Revision 52-09/29/2016 NAPS UFSAR 11.2-8(11.2-2)where, for any radionuclide:
N R= curies in the reservoir at time t N L = curies in the Waste Heat Treatment Facility at time t V R = volume of the reservoir, cm 3 V L = volume of the Waste Heat Treatment Facility, cm 3P = Ci/sec discharged from the plant to the circulating watert = time, sec
= decay constant, sec
-1 R IR = inlet flow rate to the re servoir from the environment, cm 3/sec R EL = evaporation rate from the Waste Heat Treatment Facility, cm 3/sec 1 R IL = inlet flow rate to the Waste Heat Tr eatment Facility from the environment, cm 3/sec R OR = (R IR + R IL - R ER - R EL) = overflow rate from the reservoir, cm 3/sec R RL = recirculation flow rate from the reservoir to the Waste Heat Treatment Facility, cm 3/sec R ER = evaporation rate from the reservoir, cm 3/sec 2 R LR = (R LR + R IL -R EL) = return flow from the Waste Heat Treatment Facility to the reservoir, cm 3/sec Let:(11.2-3)(11.2-4)1.Evaporation rates are removal terms for tritium only. For all other radionuclides, R EL and R ER are set equal to zero in the differential equations and no credit is taken for the removal of the other radionuclides by evaporation.2.Evaporation rates are removal terms for tritium only. For all other radionuclides, R EL and R ER are set equal to zero in the differential equations and no credit is taken for the removal of the other radionuclides by evaporation.
dN L dt----------P R RL V R----------N R R EL R LR+V L--------------------------+N L-+=R R ER R OR R RL++V R-------------------------------------------
-+=L R EL R LR+V L--------------------------+=
Revision 52-09/29/2016 NAPS UFSAR 11.2-9 At equilibrium, the concentration (µCi/cm 3) in the North Anna Reservoir and Waste Heat Treatment Facility is:(11.2-5)(11.2-6)The concentration in the discharge canal is:(11.2-7)(11.2-8)The maximum permissible concentrations (MPC) of radionuclides set forth in 10 CFR 20 are not to be exc eeded in the North Anna Reservoir, Waste Heat Tr eatment Facility, or discharge canal for the design case. Because of recirculation effects, and because the discharge point from the station is at the discharge canal, the point of maximum concentration for any radionuclide is in the discharge canal. Thus, the concentration in the discharge canal is limiting in this analysis.
For a single radionuclide, i, the concentration in the dischar ge canal must be less than MPC, so that the maximum allowable discharge rate, P i, for that radionuclide, if it alone were discharged from the station, would be:(11.2-9)For a mixture of radionuclides of known concentrations, 10 CFR 20 requires that:(11.2-10)Let:X = gross activity discharge rate from the wa ste disposal system, excluding tritium, Ci/sec f i = fraction of nuclide i in the nontritium mixture Then Xf i = discharge rate of nuclide i in the mixture of known concentrations, Ci/secThe concentration in the discharge canal of nuclide i is: C R N R V R-------P x R LRLR V L V R R RL R LR--------------------------------------------------------
==C L N L V L-------P x R V RLR V L V R R RL R LR--------------------------------------------------------
==C C P R RL----------C R+=C C P R RL----------LR V L V RLR V L V R R RL R LR--------------------------------------------------------
=P i MPC i R RLLiRi V L V R R RL R LR-LiRi V L V R----------------------------------------------------------
-C 1 MPC 1---------------
C 2 MPC 2---------------
C 3 MPC 3---------------
1+++
Revision 52-09/29/2016 NAPS UFSAR 11.2-10(11.2-11)Let:(11.2-12)Substituting into Equation 11.2-10 gives:(11.2-13)and:(11.2-14)Equation 11.2-14 gives the maximum gross activity dischar ge rate for a mixture of known concentration, so that 10 CFR 20 is not exceeded in the discharge canal, and Xf i gives the maximum discharge rate of an indi vidual radionuclide in that mixture.The radionuclides that could be discharge fro m the waste disposal system are listed in Table 11.2-12 for the design case and Table 11.2-13 for the expected case.From Table 11.2-12 and Table 11.2-13 , it is estimated that 332 Ci/yr. are discharged from the station for the design case and 3.50 Ci/yr. for the expected case. These values do not include tritium, of which there are 1 183 Ci/yr. available for re lease. Based on the expected release rates for tritium and nontritium activity, the following equilibrium concentrations may be expected at the station:
LocationConcentrations (pCi/1)
Gross Beta a T ritium Discharge canal4.785470 Waste Heat Treatment Facility1.385270 North Anna Reservoir0.704080a.Gross beta is used to express total nontritium activity, since the environmental progress calls for gross beta measurements and the nuclides that contribute more than 90% of the activity are 100% beta emitters C Ci Xf i R RL----------LiRi V L V RLiRi V L R R R RL R LR----------------------------------------------------------
-=R RL i 1 R RL----------LiRi V L V RLiRi V L V R R RL R LR-----------------------------------------------------------
=P H3 R RLH3 MPC H3---------------
Xf i R RLi MPC i-------------------
-1+X 1 P H3 R RLH3 MPC H3-------------
-f i R RLi MPC i-------------------------------------------------------
Revision 52-09/29/2016 NAPS UFSAR 11.2-11 Thus liquid releases may result in detectable radioactivity levels in the lake water, which in turn could result in detect able radioactivity levels in fish living in the lake and in the sediments of the lake bed.
Samples of the above three medi a are taken from the Waste Heat Treatment Facility and the North Anna Reservoir. River water and silt are also sampled downstream from the dam site.
Groundwater movement is described in Section 2.4.13.From the above, the fraction of each radionuclide (f i in Equation 11.2-14) in a mixture of known concentration at the point of dischar ge from the station can be determined. Assuming that these fractions remain constant, and assuming that the discharg e rate of tritium remains constant, the maximum permissible release rate based on MPC values from the waste disposal system of each radionuclide in the mixture was calculated using Equation 11.2-14. These values are listed in Table 11.2-12 for the design case along with the allowabl e release rate for a single radionuclide based on Equation 11.2-9.In this analysis, volumes and flow conditions for the average North Anna Reservoir and the Waste Heat Treatment Facility were used. These values are listed in Table 11.2-20. The total amount of water in the North Anna Reservoir and the Waste He at Treatment Facility and the amount of overflow at the dam va ry between the dry and wet seas ons; hence, the concentrations also vary. However, because the average reside nce time of the body of water comprising both the North Anna Reservoir an d the Waste Heat Treatment Facility is nearly 2 years, it takes about 7 years for a long-lived radionuclide to r each equilibrium in either the North Anna Reservoir or the Waste Heat Treatment Facility. Since projected minimum North Anna Reservoir overflow rates cannot be sustained for this length of time, there is justification for us ing average flows and volumes rather than minimum va lues. The most limiting circul ating water flow rate possible (i.e. operation of one unit with two circ ulating water pumps) is used fo r the station as the basis for liquid pathway dose commitment calculations. It s hould be noted that credit was not taken for radioactive decontamination inhe rent in the reserv oir or treatment fa cilities for various radionuclides, since there is no accurate means of estimating or calculating it.11.2.6 Release PointsThe only release point from the liquid waste disp osal system to the environment is to the circulating-water discharge tunne l as shown on Reference Drawing
- 3. The circulating-water discharge tunnel flows into the discharge canal (C anal A) via the seal pit as shown on the site plan, Reference Drawing 6.11.2.7 Dilution FactorsTables 11.2-12 and 11.2-14 through 11.2-16 for the design case and Tables 11.2-13 and 11.2-17 through 11.2-19 for the expected case list the concentrations of radionuclides, including tritium, in the liquid waste disposal system, the discharge canal, the Waste Heat Revision 52-09/29/2016 NAPS UFSAR 11.2-12Treatment Facility, and the North Anna Reservoir. It can be seen fr om th ese tables that, even with recirculation, the equilibrium co ncentration for any single radionuc lide decreases in passing from the discharge canal to the Waste Heat Treatment Facility and then to the North Anna Reservoir, the highest concentration being in the liq uid waste disposal system, as expected.
For the design case, the total nontritium ac tivity per unit volume from a mixture of radionuclides in the liquid waste disposal system with an 90.8 gpm flow rate is reduced by a factor of 2.1 x 10-4 owing to volume dilution in the discharge canal at a flow rate of 962 cfs. Because of recirculation ef fects, the actual dilution factor is 3.1 x 10-4.Furthermore, the effective dilu tion factor is 0.49 for the Waste Heat Treatment Facility and 0.67 for the North Anna Reservoir; hence, there is an overall dilution factor of 1.0 x 10-4 from the liquid waste disposal system to the North Anna Reservoir.
For the expected case, the total nontritium activity per unit volume from a mixture of radionuclides in the liquid wast e disposal system with a 78.7 gpm flow rate is reduced by a factor of 1.8 x 10-4 owing to volume dilution in the discharge canal at a flow rate of 962 cfs. Because of recirculation ef fects, the actual dilution factor is 2.2 x 10-4.For this case, the effective di lution factor is 0.29 for the Waste Heat Treatment Facility and 0.51 for the North Anna Reservoir; the result is an overall dilution factor of 3.2 x 10-5 from the liquid waste disposal system to the North Anna Reservoir.
The model and method used to ca lculate the estimated concentrations due to releases from the liquid waste disposal system are presented in Section 11.2.5.11.2.8 Estimated Doses from Liquid Effluents The potential radiological impact of the antici pated releases of sma ll amounts of liquid radioactivity from the station has been evaluated in detail. A full and complete description of the analysis is contained in Appendix 11B. A summary of the doses resu lting from expected liquid radwaste releases for a core utilizing a 15 x 15 fuel assembly array is presented here.Potential radiation dosage fr om liquid releases calculate d for the expected case was estimated both for the population as a whole and for a hypothetical maximally exposed individual.
All dosage levels are based on th e estimated equilibrium radioact ivity concentrations for the station Waste Heat Treatment Facility and for the North Anna Reservoir. Thes e concentratio ns are presented in Tables 11.2-18 and 11.2-19. The potential maximum individual exposure was evaluated for the following exposure pathways.1.Daily ingestion of 1.2 liters of water taken from the rese rvoir or the Waste Heat Treatment Facility.2.Daily ingestion of 50g of fish taken from the reservoir or the Waste Heat Treatment Facility.3.Swimming 200 hr/yr in the reservoir or Wa ste Heat Treatment Facility.
Revision 52-09/29/2016 NAPS UFSAR 11.2-134.Boating 500 hr/yr in the reservoir or Wa ste Heat Treatment Facility.5.Sunbathing 300 hr/yr along the reservoir or Wa ste Heat Treatment Facility.
The resulting whole-bod y and body-or gan exposure rates as calculated by SWEC computer codes IND1109E and DUCKMANE are presented in Table 11.2-21 for exposure from use of the North Anna Reservoir, and in Table 11.2-22 for exposure from the use of the Waste Heat Treatment Facility.The maximum total annual whole-body dose has been calculated as 3.878 mrem for both units. This figure includes 1.646 mrem from exposure via various pa thways from radwaste in the North Anna Reservoir and 2.232 mrem from exposure via various pa thways from radwaste in the Waste Heat Treatment Facility.
Although the two doses have been added here, a single individual could experience only e xposure to one or the other, or a mixture of th e two, which would not exceed the 2.232 mrem from the Waste Heat Treatment Facility. The maximum annual organ dose is 5.088 mrem for both units. The dose s hown is a liver dose; all other or gans receive a smaller dose. It includes 2.156 mrem from the reservoir and 2.932 mrem from the Wast e Heat Treatment Facility. As stated above, the dose to the liver of a single i ndividual would not exceed the 2.932 mrem from the Waste Heat Treatment Facility. As a co mparison, the maximum doses permitted by 10 CFR 50, Appendix I as the total annual body dos e and the annual or gan dose are 3 mrem per reactor and 10 mrem per reactor, respectively, for each reactor at a site. Therefore, all exposure rates, even though calculated very co nservatively, fall within the limits set by Federal regulations.
The potential population exposure due to the expe cted releases of liqui d radwaste has been conservatively evaluated. The Environmental Re port prepared to support the licensing of North Anna concluded that there are no known potable water withdrawals a nd only very limited recreational potential along the entire course of the North Anna River downstream from the site to West Point, about 65 miles southeast. The Environmental Re port also concluded that there were no withdrawals of North Anna River waters for public or pr ivate use within Spotsylvania or Louisa counties. Hence, all significant sources of population exposure due to liquid radwaste release stem from public use of the cooling water storage system. Potential sources of exposure considered significant are the use of the system as a source of water and fish, and its use for recreational activitie s such as swimming, boating, and sunbathing.For each pathway considered to be of potential importance, the total pop ulation exposures that could be expected to occu r in the year 2000 we re evaluated. Conser vative projections of community development and recreational use of the reservoir were used in each case.Also, since there are no physical impediments to the use of the reservoir as a community water supply source, it was assumed that this was already the case.
The resulting population exposure rates are presented and totaled in Table 11.2-23. Appendix 11B contains a full explanation of their derivation.
Revision 52-09/29/2016 NAPS UFSAR 11.2-1411.2 REFERENCE DRAWINGSThe list of Station Drawings below is provided fo r information only. The referenced drawings are not part of the UFSAR. This is not intended to be a complete listing of all Station Drawings referenced from this section of the UFSAR. The contents of St ation Drawings are controlled by station procedure.
Drawing Number Description 1.11715-FM-087AFlow/Valve Operating Number s Diagram: Waste Disposal System, Unit 1 2.11715-FM-087BFlow/Valve Operating Number s Diagram: Waste Disposal System, Unit 1 3.11715-FM-087CFlow/Valve Operating Number s Diagram: Waste Disposal System, Unit 1 4.11715-FM-087DFlow/Valve Operating Number s Diagram: Waste Disposal System, Unit 1 5.11715-FM-087EFlow/Valve Operating Number s Diagram: Waste Disposal System, Unit 1 6.11715-FY-1BSite Plan, Units 1 & 2 Revision 52-09/29/2016 NAPS UFSAR 11.2-15Table 11.2-1 LIQUID WASTE DISPOSAL EQUIPMENT DESIGN DATAHigh-Level Waste Drain Tank Number 2 Capacity per tank 5000 gal Design pressure 25 psig Design temperature 200°F Operating pressure Atmospheric Operating temperature 120°F Material SS 316 Design Code ASME VIII, Division 1, 1968Low-Level Waste Drain Tank Number 2 Capacity per tank 5000 gal Design pressure 25 psig Design temperature 200°F Operating pressure Atmospheric Operating temperature 120°F Material SS 316 Design Code ASME VIII, Division 1, 1968Waste Disposal Evaporator Test Tanks Number 2 Capacity per tank 1500 gal Design pressure 25 psig Design temperature 250°F Operating pressure Atmospheric Operating temperature 140°F Material SS 304 Design Code ASME VIII, Division 1, 1968Contaminated Drain Collection Tanks Number 2 Capacity per tank 1050 gal Design pressure 15 psig Design temperature 200°F Operating pressure Atmospheric Operating temperature 120°F Material SS 304 Design Code ASME VIII, Division 1, 1968 Revision 52-09/29/2016 NAPS UFSAR 11.2-16Low-Level Waste Drain Tank Pumps Number 2Type Horizontal centrifugal Motor horsepower 7.5 Seal type Mechanical Capacity per pump 50 gpm Head at rated capacity 150 ft Design pressure 220 psig Materials Casing SS 316 Shaft SS 316 Impeller SS 316High-Level Waste Drain Tank Pumps Number 2Type Horizontal centrifugal Motor horsepower 3 Seal typeDouble mechanical Capacity per pump 12 gpm Head at rated capacity 97 ft Design pressure 220 psig Materials Pump casing SS 316 Shaft SS 316 Impeller SS 316Waste Disposal Evaporator Test Tank Pumps Number 2Type Horizontal centrifugal Motor horsepower 10 Seal type Mechanical Capacity per pump 50 gpm Head at rated capacity 195 ft Design pressure 220 psig Materials Pump casing SS 316 Shaft SS 316 Impeller SS 316Table 11.2-1 (continued)
LIQUID WASTE DISPOSAL EQUIPMENT DESIGN DATA Revision 52-09/29/2016 NAPS UFSAR 11.2-17Contaminated Drain Transfer Pumps Number 2Type Horizontal centrifugal Motor horsepower 7.5 Seal type Mechanical Capacity per pump 50 gpm Head at rated capacity 126 ft Design pressure 220 psig Materials Pump casing SS 316 Shaft SS 316 Impeller SS 316Steam Generator Blowdown Tank Pumps Number 2Type Horizontal centrifugal Motor horsepower 7.5 Seal type Mechanical Capacity per pump110 gpm Head at rated capacity 101 ft Design pressure 220 psig Materials Pump casing SS 316 Shaft SS 316 Impeller SS 316 Clarifier Discharge Pumps Number 2Type Horizontal centrifugal Motor horsepower 25 Seal type Mechanical Capacity per pump 300 gpm Head at rated capacity 145 ft Design pressure 220 psig Materials Pump casing SS 316 Shaft SS 316 Impeller SS 316Table 11.2-1 (continued)
LIQUID WASTE DISPOSAL EQUIPMENT DESIGN DATA Revision 52-09/29/2016 NAPS UFSAR 11.2-18Steam Generator Blowdown Heat Exchanger Number 2Total duty 5.1 x 10 6 Btu/hr ShellTube Design pressure 150 psig 150 psig Design temperature 150°F 250°F Operating pressure 70 psig 20 psig Operating temperature, in/out 105°F/125.5°F 212°F/120°F MaterialCarbon SteelSS 304 FluidWaterWater Design Code ASME VIII, Division I, 196 8ASME VIII, Division 1, 1968Waste Disposal Evaporator Distillate Demineralizer Number 1 Design flow 100 gpmDemineralizer, resinorganic anion resin Active volume 17 ft 3 Design pressure 200 psig Design temperature 250°F Operating temperature 130°F Material SS 316L Design Code ASME VIII, Division 1, 1968Clarifier Demineralizer Number 2 Design flow 200 gpmDemineralizer, resinH-OH mixed bed or organic anion resin with inor ganic oxide for cation exchange Active volume 45 ft 3 Design pressure 200 psig Design temperature 250°F Operating temperature 125°F Material SS 316L Design Code ASME VIII, Division 1, 1968Liquid Waste Effl uent Filters Number 2Retention size 5 µmFilter element materialCottonTable 11.2-1 (continued)
LIQUID WASTE DISPOSAL EQUIPMENT DESIGN DATA Revision 52-09/29/2016 NAPS UFSAR 11.2-19 Normal capacity 50 gpmMaximum capacity 75 gpm Material SS 304 Design pressure 150 psig Design temperature 250°F Design Code ASME VIII, Division 1, 1968Waste Disposal Distillate Filter Number 1Retention size 3 µmFilter element material Synthetic fiber Normal capacity 40 gpmMaximum capacity 75 gpm Material SS 304 Design pressure 150 psig Design temperature 250°F Design Code ASME VIII, Division 1, 1968Spent Resin Dewatering Filter Number 1Retention size 5 µmFilter element materialCotton Normal capacity 100 gpmMaximum capacity 150 gpm Material SS 304 Design pressure 150 psig Design temperature 250°F Design Code ASME VIII, Division 1, 1968Clarifier Filters Number 6Filter element material Sand Normal capacity 65 gpmMaximum capacity 100 gpm Material Carbon steel Design pressure 150 psig Design temperature 120°F Design Code ASME VIII, Division 1, 1968Table 11.2-1 (continued)
LIQUID WASTE DISPOSAL EQUIPMENT DESIGN DATA Revision 52-09/29/2016 NAPS UFSAR 11.2-20Clarifier Demineralizer Filters Number 2Retention size 3 µmFilter element material Synthetic fiber Normal capacity 200 gpmMaximum capacity 300 gpm Material SS 304 Design pressure 150 psig Design temperature 250°F Design Code ASME VIII, Division 1, 1968 Clarifiers Number 2Maximum capacity 300 gpmHold-up time 2 hr at 200 gpm Rise rate 0.75 gpm/ft 2 at 200 gpm Diameter 19 ft Height 14 ft MaterialSteel Design CodeAWWA-D-100-65 DF (including clarifier demineralizer) 100 for all radionuclides except Mo, I, and Te, for which DF equals 10Resin Transfer Pump Number 2Type Positive displacement, progressing cavitySeal Type Mechanical Motor horsepower 10 Capacity 30 gpm Head at rated capacity 87 ft Material Pump casing SS 316Stator Natural rubber Rotor SS 316Vendor-Supplied Filter/DemineralizerData are not listed here because Virginia Power may utilize various suppliers for this system.
Specific design data is contained in Company records.Table 11.2-1 (continued)
LIQUID WASTE DISPOSAL EQUIPMENT DESIGN DATA Revision 52-09/29/2016 NAPS UFSAR 11.2-21Table 11.2-2 ACTIVITY FROM STEAM GENERATOR BLOWDOWN - DESIGN CASEDF Waste Disposal System for this Source = 1.00E+01 Decay Time in Waste Disp Sys (hours) = 0.0 Flow Rate (gal/yr) = 1.97E+07NuclideInitial Activity
(µC/GM)Activity After Treatment (µC/GM)Discharge Rate from W.D. System (Ci/yr)
CR51 2.2E-06 2.2E-07 1.6E-02 MN54 1.9E-06 1.9E-07 1.4E-02 CO58 6.0E-05 5.9E-06 4.4E-01 FE59 2.5E-06 2.5E-07 1.8E-02 CO60 1.8E-06 1.8E-07 1.3E-02 RB88 2.3E-04 2.3E-05 1.7E+00 SR89 9.4E-06 9.3E-07 6.9E-02 SR90 3.5E-07 3.5E-08 2.6E-03 SR91 2.2E-06 2.2E-07 1.6E-02 Y90 4.1E-07 4.1E-08 3.0E-03 Y91 1.2E-05 1.1E-06 8.5E-02 ZR95 1.7E-06 1.7E-07 1.3E-02 NB95 1.7E-06 1.7E-07 1.3E-02 TC99M 9.9E-03 9.9E-04 7.3E+01 MO99 1.1E-02 1.1E-03 8.4E+01 I131 5.8E-03 5.8E-04 4.3E+01 I132 8.5E-04 8.5E-05 6.3E+00 I133 6.4E-03 6.4E-04 4.7E+01 I134 1.0E-04 1.0E-05 7.5E-01 I135 1.5E-05 1.5E-06 1.1E-01 TE132 5.7E-04 5.7E-05 4.2E+00 CS134 6.6E-04 6.6E-05 4.9E+00 CS136 2.7E-04 2.7E-05 2.0E+00 CS137 3.3E-03 3.3E-04 2.4E+01 BA137M 3.0E-03 3.0E-04 2.2E+01 BA140 1.0E-05 1.0E-06 7.5E-02 LA140 5.1E-06 5.1E-07 3.8E-02 CE144 8.0E-07 8.0E-08 5.9E-03TOTAL 4.3E-02 4.3E-03 3.2E+02 Revision 52-09/29/2016 NAPS UFSAR 11.2-22Table 11.2-3ACTIVITY FROM LAUNDRY DRAINS - DESIGN CASEDF Waste Disposal System for this Source = 1.00E+01 Decay Time in Waste Disp Sys (hours) = 0.0 Flow Rate (gal/yr) = 2.63E+06 NuclideInitial Activity
(µC/GM)Activity After Treatment (µC/GM)Discharge Rate from W.D. System (Ci/yr)
MN54 1.0E-07 1.0E-08 9.9E-05 CO58 4.1E-07 4.0E-08 4.0E-04 CO60 9.1E-07 9.1E-08 8.9E-04 ZR95 1.4E-07 1.4E-08 1.4E-04 NB95 2.0E-07 2.0E-08 2.0E-04 RU103 1.4E-08 1.4E-09 1.4E-05 RU106 9.3E-07 9.3E-08 9.2E-06 RH103M 9.2E-07 2.4E-08 9.2E-06 RH106 2.4E-07 2.4E-08 2.3E-04 I131 6.0E-08 6.0E-09 5.9E-05 CS134 1.3E-06 1.3E-07 1.3E-03 CS137 2.4E-06 2.4E-07 2.3E-03 BA137M 2.1E-06 2.1E-07 2.1E-03 CE144 5.1E-07 5.1E-08 4.9E-04 PR-144 4.5E-07 4.5E-08 4.5E-04TOTAL 9.1E-06 9.1E-07 8.9E-03 Revision 52-09/29/2016 NAPS UFSAR 11.2-23Table 11.2-4 ACTIVITY FROM BORON RECOVERY - DESIGN CASEDF Waste Disposal System for this Source = 1.00E+06 a Decay Time in Waste Disp Sys (hours) = 8.00E+01 Flow Rate (gal/yr) = 4.38E+06 NuclideInitial Activity
(µC/GM)Activity After Treatment (µC/GM)Discharge Rate from W.D. System (Ci/yr)
CR51 9.4E-04 8.2E-10 1.3E-05 MN54 7.8E-04 7.7E-10 1.3E-05 FE59 2.5E-02 2.4E-08 3.9E-04 CO58 1.0E-03 9.2E-10 1.5E-05 CO60 7.5E-04 7.5E-10 1.2E-05 RB88 3.8E+00 2.2E-10 1.0E-05 SR89 3.4E-03 3.1E-09 5.0E-05 SR90 1.8E-04 1.8E-10 3.0E-06 SR91 2.0E-032.4E-11 4.0E-07 Y90 2.1E-04 1.9E-10 3.1E-06 Y91 6.2E-03 5.8E-09 9.6E-05 NB95 7.1E-04 6.4E-10 1.0E-05 TC99M 0.0 1.5E-06 2.5E-02 MO99 5.4E+00 1.6E-06 2.6E-02 I131 2.5E+00 1.6E-05 2.5E-02 I132 9.2E-01 1.5E-07 2.4E-01 I133 4.1E+00 2.2E-06 2.5E-03 I134 5.7E-01 5.9E-10 3.6E-02 I135 2.2E+00 1.3E-07 9.6E-06 TE132 2.7E-01 9.3E-08 2.1E-03 CS134 3.0E-01 1.5E-06 1.5E-03 CS136 1.5E-01 5.6E-07 2.6E-02a.Includes DF from Boron Recovery System Notes:1.Mixed Bed Demineralizer with DF = 100 for all Radionuclides except Cs and Rb for which the DF = 202.Cation Removal Bed with a BF in the Ch emical and Volume Control System = 10 for Cs and Rb and = 1 for all other isotopes.3.Boron Evaporator with a DF = 1000 for all Radionuclides excep t I for initial H.
DF = 100.
Revision 52-09/29/2016 NAPS UFSAR 11.2-24 CS137 1.5E-01 7.5E-07 9.1E-03 BA137M 0.0 7.1E-07 1.2E-02 BA140 4.4E-03 3.3E-09 1.1E-02 LA140 1.5E-03 3.2E-09 5.5E-06 CE144 4.5E-04 4.4E-10 7.3E-06TOTAL 2.0E+01 2.5E-05 4.1E-01Table 11.2-4 (continued)ACTIVITY FROM BORON RECOVERY - DESIGN CASEDF Waste Disposal System for this Source = 1.00E+06 a Decay Time in Waste Disp Sys (hours) = 8.00E+01 Flow Rate (gal/yr) = 4.38E+06 NuclideInitial Activity
(µC/GM)Activity After Treatment (µC/GM)Discharge Rate from W.D. System (Ci/yr)a.Includes DF from Boron Recovery System Notes:1.Mixed Bed Demineralizer with DF = 100 for all Radionuclides except Cs and Rb for which the DF = 202.Cation Removal Bed with a BF in the Chemical and Volume Control System = 10 for Cs and Rb and = 1 for all other isotopes.3.Boron Evaporator with a DF = 1000 for all Radionuclides excep t I for initial H.
DF = 100.
Revision 52-09/29/2016 NAPS UFSAR 11.2-25Table 11.2-5 ACTIVITY FROM PRIMARY COOLANT SYSTEM LEAKAGE (HLWDT) -
DESIGN CASE aDF Waste Disposal System for this Source = 1.00E+06 Decay Time in Waste Disp Sys (hours) = 1.67E+00 Flow Rate (gal/yr) = 2.10E+07NuclideInitial Activity
(µC/GM)Activity After Treatment (µC/GM)Discharge Rate from W.D. System (Ci/yr)
CR51 1.9E-04 1.9E-10 1.5E-05 MN54 1.6E-04 1.6E-10 1.3E-05 FE59 5.3E-03 5.1E-09 4.0E-04 CO58 2.0E-04 2.0E-10 1.6E-05 CO60 7.8E-01 1.5E-10 1.2E-05 RB88 1.6E-04 2.4E-06 1.9E-01 SR89 7.0E-04 7.0E-10 5.5E-05 SR90 3.7E-053.7E-11 2.9E-06 SR91 4.1E-04 3.6E-10 2.8E-05 Y90 4.0E-054.1E-11 3.2E-06 Y91 1.3E-03 1.3E-09 1.0E-04 ZR95 0.0 0.0 0.0NB95 1.5E-04 1.5E-10 1.2E-05 MO99 1.1E+00 1.1E-06 8.7E-02 TC99M 0.0 1.7E-07 1.3E-02 I131 5.3E-01 5.1E-05 4.0E+00 I132 1.9E-01 1.3E-05 1.0E+00 I133 8.6E-01 8.0E-05 6.3E+00 I134 1.2E-01 3.6E-06 2.8E-01 I135 4.5E-01 3.8E-05 3.0E+00 TE132 5.7E-02 5.5E-08 4.3E-03 CS134 6.1E-02 3.1E-06 2.4E-01 CS136 3.1E-02 1.5E-06 1.2E-01 CS137 3.1E-02 1.5E-06 1.2E-01 BA137M 0.0 1.2E-06 9.5E-02 BA140 9.0E-04 9.0E-10 7.1E-05 LA140 3.1E-04 3.2E-10 2.5E-06 CE144 9.4E-059.2E-11 7.2E-06a.Includes Containment Building Sumps, Safeguards Sumps, Auxiliary Building Sumps, Fuel Building Sumps, and Laboratory Drains.
Revision 52-09/29/2016 NAPS UFSAR 11.2-26TOTAL 4.2E+00 2.0E-04 1.6E+01Table 11.2-5 (continued)ACTIVITY FROM PRIMARY COOLANT SYSTEM LEAKAGE (HLWDT) - DESIGN CASE aDF Waste Disposal System for this Source = 1.00E+06 Decay Time in Waste Disp Sys (hours) = 1.67E+00 Flow Rate (gal/yr) = 2.10E+07NuclideInitial Activity
(µC/GM)Activity After Treatment (µC/GM)Discharge Rate from W.D. System (Ci/yr)a.Includes Containment Building Sumps, Safeguards Sumps, Auxiliary Building Sumps, Fuel Building Sumps, and Laboratory Drains.
Revision 52-09/29/2016 NAPS UFSAR 11.2-27Table 11.2-6 ACTIVITY FROM DECONTAMINATION BUILDING SUMPS - DESIGN CASEDF Waste Disposal System For This Source = 1.00E+06 Decay Time in Waste Disp Sys (hours) = 4.59 Flow Rate (gal/yr) = 5.03E+05NuclideInitial Activity
(µC/GM)Activity After Treatment (µC/GM)Discharge Rate from W.D. System (Ci/yr)
CR51 9.4E-06 9.2E-12 1.7E-08 MN54 7.8E-06 7.8E-12 1.5E-08 FE59 2.5E-04 2.5E-10 4.7E-07 CO58 1.0E-05 9.9E-12 1.9E-08 CO60 7.5E-06 7.5E-12 1.4E-08 RB88 3.8E-02 2.8E-09 5.3E-06 SR89 3.4E-053.4E-11 6.4E-08 SR90 1.8E-06 1.8E-12 3.4E-09 SR91 2.0E-05 5.6E-12 1.1E-08 Y90 2.1E-06 1.9E-12 3.6E-09 Y91 6.2E-056.1E-11 1.2E-07 ZR95 0.0 0.0 0.0NB95 7.1E-06 7.0E-12 1.3E-08 MO99 5.4E-02 4.3E-08 8.1E-05 TC99M 0.0 3.3E-08 6.2E-05 I131 2.5E-02 2.3E-06 4.3E-03 I132 9.1E-03 1.9E-07 3.6E-04 I133 4.1E-02 2.1E-06 4.0E-03 I134 5.7E-03 6.7E-09 1.2E-05 I135 2.2E-02 4.3E-07 8.1E-04 TE132 2.7E-03 2.2E-09 4.1E-06 CS134 3.0E-03 1.5E-07 2.8E-04 CS136 1.5E-03 7.1E-08 1.3E-04 CS137 1.5E-03 7.5E-08 1.4E-04 BA137M 0.0 6.4E-08 1.2E-04 BA140 4.4E-054.2E-11 7.9E-08 LA140 1.5E-052.3E-11 4.3E-08 CE144 4.5E-06 4.5E-12 8.5E-09TOTAL 2.0E-01 5.5E-06 1.0E-02 Revision 52-09/29/2016 NAPS UFSAR 11.2-28Table 11.2-7 ACTIVITY FROM STEAM GENERATO R BLOWDOWN - EXPECTED CASEDF WAste Disposal System for this Source = 1.00E+01 Decay Time in Waste Disp Sys (hours) = 0.0 Flow Rate (gal/yr) = 4.80E+07NuclideInitial Activity
(µC/GM)Activity After Treatment (µC/GM)Discharge Rate from W.D. System (Ci/yr)
CR51 2.4E-07 2.4E-08 4.3E-03 MN54 5.3E-08 5.3E-09 9.5E-04 FE55 2.1E-07 2.1E-08 3.8E-03 FE59 1.6E-07 1.6E-08 2.9E-03 CO58 2.1E-06 2.1E-07 3.8E-02 CO60 2.4E-07 2.4E-08 4.3E-03 SR89 5.3E-08 5.3E-09 2.6E-04 SR90 1.1E-09 1.1E-10 2.0E-05 SR91 3.5E-08 3.5E-09 6.3E-04 Y90 1.9E-101.9E-11 3.4E-06 Y91M 1.1E-08 1.1E-09 2.0E-04 Y91 7.9E-09 7.9E-10 1.4E-04 Y93 1.8E-09 1.8E-10 3.2E-05 ZR95 1.1E-08 1.1E-09 2.0E-04 NB95 1.1E-08 1.1E-09 2.0E-04 MO99 9.6E-06 9.6E-07 1.7E-01 TC99M 4.8E-06 4.8E-07 8.6E-02 RU103 5.3E-09 5.3E-10 9.5E-05 RU106 1.1E-09 1.1E-10 2.0E-05 RH103M 2.3E-09 2.3E-10 4.1E-05 RH106 4.0E-103.8E-11 6.8E-06 TE125M 2.6E-09 2.6E-10 4.7E-05 TE127M 2.6E-08 2.6E-09 4.8E-04 TE127 5.3E-08 5.3E-09 9.5E-04 TE129M 1.6E-07 1.6E-08 2.9E-03 TE129 6.9E-08 6.9E-09 1.2E-03 TE131M 2.2E-07 2.2E-08 4.0E-03 TE131 2.1E-08 2.1E-09 3.8E-04 TE132 2.4E-06 2.4E-07 4.3E-02 BA-37M 9.0E-07 8.9E-08 1.6E-02 BA140 2.6E-08 2.6E-09 4.7E-04 Revision 52-09/29/2016 NAPS UFSAR 11.2-29 LA140 1.6E-08 1.6E-09 2.9E-04 CE141 1.1E-08 1.1E-09 2.0E-04 CE143 2.2E-09 2.2E-10 4.0E-05 CE144 5.3E-09 5.3E-10 9.5E-05 PR143 5.2E-09 5.2E-10 9.4E-05 PR144 2.1E-09 2.1E-10 3.8E-05 NP239 1.4E-07 1.4E-08 2.5E-03 BR83 1.2E-07 1.2E-08 2.2E-03 BR84 1.8E-08 1.8E-09 3.2E-04 BR85 2.0E-102.0E-11 3.6E-06 I130 1.5E-07 1.5E-08 2.7E-03 I131 3.3E-05 3.3E-06 5.9E-01 I132 3.3E-06 3.3E-07 5.9E-02 I133 3.3E-05 3.3E-06 5.9E-01 I134 5.0E-07 5.0E-08 9.0E-03 I135 9.7E-06 9.7E-07 1.7E-01 RB86 1.0E-08 1.0E-09 1.8E-04 RB88 7.6E-07 7.6E-08 1.4E-02 CS134 3.0E-06 3.0E-07 5.4E-02 CS136 1.5E-06 1.5E-07 2.7E-02 CS137 2.2E-06 2.2E-07 4.0E-02TOTAL 1.6E+00 1.1E-05 2.0E+00Table 11.2-7 (continued)
ACTIVITY FROM S TEAM GENERATOR BLOWDOWN - EXPECTED CASEDF WAste Disposal System for this Source = 1.00E+01 Decay Time in Waste Disp Sys (hours) = 0.0 Flow Rate (gal/yr) = 4.80E+07NuclideInitial Activity
(µC/GM)Activity After Treatment (µC/GM)Discharge Rate from W.D. System (Ci/yr)
Revision 52-09/29/2016 NAPS UFSAR 11.2-30Table 11.2-8ACTIVITY FROM LAUNDRY DRAINS - EXPECTED CASEDF Waste Disposal System for this Source = 1.00E+01 Decay Time in Waste Disp Sys (hours) = 0.0 Flow Rate (gal/yr) = 2.10E+06NuclideInitial Activity
(µC/GM)Activity After Treatment (µC/GM)Discharge Rate from W.D. System (Ci/yr)
MN54 1.3E-07 1.3E-08 1.0E-04 CO58 5.1E-07 5.1E-08 4.0E-04 CO60 1.1E-06 1.1E-07 8.7E-04 ZR95 1.8E-07 1.8E-08 1.4E-04 NB95 2.5E-07 2.5E-08 2.0E-04 RU103 1.8E-08 1.8E-09 1.4E-05 RU106 3.0E-07 3.0E-08 2.4E-04 RH103M 1.3E-08 1.3E-09 1.0E-05 RH106 3.0E-07 3.0E-08 2.4E-04 I131 7.5E-08 7.5E-09 5.9E-05 CS134 1.6E-06 1.6E-07 1.3E-03 CS137 3.0E-06 3.0E-07 2.4E-03 BA137M 2.7E-06 2.7E-07 2.1E-03 CE144 6.3E-07 6.3E-08 5.0E-04 PR144 5.7E-07 5.7E-08 4.5E-04TOTAL 1.2E-05 1.2E-06 9.5E-03 Revision 52-09/29/2016 NAPS UFSAR 11.2-31Table 11.2-9 ACTIVITY FROM BORON RE COVERY - EXPECTED CASEDF Waste Disposal System for this Source = 1.00E+06 a Decay Time in Waste Disp Sys (hours) = 8.0E+01 Flow Rate (gal/yr) = 4.38E+06 NuclideInitial Activity (µC/GM)Activity After Treatment
(µC/GM)Discharge Rate from W.D. System (Ci/yr)
CR51 2.6E-03 2.3E-09 3.8E-05 MN54 4.3E-04 4.2E-10 6.9E-06 FE55 2.2E-03 2.2E-09 2.6E-05 FE59 1.4E-03 1.3E-09 2.1E-05 CO58 2.2E-02 2.1E-08 3.4E-04 CO60 2.8E-03 2.8E-09 4.6E-05 SR89 4.9E-04 4.5E-10 7.4E-06 SR90 1.4E-051.4E-11 2.6E-07 SR91 7.9E-04 9.6E-12 1.6E-07 Y90 1.6E-061.0E-11 1.6E-07 Y91M 4.0E-04 6.5E-12 1.1E-07 Y91 8.9E-04 8.4E-10 1.4E-05 Y93 4.2E-05 5.9E-13 7.7E-09 ZR95 8.4E-057.9E-11 1.3E-06NB95 7.0E-057.1E-11 1.2E-06 MO99 1.1E-01 3.2E-08 5.3E-04 TC99M 5.7E-02 3.1E-08 5.1E-04 RU103 6.3E-055.7E-11 9.4E-07 RU106 1.4E-051.4E-11 2.3E-07 RH103M 5.0E-055.7E-11 2.4E-07 RH106 1.1E-051.4E-11 2.3E-07 TE125M 4.0E-053.7E-11 6.1E-07 TE127M 3.9E-04 3.8E-10 6.2E-06 TE127 1.0E-03 3.8E-10 6.2E-06a.Includes DF from Boron Recovery System.
Notes:1.Mixed Bed Demineralizer with DF = 10 for all Radionuclides except Cs and Rb for which the DF = 202.Cation Removal Bed with a DF in the Chemic al and V olume control system = 10 for Cs and Rb and = 1 for all other isotopes.3.Boron Evaporator with a DF = 1000 for al l radionuclides except I, for which the DF
= 100.
Revision 52-09/29/2016 NAPS UFSAR 11.2-32 TE129M 1.9E-03 1.7E-09 2.0E-05 TE129 1.8E-03 1.1E-09 1.0E-05 TE131M 3.2E-03 3.2E-10 5.3E-06 TE131 1.2E-035.9E-11 9.7E-07 TE132 3.6E-02 1.2E-08 2.0E-04 BA137M 1.8E-02 1.1E-07 1.0E-03 BA140 3.0E-04 2.2E-10 3.6E-06 LA140 2.0E-04 2.3E-10 3.0E-06 CE141 9.7E-058.6E-11 1.4E-06 CE143 5.2E-05 6.1E-12 1.0E-07 CE144 4.6E-054.5E-11 2.4E-07 PR143 6.9E-055.6E-11 2.2E-07 PR144 3.7E-054.5E-11 7.4E-07 NP239 1.6E-03 3.9E-10 6.4E-06 BR83 5.5E-03 4.3E-12 7.1E-08 BR84 2.9E-03 1.1E-13 1.8E-07 BR85 3.3E-04 1.0E-16 1.6E-12 I130 2.6E-03 5.4E-10 8.9E-06 I131 3.7E-01 2.3E-06 3.8E-02 I132 1.1E-01 2.0E-08 3.3E-04 I133 4.9E-01 2.7E-07 4.4E-03 I134 5.3E-025.5E-11 2.0E-07 I135 2.3E-01 1.4E-08 2.3E-04 RB86 1.1E-04 4.5E-10 2.4E-06Table 11.2-9 (continued)
ACTIVITY FROM BORON RECOVERY - EXPECTED CASEDF Waste Disposal System for this Source = 1.00E+06 a Decay Time in Waste Disp Sys (hours) = 8.0E+01 Flow Rate (gal/yr) = 4.38E+06NuclideInitial Activity (µC/GM)Activity After Treatment
(µC/GM)Discharge Rate from W.D. System (Ci/yr)a.Includes DF from Boron Recovery System.
Notes:1.Mixed Bed Demineralizer with DF = 10 for all Radionuclides except Cs and Rb for which the DF = 202.Cation Removal Bed with a DF in the Chemical and Volume control system = 10 for Cs and Rb and = 1 for all other isotopes.3.Boron Evaporator with a DF = 1000 for all radionuclides except I, for which the DF = 100.
Revision 52-09/29/2016 NAPS UFSAR 11.2-33 RB88 2.2E-011.3E-11 2.1E-07 CS134 3.2E-02 1.6E-07 2.6E-03 CS136 1.6E-02 6.0E-08 9.9E-04 CS137 2.3E-02 1.1E-07 1.8E-03TOTAL 1.8E+00 3.2E-06 5.2E-02Table 11.2-9 (continued)
ACTIVITY FROM BORON RECOVERY - EXPECTED CASEDF Waste Disposal System for this Source = 1.00E+06 a Decay Time in Waste Disp Sys (hours) = 8.0E+01 Flow Rate (gal/yr) = 4.38E+06NuclideInitial Activity (µC/GM)Activity After Treatment
(µC/GM)Discharge Rate from W.D. System (Ci/yr)a.Includes DF from Boron Recovery System.
Notes:1.Mixed Bed Demineralizer with DF = 10 for all Radionuclides except Cs and Rb for which the DF = 202.Cation Removal Bed with a DF in the Chemical and Volume control system = 10 for Cs and Rb and = 1 for all other isotopes.3.Boron Evaporator with a DF = 1000 for all radionuclides except I, for which the DF = 100.
Revision 52-09/29/2016 NAPS UFSAR 11.2-34Table 11.2-10 ACTIVITY FROM PRIMARY COOLANT SYSTEM LEAKAGE (HLWDT) - EXPECTED CASEDF Waste Disposal System for this Source = 1.00E+06 a Decay Time in Waste Disp Sys (hours) = 1.67E+00 Flow Rate (gal/yr) = 1.48E+07NuclideInitial Activity
(µC/GM)Activity After Treatment (µC/GM)Discharge Rate from W.D. System (Ci/yr)
CR51 5.3E-04 5.3E-10 2.9E-05 MN54 8.8E-058.8E-11 4.9E-06 FE55 4.5E-04 4.5E-10 2.5E-05 FE59 2.9E-04 2.9E-10 1.6E-05 CO58 4.5E-03 4.5E-09 2.5E-04 CO60 5.7E-04 5.7E-10 3.2E-05 SR89 1.0E-04 1.0E-10 5.6E-06 SR90 2.9E-06 2.9E-12 1.6E-07 SR91 1.6E-04 1.4E-10 7.8E-06 Y90 3.3E-07 3.1E-13 1.7E-08 Y91M 8.2E-058.9E-11 4.9E-06 Y91 1.8E-04 1.8E-10 1.0E-05 Y93 8.6E-06 7.5E-12 4.2E-07 ZR95 1.7E-051.7E-11 7.4E-07 NB95 1.4E-051.4E-11 7.8E-07 MO99 2.2E-02 2.2E-08 1.2E-03 TC99M 1.1E-02 1.3E-08 7.2E-04 RU103 1.3E-051.3E-11 7.2E-07 RU106 2.9E-06 2.9E-12 1.6E-07 RH103M 1.0E-051.2E-11 6.9E-07 RH106 2.3E-06 2.9E-12 1.6E-07 TE125M 8.2E-06 8.2E-12 4.6E-07 TE127M 8.0E-058.0E-11 4.4E-06 TE127 2.1E-04 1.9E-10 1.1E-05 TE129M 3.9E-04 3.9E-10 2.2E-05 TE129 3.7E-04 2.9E-10 1.6E-05 TE131M 6.6E-04 6.3E-10 3.5E-05a.Includes Containment Building Sumps, Safeguards Sumps, Auxiliary Building Sumps, Fuel Building Sumps and Laboratory Drains.
Revision 52-09/29/2016 NAPS UFSAR 11.2-35 TE131 2.5E-04 1.3E-10 7.2E-06 TE132 7.4E-03 7.3E-09 4.1E-04 BA137M 3.7E-03 1.9E-07 1.1E-02 BA140 6.2E-056.1E-11 3.4E-06 LA140 4.1E-054.2E-11 2.3E-06 CE141 2.0E-052.0E-11 1.1E-06 CE143 1.1E-051.0E-11 5.6E-07 CE144 9.4E-06 9.4E-12 5.2E-07 PR143 1.4E-051.4E-11 7.8E-07 PR144 7.6E-06 9.3E-12 5.2E-07 NP239 3.3E-04 3.2E-10 1.8E-05 BR83 1.1E-03 6.5E-10 3.6E-05 BR84 5.9E-047.5E-11 4.2E-06 BR85 6.8E-05 8.3E-14 4.6E-09 I130 5.3E-04 4.8E-08 2.7E-03 I131 7.6E-02 7.5E-06 4.2E-01 I132 2.3E-02 1.4E-06 7.8E-02 I133 1.0E-01 9.4E-06 5.2E-01 I134 1.1E-02 2.8E-07 1.6E-02 I135 4.7E-02 3.8E-06 2.1E-01 RB86 2.3E-05 1.1E-09 6.1E-05 RB88 4.5E-02 1.1E-07 5.6E-03 CS134 6.6E-03 3.3E-07 1.8E-02 CS136 3.3E-03 1.6E-07 8.9E-03 CS137 4.7E-03 2.4E-07 1.3E-02TOTAL 3.7E-01 2.4E-05 1.3E+00Table 11.2-10 (continued)ACTIVITY FROM PRIMARY COOLANT SYSTEMLEAKAGE (HLWDT) - EXPECTED CASEDF Waste Disposal System for this Source = 1.00E+06 a Decay Time in Waste Disp Sys (hours) = 1.67E+00 Flow Rate (gal/yr) = 1.48E+07NuclideInitial Activity
(µC/GM)Activity After Treatment (µC/GM)Discharge Rate from W.D. System (Ci/yr)a.Includes Containment Building Sumps, Safeguards Sumps, Auxiliary Building Sumps, Fuel Building Sumps and Laboratory Drains.
Revision 52-09/29/2016 NAPS UFSAR 11.2-36Table 11.2-11 ACTIVITY FROM DECONTAMINATION BUILDING SUMPS - EXPECTED CASEDF Waste Disposal System for this Source = 1.00E+06 Decay Time in Waste Disp Sys (hours) = 2.92 Flow Rate (gal/yr) = 3.62E+05NuclideInitial Activity
(µC/GM)Activity After Treatment (µC/GM)Discharge Rate from W.D. System (Ci/yr)
CR51 2.6E-052.5E-11 3.4E-08 MN54 4.3E-06 4.3E-12 5.8E-09 FE55 2.2E-052.2E-11 3.0E-08 FE59 1.4E-051.4E-11 1.9E-08 CO58 2.2E-04 2.2E-10 3.0E-07 CO60 2.8E-052.8E-11 3.8E-08 SR89 4.9E-06 4.8E-12 6.6E-09 SR90 1.4E-07 1.4E-13 1.9E-10 SR91 7.7E-06 1.7E-12 2.3E-09 Y90 1.6E-08 4.1E-145.6E-11 Y91M 4.0E-06 1.1E-12 1.5E-09 Y91 8.9E-06 8.8E-12 1.2E-08 Y93 4.2E-07 9.5E-14 1.3E-10 ZR95 8.4E-07 8.3E-13 1.1E-09 NB95 7.0E-07 7.0E-13 9.5E-10 MO99 1.1E-03 8.1E-10 1.1E-06 TC99M 5.7E-04 7.2E-10 9.8E-07 RU103 6.3E-07 6.2E-13 8.4E-10 RU106 1.4E-07 1.4E-13 1.9E-10 RH103M 5.0E-07 6.1E-13 8.3E-10 RH106 1.1E-07 1.4E-13 1.9E-10 TE125M 4.0E-07 3.9E-13 5.3E-10 TE127M 3.9E-06 3.9E-12 5.3E-09 TE127 1.0E-05 5.1E-12 6.9E-09 TE129M 1.9E-051.9E-11 2.6E-08 TE129 1.8E-051.2E-11 1.6E-08 TE131M 3.2E-051.7E-11 2.3E-08 TE131 1.2E-05 3.1E-12 4.2E-09 TE132 3.6E-04 2.8E-10 3.8E-07 BA137M 1.8E-04 9.8E-09 1.3E-05 BA140 3.0E-06 2.8E-12 3.8E-07 Revision 52-09/29/2016 NAPS UFSAR 11.2-37 LA140 2.0E-06 2.3E-12 3.1E-07 CE141 9.7E-07 9.4E-13 1.3E-07 CE143 5.2E-07 2.9E-13 3.9E-10 CE144 4.6E-07 4.6E-13 6.2E-10 PR143 6.9E-07 6.7E-13 9.1E-10 PR144 3.9E-07 4.6E-13 6.2E-10 NP239 1.6E-051.1E-11 1.5E-08 BR83 5.5E-05 2.2E-12 3.0E-09 BR84 2.9E-05 9.6E-14 1.2E-10 BR85 3.3E-06 9.2E-17 1.2E-13 I130 2.6E-05 7.1E-10 9.6E-07 I131 3.7E-03 3.3E-07 4.6E-04 I132 1.1E-03 2.2E-08 3.0E-05 I133 4.9E-03 2.1E-07 2.9E-04 I134 5.3E-04 4.5E-10 6.1E-07 I135 2.3E-03 3.2E-08 4.3E-05 RB86 1.1E-065.2E-11 7.1E-08 RB88 2.2E-03 1.2E-10 1.6E-07 CS134 3.2E-04 1.6E-08 2.2E-05 CS136 1.6E-04 7.5E-09 1.0E-05 CS137 2.3E-04 1.1E-08 1.5E-05TOTAL 1.8E-02 6.4E-07 8.7E-04Table 11.2-11 (continued)
ACTIVITY FROM DECONTAMINATION BUILDING SUMPS - EXPECTED CASEDF Waste Disposal System for this Source = 1.00E+06 Decay Time in Waste Disp Sys (hours) = 2.92 Flow Rate (gal/yr) = 3.62E+05NuclideInitial Activity
(µC/GM)Activity After Treatment (µC/GM)Discharge Rate from W.D. System (Ci/yr)
Revision 52-09/29/2016 NAPS UFSAR 11.2-38Table 11.2-12 ACTIVITY IN WASTE DISPOSAL SYSTEM WITH STEAM GENERATOR LEAKAGE - DESIGN CASE Calculated Maximum Allowable Di schar ge Rate (Ci/yr) = 2.5E+03 Calculated Total Discharg e Flow Rate (gpm) = 90.8 Nuclide Initial Activity
(µC/gm)Actual Disch.
Rate (Ci/yr)Allowable Discharge Rate Mixture (Ci/yr) Single (Ci/yr)H3 6.6E-03 1.2E+03 1.2E+03 6.6E+05 CR51 9.5E-08 1.7E-02 6.8E-02 6.8E+06 MN54 7.8E-08 1.4E-02 5.6E-02 1.4E+05CO58 2.5E-06 4.4E-01 1.8E+00 2.2E+05FE59 1.0E-07 1.8E-02 7.2E-02 1.4E+05CO60 7.8E-08 1.4E-02 5.6E-02 2.8E+04 SR89 3.9E-07 6.9E-02 2.8E-01 8.0E+03 SR90 1.5E-08 2.6E-03 1.0E-02 2.4E+02 SR91 8.9E-08 1.6E-02 6.4E-02 1.9E+05 Y90 1.7E-08 3.0E-03 1.2E-02 1.9E+04 Y91 4.7E-07 8.5E-02 3.4E-01 7.6E+04 ZR95 7.3E-08 1.3E-02 5.2E-02 1.5E+04 NB95 7.3E-08 1.3E-02 5.2E-02 2.4E+05 TC99M 4.1E-04 7.4E+01 3.0E+02 1.1E+07 MO99 4.7E-04 8.4E+01 3.4E+02 1.4E+05 RU1037.8E-11 1.4E-05 5.6E-05 RU106 1.3E-09 2.4E-04 9.6E-04 RH103M5.1E-11 9.2E-06 3.7E-05 RH106 1.3E-09 2.4E-04 9.6E-04 I131 2.6E-04 4.7E+01 1.9E+02 1.1E+03 I132 4.1E-05 7.3E+00 2.9E+01 2.6E+04 I133 3.0E-04 5.4E+01 2.2E+02 3.5E+05 I134 5.6E-06 1.0E+00 4.0E+00 6.0E+04 I135 1.7E-05 3.1E+00 1.2E+01 1.3E+04 TE122 2.3E-05 4.2E+00 1.7E+01 7.1E+04 CS134 2.8E-05 5.1E+00 2.0E+01 1.0E+04 CS136 1.2E-05 2.1E+00 8.4E+00 2.0E+05 CS137 1.4E-04 2.5E+01 1.0E+02 1.7E+04 BA140 4.2E-07 7.6E-02 3.0E-01 6.5E+04 LA140 2.1E-07 3.8E-02 1.5E-01 6.3E+04 Revision 52-09/29/2016 NAPS UFSAR 11.2-39 CE144 3.6E-08 6.5E-03 2.6E-02 1.4E+04Total 8.4E-03 1.5E+03 2.5E+03Total (Non-Tritium) 1.9E-03 3.3E+02 1.3E+03Ratio of Allowable To Actual Discha r ge Rate Of Mixture, Excluding H3
= 3.99E+00Table 11.2-12 (continued)
ACTIVITY IN WASTE DISPOSAL SYSTEMWITH STEAM GENERATOR LEAKAGE - DESIGN CASE Calculated Maximum Allowable Discharge Rate (Ci/yr) = 2.5E+03 Calculated Total Discharg e Flow Rate (gpm) = 90.8 Nuclide Initial Activity
(µC/gm)Actual Disch.Rate (Ci/yr)Allowable Discharge Rate Mixture(Ci/yr) Single (Ci/yr)
Revision 52-09/29/2016 NAPS UFSAR 11.2-40Table 11.2-13 ACTIVITY IN WASTE DISPOSAL SYSTEM WITH S TEAM GENERATOR LEAKAGE - EXPECTED CASECalculated Total Discharg e Flow Rate (gpm) = 78.7 NuclideInitial Activity
(µC/gm)Actual Disch. Rate (Ci/yr)CR51 5.3E-12 4.5E-03 MN54 1.3E-12 1.1E-03 FE55 4.6E-12 4.0E-03 FE59 3.5E-12 3.0E-03 CO584.7E-11 4.0E-02 CO60 6.4E-12 5.5E-03 SR89 1.2E-12 1.0E-03 SR90 2.4E-14 2.1E-05 SR91 7.6E-13 6.6E-04 Y90 4.3E-15 3.7E-06 Y91M 2.4E-13 2.1E-04 Y91 2.0E-13 1.7E-04 Y93 3.9E-14 3.4E-05 ZR95 4.1E-13 3.5E-04NB95 4.8E-13 4.2E-04 MO99 2.1E-10 1.8E-01 TC99M 1.1E-10 9.0E-02 RU103 1.3E-13 1.1E-04 RU106 3.2E-13 2.7E-04 RH103M 6.4E-14 5.5E-05 RH106 3.0E-13 2.6E-04 TE125M 5.7E-14 4.9E-05 TE127M 5.7E-13 4.9E-04 TE127 1.2E-12 1.0E-03 TE129M 3.5E-12 3.0E-03 TE129 1.5E-12 1.3E-03 TE131M 4.8E-12 4.1E-03 TE131 4.6E-13 4.0E-04 TE1325.3E-11 4.5E-02 BA137M3.7E-11 3.2E-02 BA140 5.7E-13 4.9E-04 Revision 52-09/29/2016 NAPS UFSAR 11.2-41 LA140 3.5E-13 3.0E-04 CE141 2.4E-13 2.1E-04 CE143 4.8E-14 4.1E-05 CE144 7.2E-13 6.2E-04 PR143 1.1E-13 9.8E-05 PR144 6.0E-13 5.1E-04 NP239 3.1E-12 2.6E-03 BR83 2.6E-12 2.3E-03 BR84 3.9E-13 3.4E-04 BR85 4.3E-15 3.7E-06 I130 6.5E-12 5.6E-03 I131 1.3E-09 1.1E+00 I132 1.7E-10 1.4E-01 I133 1.4E-09 1.2E+00 I1342.9E-11 2.5E-02 I135 4.7E-10 4.0E-01 RB86 3.0E-13 2.6E-04 RB882.3E-11 2.0E-02 CS1349.2E-11 7.9E-02 CS1364.5E-11 3.8E-02 CS1376.9E-11 5.9E-02 H3 2.8E-06 2.4E+03Total 2.8E-06 2.4E+03Total (Non-Tritium) 4.0E-09 3.5E+00Table 11.2-13 (continued)
ACTIVITY IN WASTE DISPOSAL SYSTEMWITH STEAM GENERATOR LEAKAGE - EXPECTED CASECalculated Total Discharg e Flow Rate (gpm) = 78.7 NuclideInitial Activity
(µC/gm)Actual Disch. Rate (Ci/yr)
Revision 52-09/29/2016 NAPS UFSAR 11.2-42Table 11.2-14 ACTIVITY IN DISCHARGE CANAL - DESIGN CASENuclide MPC (µC/cc)Actual Activity (µC/cc)Ratio (µC/cc)/MPC Allowable Activity (µC/cc)Ratio (µC/cc)/MPC H3 3.0E-03 5.5E-06 1.8E-03 5.5E-06 1.8E-03 CR51 2.0E-032.3E-11 1.1E-089.1E-11 4.4E-08 MN54 1.0E-043.9E-11 3.9E-07 1.6E-10 1.6E-06 CO58 9.0E-05 7.4E-10 8.2E-06 2.9E-07 3.3E-05 FE59 5.0E-052.6E-11 5.3E-07 1.1E-10 2.1E-06 CO60 3.0E-056.0E-11 2.0E-06 2.4E-10 8.0E-06 SR89 3.0E-06 1.1E-10 3.5E-05 4.2E-10 1.4E-04 SR90 3.0E-071.2E-11 4.1E-054.7E-11 1.6E-04 SR91 5.0E-051.9E-11 3.7E-077.5E-11 1.5E-06 Y90 2.0E-051.3E-11 6.3E-075.0E-11 2.5E-06 Y91 3.0E-05 1.3E-10 4.5E-06 5.4E-10 1.8E-05 ZR95 6.0E-052.1E-11 3.5E-078.4E-11 1.4E-06 NB95 1.0E-042.2E-11 2.2E-078.8E-11 8.8E-07 TC99M 3.0E-03 8.5E-08 2.8E-05 3.4E-07 1.1E-04 MO99 4.0E-05 9.9E-08 2.5E-03 4.0E-07 1.0E-02 I131 3.0E-07 5.6E-08 1.8E-01 2.2E-07 7.2E-01 I132 3.0E-06 8.5E-09 1.1E-03 3.4E-08 4.4E-03 I133 1.0E-06 6.2E-08 6.2E-06 2.5E-07 2.4E-01 I134 2.0E-05 1.2E-09 5.9E-05 4.7E-09 2.4E-04 I135 4.0E-06 3.6E-09 9.0E-04 1.4E-08 3.6E-03 TE132 2.0E-05 4.8E-09 2.4E-04 1.9E-08 9.6E-04 CS134 9.0E-06 1.8E-08 2.0E-03 7.3E-08 8.0E-03 CS136 6.0E-05 2.6E-09 4.3E-05 1.0E-08 1.7E-04 CS137 2.0E-05 1.2E-07 5.9E-03 4.7E-07 2.4E-02 BA140 2.0E-059.2E-11 4.6E-06 3.7E-10 1.8E-05 LA140 2.0E-054.8E-11 2.4E-06 1.9E-10 9.6E-06 CE144 1.0E-051.8E-11 1.8E-067.2E-11 7.2E-06Total 6.4E-06 2.6E-01 7.3E-06 1.0E-00Total (Non-Tritium) 5.7E-07 2.5E-01 1.8E-06 9.9E-01 Revision 52-09/29/2016 NAPS UFSAR 11.2-43Table 11.2-15ACTIVITY IN WASTE HEAT TREATM ENT FACILITIES - DESIGN CASENuclide MPC (µC/cc)Actual Activity (µC/cc)Ratio (µC/cc)/MPC Allowable Ac tivity (µC/cc)Ratio (µC/cc)/MPC H3 3.0E-03 5.7E-06 1.8E-03 5.3E-06 1.8E-03 CR51 2.0E-031.2E-11 6.2E-094.8E-11 2.5E-08 MN54 1.0E-043.5E-11 3.5E-07 1.4E-10 1.4E-06 CO58 9.0E-05 5.5E-10 6.1E-06 2.2E-09 2.4E-05 FE59 5.0E-051.7E-11 3.5E-076.8E-11 1.4E-06 CO60 3.0E-055.7E-11 1.9E-06 2.3E-10 7.6E-06 SR89 3.0E-067.1E-11 2.4E-05 2.8E-10 9.6E-05 SR90 3.0E-071.2E-11 3.9E-054.8E-11 1.6E-04 SR91 5.0E-05 3.3E-13 6.5E-09 1.3E-12 2.6E-08 Y90 2.0E-051.1E-11 5.5E-074.4E-11 2.2E-06 Y91 3.0E-059.5E-11 3.2E-06 3.8E-10 1.8E-05 ZR95 6.0E-051.5E-11 2.5E-076.0E-11 1.0E-06 NB95 1.0E-041.7E-11 1.7E-076.0E-11 6.8E-07 TC99M 3.0E-03 1.0E-08 3.5E-06 4.0E-08 1.4E-05 MO99 4.0E-05 1.1E-08 2.9E-04 4.4E-08 1.1E-03 I131 3.0E-07 1.5E-08 5.0E-02 6.0E-08 2.0E-01 I132 3.0E-06 6.4E-10 8.0E-05 2.6E-09 3.2E-04 I133 1.0E-06 2.3E-09 2.3E-03 9.2E-09 9.2E-03 I134 2.0E-05 1.9E-12 9.9E-08 7.6E-12 3.9E-07 I135 4.0E-064.4E-11 1.1E-05 1.8E-10 4.4E-05 TE132 2.0E-05 6.1E-10 3.0E-05 2.4E-09 1.2E-04 CS134 9.0E-06 1.7E-08 1.9E-03 6.8E-08 7.6E-03 CS136 6.0E-05 9.4E-10 1.6E-05 3.8E-09 6.4E-05 CS137 2.0E-05 1.1E-07 5.7E-03 4.4E-07 2.3E-02 BA140 2.0E-053.3E-11 1.7E-06 1.3E-10 6.8E-06 LA140 2.0E-053.4E-11 1.7E-06 1.4E-10 6.8E-06 CE144 1.0E-051.6E-11 1.2E-066.4E-11 6.4E-06Total 5.9E-06 6.2E-02 6.4E-06 2.4E-01Total (Non-Tritium) 2.8E-07 6.0E-02 1.1E-06 2.4E-01 Revision 52-09/29/2016 NAPS UFSAR 11.2-44Table 11.2-16 ACTIVITY IN NORTH ANNA RESERVOIR - DESIGN CASE NuclideMPC (µC/cc)Actual Activity (µC/cc)Ratio (µC/cc)/MPCAllowable Activity (µC/cc)Ratio (µC/cc)/MPC H3 3.0E-03 4.1E-06 1.4E-03 4.1E-06 1.4E-03 CR51 2.0E-03 2.9E-12 1.4E-091.2E-11 5.6E-09 MN54 1.0E-042.3E-11 2.3E-079.2E-11 9.2E-07 CO58 9.0E-05 2.2E-10 2.5E-06 8.8E-10 1.0E-05 FE59 5.0E-05 5.5E-12 1.1E-072.2E-11 4.4E-07 CO60 3.0E-054.4E-11 1.5E-06 1.8E-10 6.0E-06 SR89 3.0E-062.4E-11 8.0E-069.6E-11 3.2E-05 SR90 3.0E-07 9.3E-12 3.1E-053.7E-11 1.2E-04 SR91 5.0E-05 1.5E-153.0E-11 6.0E-15 1.2E-10 Y90 2.0E-05 9.0E-12 4.5E-073.6E-11 1.8E-06 Y91 3.0E-053.5E-11 1.2E-06 1.4E-10 4.8E-06 ZR95 6.0E-05 5.9E-12 9.9E-082.4E-11 4.0E-07 NB95 1.0E-04 7.1E-12 7.1E-082.0E-11 2.8E-07 TC99M 3.0E-03 3.0E-10 9.9E-08 1.2E-09 4.0E-07 MO99 4.0E-05 3.4E-10 8.4E-06 1.4E-09 3.4E-05 I131 3.0E-07 1.3E-09 4.2E-03 5.2E-09 1.7E-02 I132 8.0E-062.2E-11 2.8E-068.8E-11 1.1E-05 I133 1.0E-062.4E-11 2.4E-059.6E-11 9.6E-05 I134 2.0E-05 8.3E-164.1E-11 3.3E-15 1.6E-10 I135 4.0E-05 1.4E-13 3.5E-08 5.6E-13 1.4E-07 TE132 2.0E-052.2E-11 1.1E-068.8E-11 4.4E-06 CS134 9.0E-06 1.2E-08 1.4E-03 4.8E-08 5.6E-03 CS136 6.0E-05 1.2E-10 2.0E-06 4.8E-10 8.0E-06 CS137 2.0E-05 8.9E-08 4.5E-03 3.6E-07 1.8E-02 BA140 2.0E-05 4.2E-12 2.1E-071.7E-11 8.4E-07 LA140 2.0E-05 4.2E-12 2.1E-071.7E-11 8.4E-07 CE144 1.0E-051.0E-11 1.0E-064.0E-11 4.0E-06Total 4.2E-06 1.1E-02 4.9E-06 4.1E-02Total (Non-Tritium) 1.0E-07 1.0E-02 7.6E-07 4.0E-02 Revision 52-09/29/2016 NAPS UFSAR 11.2-45Table 11.2-17 ACTIVITY IN DISCHARGE CANAL - EXPECTED CASE Nuclide Activity (µC/gm)CR51 5.9E-12 MN54 3.1E-12 FE551.6E-11 FE59 4.4E-12 CO586.8E-11 CO602.3E-11 SR89 1.5E-12 SR90 1.0E-13 SR91 7.7E-13 Y90 7.9E-14 Y91M 2.5E-13 Y91 2.9E-13 Y93 4.0E-14 ZR95 5.7E-13NB95 6.8E-13 MO99 2.1E-10 TC99M 1.1E-10 RU103 1.6E-13 RU106 8.1E-13 RH103M 8.8E-14 RH106 7.9E-13 TE125M 7.9E-14 TE127M 9.7E-13 TE127 1.6E-12 TE129M 4.1E-12 TE129 1.9E-12 TE-131M 4.8E-12 TE-131 4.8E-13 TE-1325.2E-11 BA137M 2.4E-10 BA140 6.1E-13 LA140 3.8E-13 CE141 2.9E-13 CE143 4.8E-14 Revision 52-09/29/2016 NAPS UFSAR 11.2-46 CE144 1.7E-12 PR143 1.2E-13 PR144 1.6E-12 NP239 3.0E-12 BR83 2.7E-12 BR84 4.0E-13 BR85 4.4E-15 I130 6.6E-12 I131 1.3E-09 I132 1.6E-10 I133 1.4E-09 I1342.9E-11 I135 4.8E-10 RB86 3.3E-13 RB882.3E-11 CS134 2.9E-10 CS1364.6E-11 CS137 2.8E-10 H3 5.5E-06Total 5.5E-06Total (Non-Tritium) 4.8E-09Table 11.2-17 (continued)
ACTIVITY IN DISCHARGE CANAL - EXPECTED CASENuclideActivity (µC/gm)
Revision 52-09/29/2016 NAPS UFSAR 11.2-47Table 11.2-18 ACTIVITY IN WASTE HEAT TREATM ENT FACILITY - EXPECTED CASE NuclideActivity (µC/gm)CR51 3.2E-12 MN54 2.8E-12 FE551.5E-11 FE59 2.9E-12 CO585.1E-11 CO602.2E-11 SR89 1.0E-12 SR90 9.7E-14 SR91 1.4E-14 Y90 8.7E-14 Y91M 8.2E-15 Y91 1.9E-13 Y93 7.6E-16 ZR95 4.2E-13NB95 5.0E-13 MO992.3E-11 TC99M2.1E-11 RU103 9.8E-14 RU106 7.4E-13 RH103M 8.9E-14 RH106 7.4E-13 TE125M 5.6E-14 TE127M 7.8E-13 TE127 7.9E-13 TE129M 2.4E-12 TE129 1.6E-12 TE131M 2.5E-13 TE131 5.6E-14 TE132 6.6E-12 BA137M 2.6E-10 BA140 2.2E-13 LA140 2.3E-13 CE141 1.7E-13 CE143 2.8E-15 Revision 52-09/29/2016 NAPS UFSAR 11.2-48 CE144 1.6E-12 PR143 4.7E-14 PR144 1.6E-12 NP239 2.9E-13 BR83 1.2E-14 BR84 4.0E-16 BR85 4.0E-19 I130 1.5E-13 I131 3.4E-10 I132 7.2E-12 I1335.2E-11 I134 4.8E-14 I135 5.8E-12 RB86 1.5E-13 RB88 1.3E-14 CS134 2.7E-10 CS1361.7E-11 CS137 2.7E-10 H3 5.3E-06Total 5.3E-06Total (Non-Tritium) 1.4E-09Table 11.2-18 (continued)
ACTIVITY IN WASTE HEAT TREATM ENT FACILITY - EXPECTED CASENuclideActivity (µC/gm)
Revision 52-09/29/2016 NAPS UFSAR 11.2-49Table 11.2-19 ACTIVITY IN NORTH ANNA RESERVOIR - EXPECTED CASE NuclideActivity (µC/gm)CR51 7.4E-13 MN54 1.8E-12 FE551.1E-11 FE59 9.1E-13 CO582.1E-11 CO601.7E-11 SR89 3.5E-13 SR90 7.6E-14 SR91 6.3E-17 Y90 7.4E-14 Y91M 3.6E-17 Y91 7.0E-14 Y93 3.7E-18 ZR95 1.6E-13NB95 2.1E-13 MO99 7.1E-13 TC99M 6.3E-13 RU103 2.9E-14 RU106 4.9E-13 RH103M 2.6E-14 RH106 4.9E-13 TE125M 2.0E-14 TE127M 3.8E-13 TE127 3.8E-13 TE129M 6.4E-13 TE129 4.1E-13 TE131M 3.7E-15 TE131 8.0E-16 TE132 2.4E-13 BA137M 2.0E-10 BA140 2.8E-14 LA140 2.8E-14 CE141 4.3E-14 CE143 4.4E-17 Revision 52-09/29/2016 NAPS UFSAR 11.2-50 CE144 9.9E-13 PR143 6.0E-15 NP239 7.7E-15 BR83 1.4E-17 BR84 1.0E-19 BR85 9.2E-24 I130 9.1E-16 I1312.9E-11 I132 2.4E-13 I133 5.3E-13 I134 2.0E-17 I135 1.9E-14 RB86 2.5E-14 RB88 1.8E-18 CS134 1.9E-10 CS136 2.2E-12 CS137 2.2E-10 H3 4.1E-06Total 4.1E-06Total (Non-Tritium) 7.0E-10Table 11.2-19 (continued)
ACTIVITY IN NORTH ANNA RESERVOIR - EXPECTED CASENuclideActivity (µC/gm)
Revision 52-09/29/2016 NAPS UFSAR 11.2-51Table 11.2-20 FLOW CONDITIONS IN NORTH ANNA RESERVOIR AND WASTE HEAT TREATMENT FACILITIESParameterValueVolume of reservoir 1.06E+10 ft 3 Environmental flow ra te into reservoir 270.00 cfs Evaporation rate from reservoir 59.00 cfs Overflow rate from reservoir 220.00 cfsRecirculation flow, reservoir to Waste Heat Treatment Facility 962 cfsVolume of Waste Heat Treatment Facility 2.66E+09 ft 3Environmental flow rate into Waste Heat Treatment Facility 30.00Evaporation rate from Waste Heat Treatment Facility 21.00 cfsRecirculation flow, Waste Heat Tr eatment Facility to reservoir 971 cfsTable 11.2-21 MAXIMUM INDIVIDUAL WHOL E-BODY AND BODY-ORGAN EXPOSURE DUE TO LIQUID RADWASTE IN THE NORTH ANNA RESERVOIR Annual Radiation Exposure (mrem/yr)
Exposure Source Whole Body LungsLiverKidneyBoneThyroid LowerLargeIntestineWater ingestion, 1.2 liters/day0.200.190.210.200.0130.210.19Fish ingestion, 50 g/day1.40.221.90.641.10.0220.046Swimming, 200 hr/yr0.00020.00020.00020.00020.00020.00020.0002 Boating, 500 hr/yr0.00020.00020.00020.00020.00020.00020.0002 Sunbathing, 300 hr/yr0.0460.0460.0460.0460.0460.0460.046 Totals1.6460.4562.1560.8861.1590.2780.282 Revision 52-09/29/2016 NAPS UFSAR 11.2-52Table 11.2-22MAXIMUM INDIVIDUAL WHOLE-B ODY AND BODY-ORGAN EXPOSURE DUE TO LIQUID RADWASTE IN THE WASTE HEAT FACILITY Annual Radiation Exposure (mrem/yr)
Exposure Source Whole Body Lungs Liver Kidney Bone Thyroid Lower Lar geIntestineWater ingestion, 1.2 liters/day 0.27 0.25 0.27 0.25 0.018 0.54 0.24 Fish ingestion, 50 g/day 1.9 0.29 2.6 0.86 1.4 0.20 0.070 Swimming, 200 hr/yr 0.0003 0.0003 0.0003 0.0003 0.0003 0.0003 0.0003 Boating, 500 hr/yr 0.0004 0.0004 0.0004 0.0004 0.0004 0.0004 0.0004 Sunbathing, 300 hr/yr 0.061 0.061 0.061 0.061 0.061 0.061 0.061Totals 2.232 0.601 2.932 1.172 1.480 0.802 0.372Table 11.2-23 WHOLE-BODY POPULATION EXPOSURE DUE TO LIQUID RADWASTE IN THE NORTH ANNA COOLING WATER STORAGE SYSTEM Exposure SourceEstimated Exposure Rate(mrem/yr)in the Year 2000 Ingestion of water take n from the reservoir 3.0 Ingestion of fish taken from th e cooling-water storage system4.15 Swimming in the reservoir 0.002 Boating on the reservoir 0.002 Sunbathing along the reservoir 0.483Totals 7.637 Revision 52-09/29/2016 NAPS UFSAR 11.2-53Figure 11.2-1LIQUID WASTE DISPOSAL SY STEM-DESIGN C ONDITIONS aa.Based on original plant configuration and liquid waste processing assumptions.b.Abandoned in place.
b b Revision 52-09/29/2016 NAPS UFSAR 11.2-54Figure 11.2-2LIQUID WASTE DISPOSAL SYSTEM-EXPECTED CONDITIONS aa.Based on original plant configuration and liquid waste processing assumptions.b.Abandoned in place b b Revision 52-09/29/2016 NAPS UFSAR 11.2-55Figure 11.2-3FLOW CHART-ESTIMATED QUANTITIES LIQUID WASTE DISPOSAL-DESIGN CASE aa.Based on original plant configuration and liquid waste processing assumptions, except where noted.b.Systems added to upgrade blowdown capacity.
b Revision 52-09/29/2016 NAPS UFSAR 11.2-56Figure 11.2-4FLOW CHART-ESTIMATED QUANTITIES LIQUID WASTE DISPOSAL-EXPECTED CASE aa.Based on original plant configuration and liquid waste processing assumptions, except where noted.b.Systems added to upgrade blowdown capacity.
b Revision 52-09/29/2016 NAPS UFSAR 11.3-111.3 GASEOUS WASTE DISPOSAL SYSTEM11.3.1 Design Objectives The gaseous waste disposal system is designed to maintain ef fl uent radioactivity levels as low as practicable and below the limits of applic able regulations. The sy stem is designed to satisfy the applicable sections of the general criteria of Section 3.1 , to conform with original Atomic Energy Commission (AEC) and present NR C general design criteria, and to meet the intent of 10 CFR 20, 10 CFR 50, and 10 CFR 100, so as not to endang er the health of station operating personnel or the general public.The gaseous waste disposal system is common to both units and is sized to treat the radioactive gases released during simultaneous operation of both units.
Fission product gases and uncondensed radioactive vapors are he ld for decay , filtered, and dilu ted with ventil ation air until they may be safely released through one of the two vent stacks on top of the Unit 1 containment.The gaseous waste disposal syst em is designed to provide ade quate storage for radioactive decay time of the waste gases and, in addition, provide for holdup of these gases when adverse meteorological conditi ons make it desirable to discontinue release of waste gas to the environment.Section 11.3.5 presents the expected gaseous activ ity release, by nuclide, from North Anna Units 1 and 2 for a core utilizing a 15 x 15 fuel assembly array. (T his is greater than a 17 x 17 as discussed in Section 11.1.1.2.) Virginia Power impl emented the revised 10 CFR 20 rule on January 1, 1994. The calculational metho dology for the design and expect ed gase ous activity releases, which are based on the criteria of the old 10 CFR 20, are valid design analyses and does not need to be redone according to the criter ia of the revised 10 CFR 20. (
Reference:
Seventh Set of NRC Q/A
- 456.) The exposures received by the general publ ic as a result of these releases are presented in Section 11.3.8.11.3.2 System Description Figure 11.3-1 and Reference Drawings 1 and 2 depict the gaseous wa ste disposal system. The system is designed to receive, decay, process, dilute, and discharge potentially radioactive gases, fission product gases, a nd uncondensed vapors from the vent and drain system, boron recovery system, primary coolan t leakages, and the reactor plan
- t. The design minimizes possible personnel exposure and ensures that radioactiv e releases to the environment are ALARA.Area and effluent monitoring ensures that an y accidental radioactivity release would be detected within a reasona ble period of time.
The largest accidental radioactivity release from the gaseous waste disposal system would be caused by the rupturing of the waste gas decay tanks. An analysis of this accident is reported in Section 15.3.5. Periodic samples of the gas in the waste decay tanks are analyzed by he alth physics personne l to determine nuc lide composition and Revision 52-09/29/2016 NAPS UFSAR 11.3-2 ensure that the activity inventory in these tanks does not exceed pr escribed levels. Releases from the relief valves will be detected by instrumentation in Vent Stack B.The system is a closed loop consisting of two waste gas co mpressors, two waste gas decay tanks, and connecting piping to coll ect and filter vapors from tanks containing radioactive liquids as shown in Figure 11.3-1.Table 11.3-1 gives a summary of design parameters for gaseous waste disposal system equipment. The gaseous waste inputs to the gase ous waste system are identified by source in Section 11.1. The activity data for all ga seous waste dischar ged to the atmosphere are presented in Section 11.3.5.The process vent subsystem d ilutes and discharges the effluents of the gaseous waste disposal system to the atmo sphere. The ventilation vent subsystem, described in Section 9.4 , regulates the discharge of air fro m potentially contaminated areas, and from the st eam reliefs of the boron evaporators, waste dispos al evaporator (the waste dispos al evaporator is not used: the ion exchange filtration system (DURATEK) is used instead), gas strippers and waste gas decay tanks to the atmosphere. Discharges from both subsystems are monitored by particulate and gas monitors described in the process radiation monitoring system, Section 11.4.Gaseous waste enters the proces s vent subsystem of the gaseous waste disposal system from the waste gas decay tanks, the vent and drain system, the containment purge system and the containment vacuum system, as shown on Figure 11.3-1 and Reference Drawings 1 and 2.Two double-walled waste gas d ecay tanks are located in under ground concrete vaults for missile protection. The inner tank is fabricated of stainless st eel in accordance with Section III C, and the outer tank of carbon st eel in accordance with Section VIII, Division I, of the ASME Boiler and Pressure Vessel Code. Connections are provided for sampling the tank contents and the annular space between tanks.Overpressure relief pr otection is provided at the waste gas deca y tanks in accordance with Section III C of the ASME Code. The protective devices consist of rupture disc assemblies followed by bellows-sealed pressure relief valves. The use of bellows seals and rupture discs precludes leakage of the waste ga s to the e nvironment during normal operation of the gaseous waste disposal system. The piping downstream of the protective devices relieves to vent stack B upstream of all radiati on monitoring equipment.After sufficient decay time and sampling, the gas is released into the pr ocess vent system at the suction of the process vent blowers. These blowers also take suction on the containment vacuum compressor dischar ge and on the vents of liquid wa ste tanks, as well as the bleed of the nitrogen supply line. These gases are mixed with filtere d air from the auxilia ry building and are drawn through charcoal and high-efficiency particulate air (HEPA) filters to remove iodine. The gases then pass through a regenerative heat exchanger and are discharg ed to the atmosphere.
Revision 52-09/29/2016 NAPS UFSAR 11.3-3 The heat exchanger raises the te mperature of the inlet gas to th e charcoal filters sufficiently to prevent water adsorption.
The process vent blowers maintain a slight vac uum in the charcoal filters to prevent leakage from the filter assembly. The decay tank pressure relief valves discharge to vent stack B.The process vent discharge nozzle and the process vent blowers are sized such that the minimum exit velocity is approximately 100 fps. This exit velocity prevents any significant downdrafting of the effluent with atmospheric winds as high as 35 mph. The process vent terminates at an elevation approximately 21 feet above the top of the Unit 1 containment structure.11.3.3 Operating Procedures In the event that the activity of the process vent stream exceeds th e setting of the process vent radiation monitors, the release from the wa ste gas decay tanks and the containment vacuum pumps to the process vent are te rminated automatically; releases from tank vents to the process vent are terminated manually. The monitor also alarms in the ma in control room prior to valve closure if the activity approaches a preset value. Subsequent restar t of the gaseous release to the process vent is accomplished manually in accordance with administrative procedures.The gaseous waste disposal syst em provides adequate radioactiv e decay storage time for the waste gases and long-term holdup of these gases wh en either high-flow le tdown is required or adverse meteorological conditions make it desi rable to discontinue re lease of waste gas to environment. Gases in these tanks should be allowed to decay for 60 days before release, unless additional gas storage capacity is required by reactor shutdown or start-up activities. It is assumed that essentially all of the gases and that a very small percentage (0.1%) of the iodines are removed from the letdown stream at the gas stripper and sent to the wast e gas decay tanks. Utilization of steam heating at the gas stripper will vary with th e level of coolant activi ty due to fuel defects.
The estimated curies of each radionuclide that will be released from the station via the gaseous waste disposal system are lis ted in Table 11.3-3. The estimated gaseous releases are based on a set of assu mptions, discussed in Section 11.3.5 , regarding the operation of the gaseous waste disposal system and various process sy stem radioactive liquid flowrates. These assumptions were deve loped during the plant design to demons trate compliance with NRC effluent release regulations. These assumptions were intended to be repres entative of the plant operation. In some instances, this is not the case sinc e various system process parameters have proven to be different from the initial estimated values. These original estimates represented the basis for compliance to the NRC re quirements in the original lic ensing basis. Adherence to the gaseous waste effluent requiremen ts is monitored by procedures in accordance with the Offsite Dose Calculation Manual (ODCM), as discussed in Section 11.4.4.2.
Revision 52-09/29/2016 NAPS UFSAR 11.3-4Monitoring gaseous effluents in accordance wi th the ODCM ensures that the composite results of the variations in ga seous waste inputs and processing on the actual releases are within the accepted current licensing basi s for the gaseous waste disposal system as specified in the acceptance criteria of th e ODCM. In addition, this moni toring has demonstrated that the released gaseous waste activities are typically significantly less than th e expected case releases from Table 11.3-3.11.3.3.1 Ventilation Vent Subsystem The ventilation vent subsystem is considered to be a portion of the gaseous waste disposal system only for purposes of radiol ogical surveillance, and it is de signed on this basis. The relief valves that relieve into the ventilation vent stack B contain potentially radioactive gases and hydrogen. However, since the gase s to be handled are predominantly of nonradioactive origin, this subsystem has been considered an auxiliary system for the purpose of this report. A full description of this subsystem is included in Section 9.4.11.3.3.2 Safety Considerations There are two portions of the gaseous wast e disposal system where oxygen and hydrogen are mixed. The decay tanks discha rge into a dilution air line prior to release from the process vents. Relief valves discharge into vent stack B.The waste gas decay tank mixture, after decaying, is dischar ged into the process vent at a maximum rate of 3.0 scfm and mixed with dilution air. Th e dilution air is drawn continuously by one of two process vent blowers with a system flow specified in the Technical Requirements Manual. An oxygen sampling system and nitrogen blanket system are provided on the inner tank of the double-walled decay tanks, in addition to manual sample co nnections. Manual controls are provided to add nitrogen and take samples fro m outer tanks of the decay tanks. The oxygen concentration within the i nner tanks is monitored to verify a concentration of less than or equal to 2% by volume at all times, whenever the hydr ogen concentration could exceed 4% by volume.
The relief valves that relieve into vent stack B contain potentially radioactive gases and hydrogen. The relief valve sizing is such that the maximum disc har ge rate of hydrogen from the gas decay tanks will not produce greater than 4 volume percent hydrogen in the mixed discharge of vent stack B.11.3.4 Performance Tests During the preliminary operat ion period, all equi pment in the gaseou s waste disposal system was tested to verify conformance with specification performance requirements. All control systems and interlocks we re tested and operated to ensu re satisfactory performance and reliability.
Revision 52-09/29/2016 NAPS UFSAR 11.3-5Continuous monitoring of the effl uent from the waste gas decay tanks and the process vent discharge, coupled with periodic sampling and analysis of system influents and effluents, yield information on the performance of the system.11.3.5 Estimated Releases The gaseous releases presented in Tables 11.3-2 and 11.3-3 are based on the assumptions given in Section 11.1 and the following assumpti ons for each specific source.11.3.5.1 Waste Gas Decay Tanks The gaseous waste disposal system is desi gned to provide adequate radioactive decay storage time for the waste gases and, in addition, to provide long-term holdup of these gases when either high-flow letdown is requ ired or adverse meteorological conditions make it desirable to discontinue release of waste gas to the environment. The tanks are located within va ults south of the fuel building, as sh own on Reference Drawing
- 4. These tanks are provided with high-pressure alarms. In addition, tank pressure can be monitored in the control room. The air space of the waste gas decay tank vaults can be sa mpled by the radiation monito ring system for gaseous and particulate activity.
For the design release case, the waste gas rele ase estimates are calculated for two units in the base load cycle assuming (1) 1.0% failed fuel; (2) one unit 4 weeks behind the other; (3) a 365-day feed (including the stripping of all noble gas from one unit at the end of the feed cycle), a 60-day nominal decay after the feed cycle is complete, and a 10-day bleed cycle for the waste gas decay tank; and (4) the stripping of all noble gas from the ot her unit and the feeding of this gas to the tank at the beginning of the feed cycle.
Coolant gaseous activity at the st art of the feed cycle equals zero.Fuel activity at the start of the feed cycle is equal to one-third of a two-year-old core, one third of a one-year-old core, and one-third of a new core.
The annual average letdow n for two units in the base load cycle is 0.94 gpm. It is assumed that all of the gases and 0.1% of the iodines in the letdown will be removed at the gas stripper and sent to the waste gas decay tank.The iodine activity released from the waste gas decay tan k passes through charcoal filters (90% efficiency for iodine collectio n) in the process vent subsystem.
For the expected case, all assumptions are the sa me except that feed time to the waste gas decay tanks is 300 days and the iodine activi ty released from the wast e gas decay tank passes through charcoal filters with 99% efficiency for iodine collection.
Based on the above factors, the dose rate at the ground surface above the vaults is less than 0.75 mrem/hour.
Revision 52-09/29/2016 NAPS UFSAR 11.3-6 The design values of the radioisotope invent ory in the waste gas decay tank are listed in Table 11.3-4.11.3.5.2 Boron Recovery Tanks The three boron recovery tanks are 120,000-g allon non-seismic tanks inside a protective enclosure which is loca ted south of the Unit 1 containment as shown on Reference Drawing
- 4. Inside the enclosure, each tank is located within a Seismic Class 1 dike which is capable of retaining the entire contents of the tank, as described in Section 3.8.1.1.8.This analysis assumes that all of the noble gases are stripped from the boron recovery letdown in the gas stripper prio r to entering the boron recovery tank and are not available for release from the boron recovery tanks. However, some isotopes of xenon are produced in the boron recovery tanks from the deca y of iodines and it is assumed that 0.1% of this xenon diffuses from the liquid and is released to the environment. Any amount released to the surface of the boron recovery tanks is passed thr ough the process vent by sweep gas.
Analysis of the expected radiation level fro m the boron recovery ta nk is based on a 0.2%
failed fuel inventory and on boron re covery tanks with a volume of 120,000 gallons. One boron recovery tank is assumed to be filled with deminerali zed and degassed primary coolant that has passed through the mixed bed deminer alizer with a decontamination factor (DF) of 10 for all isotopes except Cs, Mo, and Y, a nd through a cation demineralizer w ith a DF of 10 for iodines. Operation is for 365 days in the design case and 300 days in the expected case. The rate of xenon production at this maximu m inventory is assumed to occur for the enti re year. Even with these conservative assumptions, the gaseous activity released from the boron recovery tanks is insignificant compared to other sources. Th e expected radiation level is less than 0.75 mrem/hour in all accessible areas external to the dike.
The tanks are provided with level indication, high-level alarms, and overflows to each other as safeguards against overfilling.11.3.5.3 Boron Recovery Test Tanks These tanks are located external to and a bove the underground por tion of the Auxiliary Building north of the Unit 1 containment, as show n on Reference Drawing
- 4. These tanks are non-seismic and act only as a tem porary storage location for dist illate formed from the boron recovery evaporator. These tank s have level indica tion in the control room. The tanks are designed with an overflow system that is connected between each tank and that will overflow to the low level liquid waste tanks. The dose rate at the surface of these tanks will be less than 0.75 mrem/hour. This calculation is based on the following:1.Failed fuel at 0.2%2.Maximum boron recovery tank invent ory pumped to the boron evaporators.
Revision 52-09/29/2016 NAPS UFSAR 11.3-73.Boron recovery evaporator with a DF of 10 4.4.Boron recovery test tank volume of 20,000 gallons.11.3.5.4 Refueling Water Storage TanksThese tanks are located south of the service building and adj acent to the respective unit containments, as shown on Reference Drawing
- 4. The tanks, described in Section 6.2.2.2 , are Seismic Class I structures. They are provided with leve l indication and low and high alarms to detect leakage, as discussed in Chapter 9. Radiation levels at the surf ace of the tanks are to be maintained ALARA.11.3.5.5 Primary-Grade Water Tanks The tanks are located south of the fuel building between the containments for Units 1 and 2, as shown on Reference Drawing
- 4. These tanks are non-seismic. Th ese tanks can receive liquid from the water treatment system, the condensate tanks, or from the boron re covery test tank.
These tanks provide a holdup volume for water that meet s primary coolant chemistry specifications. The radiation level at th e surface of these tanks is less than 0.75 mrem/hour. This calculation is base d on the following:1.0.2% failed fuel.2.Maximum boron recovery test tank inventor y pumped to the primary grade water tanks.3.No credit taken for decay during tran sfer to the primary-grade water tanks.4.No credit taken for dilution in the primary-grade water tanks.11.3.5.6 High-Level Liquid Waste SystemAs in the boron recove ry tanks, iodine decay is the sour ce of the noble gas released from this system.
For this analysis it is assume d that all of the flow from th e sampling sinks, laboratory wastes, boron recovery system, su mps, and spent resin flush passe s through the high-level waste system.Total flow assumed fo r this system is 240,000 gallons per year for the design case and 110,000 gallons per year for the expected case. With a high-level liquid wa ste tank volume of 5000 gallons, this results in approximately 48 tankfuls per year in the design case and 22 tankfuls per year in the expected case.
The rate of xenon production at the maximum inve ntory of one tank is assumed to occur for the entire operating year. Of th e xenon produced, 0.1% is assumed to diffuse out of the liquid and is vented to the environment.
Revision 52-09/29/2016 NAPS UFSAR 11.3-8 In this analysis, ma ximum production rates for xenon are assumed for the entire operating year, with no decay of the xenon. Even with thes e conservative assumpti ons, the total amount of xenon from the high-level waste syst em is insignificant compared to other sources listed in Table 11.3-2.11.3.5.7 Containment PurgeThe activity released from purging the contai nment after shutdown is based on the failed fuel percentage and the primary coolan t leakage to the containment given in Section 11.1.For this analysis, two purges per year per unit are assumed.
In the design case, the buildup of activity is assumed to occur for 180 days before purging. In the e xpected case, the buildup of activity in the cont ainment at the end of the buildup period is assumed to be avai lable for release.
Equilibrium primary coolan t activities are conservatively assume d to be in the primary coolant for the entire buildup period. During purge operations, iodine is passed through HEPA/charcoal filters with an assumed iodine collection efficiency of 90% fo r the design case and 99% for the expected case.A discussion of the containment ventilation purge system appears in Section 9.4.9. The installed HEPA and charcoal filters used to limit releases are discussed in Section 9.4.8.11.3.5.8 Auxiliary Building Vent The activity released to the environment from the auxiliary building ventilation has as its source the equilibrium airborne activity in the auxiliary building from miscellaneous primary coolant leakages described in Section 12.2.3 from the sample sink hoo d ventilation and from various radioactive relie f valves. For the design case, activity is as sume d to be released for 365 days, and for the expected case for 300 days. Au xiliary building ventil ation flow is passed through HEPA/charcoal filters with an assumed iodine collection ef ficiency of 90% for the design case and 99% for the expected case. Assuming that only one assembly is operational, either the auxiliary building general area e xhaust or the auxiliary buildi ng central area exhaust may be passed through the filter assembly.Each exhaust is monitored peri odically on a fixed-time cycl e from the main control room and, if a high radiation signal is received, the control room op erator will manually divert the contaminated flow to the filter bank. Radioactive relief valves will be checked to determine if any have lifted. In order not to exceed the capacity of the filter bank, the operator will manually shut off the two auxiliary building s upply fans and one exhaust fan in the contaminated system.Section 9.4.8.1 describes the efficiency of the HEPA filters and charcoal adsorbers, which will limit atmospheric releases of airborne radioactivity to th e as-low-as-practicable guideline.
Revision 52-09/29/2016 NAPS UFSAR 11.3-911.3.5.9 Steam Generator Blowdown Tank Vent When the low-capacity steam generator blowdown system is in operation, steam generator blowdown liquid flashes in the steam generator blowdown tank, resulting in the release of a fraction of the iodines containe d in the steam generator blowdow n liquid. It is assumed that 1
µCi of iodine is released fr om the liquid for every 50
µCi of iodine that ente r the blowdown tank. It is further assumed that t h e steam flashed from the blowdown tank is condensed by the steam generator blowdown tank vent condenser. Under normal conditio ns, the vent condenser would provide a DF of infinity for the iodines, since they would all be returned with the condensed steam to the steam generator blowdown stream for discharge through the clarifiers. However, in this analysis, a DF of 100 has been conservatively assumed for the condenser.11.3.5.10 Secondary Steam ReleasesWith primary to secondary leak age in the steam gene rator, the potential for the release of radioactivity exists in the main and auxiliary steam systems and through condenser air ejectors.
Main steam activities are listed in Tables 11.1-8 and 11.1-9.For this analysis all of the nobl e gases in the main steam are assumed to be dischar ged to the environment via the main condenser air ejector.
Iodine in the main steam may be released to the environment from:1.Main steam leakage to the turbine building. Th e steam has the iodine concentration listed in Tables 11.1-8 and 11.1-9.2.The heating system drain receiver vent and auxiliary steam drain receiver vent. The main steam activity is assumed to have a plateout factor of 2 in the condenser and the reflashed steam has a partition f actor of 10; thus, there is an ov erall reduction fact or of 0.05 for the main steam activity.3.The main condenser air eject or, gland seal ejector, and chilled water unit air ejector condenser. The main steam activit y has a plateout factor of 2 in the condenser and a partition factor of 10 (µCi/cm 3 liquid/µCi/cm 3 gas) from the condensed liquid to the water vapor. With a density of 0.068 lb/ft 3 of air vapor, the discharge pe r pound has an activity equivalent up to 0.045 times the main steam activity per pound.11.3.6 Release PointsRelease points from the gaseous waste systems to the environment ar e shown on the system diagrams, Reference Drawing 1 through 3.11.3.7 Dilution Factors In evaluating the estimated a nnual radiation doses resulting from the expected releases pres ented in Table 11.3-3, annual average /Q values were obtained from meteorolog ical data collected onsite. These data are presented in Section 2.3. The /Q values were generated fr om Revision 52-09/29/2016 NAPS UFSAR 11.3-10 these data assuming a continuous source and a ground-le vel release model. Dispersion attributable to release he ight, exit velocity , and plume buoyancy was not incl uded in the model. In calculating offsite radionuclide concentrations, plume depl etion, which would occur from deposition and radioactive decay, was not assumed.11.3.8 Estimated Doses from Gaseous EffluentsA full and complete evaluation of the radiological impact to be incurred by the expected gaseous radioactive releases fro m the station is contained in Appendix 11B. Only a summary of the more important features of that append ix and the doses obtained are presented here.
Maximum individual external e xposure rates due to the gaseous releases calculated for the expected case have been evaluated at the positi on of maximum dose r ate for locations on land outside the 1-mile exclusion radi us. The applicable annual average /Q at the positi on of interest, 1 mile SSE of the reactors, has b een obtained from onsite meteorol ogical data collected during the period September 6, 1971, through September 15, 1972, and is equal to 1.83 x 10-6 sec/m 3. Using the semi-infinite sphere model, the annual whol e-body exposure of a person at the given location is calculated to be 0.616 mrem/yr. The annual thyroid dose at th e same location from inhalation of released radioiodines is calculated to be 0.070 mrem/yr. The release rate s upon which these doses are based are presented in Table 11.3-3. Appendix 11B contains the mathem atical formulae and dose parameters used in the evaluation.
The potential radiation exposur e of a child' s thyroid from ingestion of mi lk containing radioactive iodine has been estimated.
Gaseous radioiodine may be de posited on nearby grazing lands following release from the station, and it may be ingested by lactating cows. Some of the iodine will then be transferred to the milk produced by the animals. Because of th e small size of the thyroid gland, the critical receptor for this exposure pathway is a young child 6 months to 1 year in age. Conservatively assuming that the cows graze on grass for the full year and that no dilu tion with other milk supplies occurs, the potential exposure from ingestion from this source at the nearest Grade A dairy farm (about 3.6 miles SSE of the reactor s) is estimated at 1.21 mrem/yr. The annual average /Q at this location is 1.20 x 10-7 sec/m 3.The combined maximum annual dose from radioiodine due to inhalation of released radioiodines (0.070 mrem) and milk ingestion (1.21 mrem) is 1.28 mrem, well below the maximum dose permitted by Appendix I of 10 CFR 50 (15 mrem). No other exposure pathways have been found to be of any significance. Only external exposure from the released radiogases is of significance regard ing population exposure.
Population exposure from expected gaseous releases has been estimated on the basis of the projected population distributions within 50 miles of the station. The pr ojections, presented in Chapter 2 , are available for the years 1970, 1980 , 1990, 2000, 2010, a nd 2020. Using the Revision 52-09/29/2016 NAPS UFSAR 11.3-11 semi-infinite sphere model, the total population exposure within 50 miles at the station has been evaluated and is as follows:
The above population expos ure due to station operation may be placed in perspective by a comparison with the exposure occurring within 50 miles due to natural background radiation, which ranges from 104,531 man-rem/yr in 1970 to 224,493 man-rem/yr in the year 2020.Any projected increase in environmental radioa ctivity or radiation le vels due to gaseous waste releases is therefor e expected to be insignifi cant, undetectable in mo st cases, and the use of source term calculations would be the only practical way to quantify such increases.11.3 REFERENCE DRAWINGSThe list of Station Drawings below is provided fo r information only. The referenced drawings are not part of the UFSAR. This is not intended to be a complete listing of all Station Drawings referenced from this section of the UFSAR. The contents of St ation Drawings are controlled by station procedure.
Drawing Number Description 1.11715-FM-097AFlow/Valve Operating Number s Diagram: Gaseous Waste Disposal System, Unit 1 2.11715-FM-097BFlow/Valve Operating Number s Diagram: Gaseous Waste Disposal System, Unit 1 3.11715-FY-1BSite Plan, Units 1 & 2 4.11715-FY-1APlot Plan, Units 1 & 2YearPersons Within 50 MilesTotal Man-Rem Within 50 Miles of the SiteMillirem Per Capita 1970 836,2503.115 0.00373 1980 998,408 3.709 0.00371 1990 1,176,590 4.373 0.00372 2000 1,363,945 5.066 0.00371 2010 1,566,731 5.820 0.00371 2020 1,795,944 6.655 0.00370 Revision 52-09/29/2016 NAPS UFSAR 11.3-12Table 11.3-1 GASEOUS WASTE DISPOSAL EQUIPMENT DESIGN DATAWaste Gas Decay Tanks Number 2 Capacity per tank 462 scf Design pressureOuter TankInner Tank Full vacuum to 137 psig Full vacuum a to 175 psig Design temperature 200°F 200°F Operating pressure, max.
5 psig 125 psig Operating temperature 120°F 140°F Material Carbon steel SS 304L Design Code ASME VIII, 1968 ASME III C, 1968Waste Gas Surge Tank Number 1 Capacity 14.7 scf Design pressure Full vacuum to 175 psig Design temperature 300°F Operating pressure Atmospheric Operating temperature 200°F Material SS 304 Design Code ASME III C, 1968Process Vent Regenerative Heat Exchanger Number 1Total duty 3.5 x 10 3 Btu/hrShellTube Design pressure 15 psig 15 psig Design temperature 180°F 180°F Operating pressure Atmospheric 2 psig Operating temperature, in/out, max.105°F/115°F 145°F/135°F Material Carbon steel SS 304 FluidAir Air Design Code ASME VIII, Division I, 1968 ASME VIII, Division I, 1968Process Vent Blower Number 2Type Multistage centrifugal Motor horsepower 7.5 Capacity per blower 307 scfma.The inner tank low pressure design is related to the outer tank pressure. If the inner tank pressure is less than the outer tank pressure, the differential pressure must be less than 18.2 psid. There is no design limitation if the inner tank is at a higher pressure than the outer tank.
Revision 52-09/29/2016 NAPS UFSAR 11.3-13Differential pressure (at rated flow)1.65 psi Suction pressure 14.2 psiaDischarge pressure 15.9 psiaWaste Gas Compressor Number 2Type Diaphragm Motor horsepower 3 Capacity per compressor 1.5 scfmDischarge pressure at rated
capacity 150 psig Design pressure 220 psig Materials Cylinder Carbon steel Piston rodForged steel Piston Nodular iron Diaphragms and parts contacting waste gas SS 304/316Waste Gas Filter Assemblies Number 2Filter element typeHEPA and activated charcoalHEPA FiltersNumber per assembly 1 Normal capacity 1000 cfm Maximum capacity 1200 cfm Frame materialCadmium plated steel Design pressure 15 psig Design temperature 250°F Design CodeUSAEC Health and Safety Bulletin 306, Type II BFilter efficiency 99.97 Charcoal FiltersNumber per assembly 3 Normal capacity 300 cfm Maximum capacity 1000 cfm Frame material 304 stainless steel Design pressure 15 psigTable 11.3-1 (continued)
GASEOUS WASTE DISPOSAL EQUIPMENT DESIGN DATAa.The inner tank low pressure design is related to the outer tank pressure. If the inner tank pressure is less than the outer tank pressure, the differential pressure must be less than 18.2 psid. There is no design limitation if the inner tank is at a higher pressure than the outer tank.
Revision 52-09/29/2016 NAPS UFSAR 11.3-14 Design temperature 250°F Design Code Specification NAS-262Elemental iodine adsorption efficiency Expected 99%For calculation of design releases 90%Table 11.3-1 (continued)
GASEOUS WASTE DISPOSAL EQUIPMENT DESIGN DATAa.The inner tank low pressure design is related to the outer tank pressure. If the inner tank pressure is less than the outer tank pressure, the differential pressure must be less than 18.2 psid. There is no design limitation if the inner tank is at a higher pressure than the outer tank.
Revision 52-09/29/2016 NAPS UFSAR 11.3-15Table 11.3-2ESTIMATED GASEOUS EFFLUENTS CI/YR FOR TWO UNITS DESIGN CASE IsotopeWasteGas Decay Tanks BoronRecovery andHigh-LevelWaste Tanks ContainmentPurge Auxiliary BuildingVentSteamGenerator BlowdownTankVentsMain Condenser AirEjectorVentsAuxiliarySteam Drain ReceiverTurbine Bldg.Ventilation Exhaust GlandSealEjectorVent Heating System Drain ReceiverVentsChilledWater AirEjectorVentsTotalI-1312.0 x 10-5-4.6 x 10-2 6.0 x 10-1 1.3 x 10-11.8 x 10-24.4 x 10-1 4.4 x 10-1 4.8 x 10-11.6 x 10-23.7 x 10-32.2 x 10 0I-132--8.1 x 10-3 2.1 x 10-1 1.9 x 10-22.7 x 10-36.4 x 10-2 6.4 x 10-2 7.0 x 10-22.4 x 10-35.3 x 10-44.4 x 10-1I-133--6.0 x 10-2 9.7 x 10-1 1.5 x 10-12.0 x 10-24.9 x 10-1 4.9 x 10-1 5.3 x 10-11.8 x 10-24.0 x 10-32.7 x 10 0I-134--1.4 x 10-3 1.3 x 10-1 2.3 x 10-33.2 x 10-47.7 x 10-3 7.7 x 10-3 8.4 x 10-32.8 x 10-46.4 x 10-51.6 x 10-1I-135--2.3 x 10-2 5.2 x 10-1 4.5 x 10-26.2 x 10-31.5 x 10-1 1.5 x 10-1 1.6 x 10-15.5 x 10-31.2 x 10-31.1 x 10 0Kr-85m--3.0 x 10-1 5.1 x 10 1-6.2 x 10 2-----6.7 x 10 2Kr-851.0 x 10 4-4.9 x 10 2 1.3 x 10 2-1.5 x 10 3-----1.2 x 10 4Kr-87--5.2 x 10-2 2.9 x 10 1-3.5 x 10 2-----3.8 x 10 2Kr-88--3.4 x 10-1 9.0 x 10 1-1.1 x 10 3-----1.2 x 10 3Xe-131m1.5 x 10 0 5.6 x 10-11.5 x 10 1 2.9 x 10-3-------1.7 x 10 1Xe-133m1.3 x 10-6 1.8 x 10-25.7 x 10 0 7.7 x 10 1-8.9 x 10 2-----9.7 x 10 2Xe-1339.0 x 10 0 3.2 x 10-11.2 x 10 3 6.9 x 10 3-8.0 x 10 4-----8.8 x 10 4Xe-135m-7.5 x 10 01.4 x 10-1 4.2 x 10 0-5.4 x 10 1-----6.6 x 10 1Xe-135-5.8 x 10-12.3 x 10 0 1.5 x 10 2-1.8 x 10 3-----2.0 x 10 3Xe-138--6.2 x 10-3 1.5 x 10 1-1.9 x 10 2-----2.1 x 10 2 Revision 52-09/29/2016 NAPS UFSAR 11.3-16Table 11.3-3ESTIMATED GASEOUS EFFLUENTS CI/YR FOR TWO UNITS EXPECTED CASE IsotopeWaste Gas Decay Tanks Boron Recovery and High-LevelWaste TanksContainmentPurgeAuxiliary BuildingVentSteam Generator BlowdownTankVents MainCondenser AirEjectorVents AuxiliarySteam DrainReceiverTurbineBldg.VentilationExhaust GlandSealEjectorVentHeatingSystem Drain ReceiverVentsChilledWater AirEjectorVentsTotalI-1314.0 x 10-7-4.2 x 10-44.8 x 10-34.2 x 10-3 9.9 x 10-4 2.4 x 10-2 2.4 x 10-2 2.6 x 10-21.1 x 10-3 2.4 x 10-4 8.6 x 10-2I-132--7.7 x 10-51.7 x 10-35.3 x 10-4 1.2 x 10-4 3.0 x 10-3 3.0 x 10-3 3.3 x 10-31.3 x 10-4 3.0 x 10-5 1.2 x 10-2I-133--5.6 x 10-47.8 x 10-33.8 x 10-3 9.1 x 10-4 2.2 x 10-2 2.2 x 10-2 2.4 x 10-29.8 x 10-4 2.2 x 10-4 8.2 x 10-2I-134--1.4 x 10-51.0 x 10-34.6 x 10-5 1.1 x 10-5 2.6 x 10-4 2.6 x 10-4 2.8 x 10-41.2 x 10-5 2.6 x 10-6 1.9 x 10-3I-135--2.1 x 10-44.2 x 10-31.0 x 10-3 2.4 x 10-4 5.8 x 10-3 5.8 x 10-3 6.3 x 10-32.6 x 10-4 5.8 x 10-5 2.4 x 10-2Kr-85m--3.0 x 10-24.2 x 10 0-2.0 x 10 1-----2.4 x 10 1Kr-851.8 x 10 3-4.1 x 10 11.0 x 10 1-4.8 x 10 1-----1.9 x 10 3Kr-87--5.2 x 10-32.4 x 10 0-1.1 x 10 1-----1.3 x 10 1Kr-88--3.4 x 10-27.3 x 10 0-3.5 x 10 1-----4.2 x 10 1Xe-131m3.0 x 10-1 9.5 x 10-2 1.5 x 10 02.3 x 10-4-------1.9 x 10 0Xe-133m2.1 x 10-7 2.5 x 10-35.7 x 10-16.2 x 10 0-2.9 x 10 1-----3.5 x 10 1Xe-1331.5 x 10 0 4.4 x 10-2 1.2 x 10 25.6 x 10 2-2.7 x 10 3-----3.4 x 10 3Xe-135m-1.0 x 10 01.4 x 10-23.4 x 10-1-1.8 x 10 0-----2.8 x 10 0Xe-135-7.9 x 10-22.3 x 10-11.2 x 10 1-5.8 x 10 1-----7.0 x 10 1Xe-138--6.2 x 10-41.2 x 10 0-6.3 x 10 0-----7.5 x 10 0 Revision 52-09/29/2016 NAPS UFSAR 11.3-17Table 11.3-4WASTE GAS DECAY TANK MAXI MUM R ADIOACTIVE GASEOUS ACTIVITY DESIGN CASE Isotope Concentration
(µCi/cm 3)Kr-85m 6.6Kr-85 8.0 x 10 2Kr-87 9.2 x 10-2Kr-88 4.7 Xe-131m 5.8 Xe-133m 4.4 x 10 1 Xe-133 4.6 x 10 3 Xe-135m 1.7 x 10-1 Xe-135 3.5 x 10 1 Xe-138 2.4 x 10-10 I-131 5.0 x 10-3 I-132 1.6 x 10-4 I-133 4.7 x 10-3 I-134 3.5 x 10-7 I-135 1.2 x 10-3 Revision 52-09/29/2016 NAPS UFSAR 11.3-18Figure 11.3-1 (SHEET 1 OF 2)GASEOUS WASTE SYSTEM Revision 52-09/29/2016 NAPS UFSAR 11.3-19Figure 11.3-1 (SHEET 2 OF 2)GASEOUS WASTE SYSTEM Revision 52-09/29/2016 NAPS UFSAR 11.3-20 Intentionally Blank Revision 52-09/29/2016 NAPS UFSAR 11.4-111.4 PROCESS AND EFFLUENT RADIA TION MONITORING SYST EM11.4.1 Design ObjectivesThe process and effluent radiation monitoring system (RMS) continuously monitors selected lines containing, or possi bly containing, radioactive ef fluent. The system's function is to warn personnel of increasing radiat ion levels, to give early warn ing of a system malfunction, and to record and control discharges of radioactive fluids and gases to the environment at permissible emission rates to meet the requirements of 10 CFR 20, 10 CFR 50, and 10 CFR 50 Appendix A General Design Criterion 64.Design objectives are to provide early warning of system malfunctions and to initiate action to mitigate the conseque nces of a malfunction.
The post-accident monitoring porti on of this system is designed to satisfy the requirements of NUREG-0578, TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations and NUREG-0737, Clarification of TMI Action Plan Requirements , as described in Section 11.4.3.The recirculation spray cooler service water outlet monitors and the RMS control room cabinets are designed to Seismic Class I requirements to ensure thei r availability under accident conditions.11.4.2 Continuous MonitoringThe process and effluent radi ation monitoring system se rving both units during normal operation consists of the channels listed in Table 11.4-1. Each channel that monitors a discharge path to the environment is located downstream from the last point of possi ble fluid addition to the ef fluent path being monitored.
Each radiation monitoring cha nnel is designed to provide c ontinuous information about the process or ef fluent stream bei ng monitored. Continuous, as used to describe the operation of the process and effluent radiation monitoring systems, means that a monitor provides the required information at all times with the following exceptions: (1) the system is not required to be in operation because of specified plant conditions gi ven in the T echnical Re quirements Manual, or (2) the system is out of service for testing or maintenance and approved alternate monitoring, sampling, or recording methods are in place.
The containment gas and particul ate monitor sample point is located as close as possible to the intake of the ventilation duct to minimize losses in the duct. Samples for the component cooling-water monitor and the liquid waste evaporator monitor are located so as to obtain a representative sample of the ra dioactive fluids being monitored.
Revision 52-09/29/2016 NAPS UFSAR 11.4-2 Each detector is located in an easily accessible area and is provi ded with sufficient shielding to ensure that the required sensitivity is achieved when the back ground radiation le vel is at the design maximum for the area, as shown in Table 11.4-1.11.4.2.1 Anticipated Concentrations, Sensitivities, and Ranges A channel is deemed to have the required sensitivity when th e count rate indicated in the main control room with the detector exposed to the nuclide con centration in the ef fluent being monitored equals or exceeds twice the count rate due to area background.Each channel listed in Table 11.4-1 monitors gross concentrati ons, and detector output is measured in counts per minute (cpm
), except the letdown monitors , which indicate mrem/hr , the process vent monitors, the ventilation vent monitors, and the high capacity SG blowdown discharge monitors, which indicate in
µCi/cc. Each channel has a minimum range of three decades, except for the recircula tion spray cooler service water outlet m onitors, which have a minimum range of two decades to increase sensitivity.
The expected concentrations of nuclides in the ef fluent streams monitored by the liquid waste monitors, the steam generator blowdown monitors, and the circulating-water discharge tunnel monitors are presented in Section 11.2.5.The expected release rates of nuclides in the ef fluent stream s monitored by the process vent monitors, the containment gas and particulate monitors, and the condenser air ejector monitors are presented in Section 11.3.5.The purpose of the following monitors is to detect leaks or sp ills into normally nonradioactive systems or areas. The expected concentrations of nuclides in the streams they monitor is that due to normal background.*Ventilation vent gas and particulate monitors.*Ventilation vent sample ga s and particulate monitors.*Component cooling-water monitor.*Component-cooling heat exch anger service-water monitor.*Service-water discharge to canal monitor.*Service-water discharge to Se rvice Water Reservoir monitor.The containment recirculation spray cooler serv ice water outlet monitors are only used in the event of a loss-of-coolant ac cident (LOCA). They ensure that any leaks in the containment recirculation coolers leading to contamination of the service water are de tected at levels well below those representing a hazard to the public.
Revision 52-09/29/2016 NAPS UFSAR 11.4-3 The reactor coolant letdown act ivity may range from negligible when the unit is at the beginning of the fuel cycle to about 215
µCi/cc if there is 1% failed fuel. The reactor coolant letdown monitor has a minimum sensitivity capable of detecting 0.1% fuel failures.
Each channel, except the high capacity SG bl owdown dischar ge monitors, has a readout at the main control room and selected ones, as indicated in Table 11.4-1, have a readout at the detector location. Each channel has two visual al arms for radiati o n levels in excess of preset values. Each channel provides a signal to the ma in control room causing an audible alarm to sound if either of the two preset radiation le vels are reached. The outpu t from all channels is documented on recorders that produ ce a continuous record of radi ation levels and radioactive discharges from the station except the high capacity SG blowdown discharge monitors which utilize computer data storage. Each channel has its own power supply and check source (except the letdown monitors, the high capacity SG blowdown discharge monitors, the normal/high range process vent and vent-vent (MGPI) effluent monitors, which do not have a check source), remotely operated from the main control room, thus making it co mpletely independent of any other channel. The MGPI equipm ent is continually self-checki ng in that, should the detector output signal drop below some prescribed value, effectively indicating th at there is no background signal, the detector will be considered faulty. This monitoring, in conjunction with the continual testing of the electronic signal processing circuits by generation and conf irmed receipt of test signals, provides assurance that th e circuits remain in good health.Adjustment of alarm setpoints, voltage, power, and other variables is made from the main control room, except for the following: (1) the high capacity SG blowdown discharge monitors are adjusted at their local controller workstation, (2) the service water discharge to the reservoir monitor is adjusted at the lo cal instrument chassis, (3) the normal/high range process vent (MGPI) and vent-vent (MGPI) ef fluent monitors which can be adjusted ei ther at the local display unit (LDU) or remote display unit (R DU) and (4) the reactor coolant letdown gross activity monitors which can be adjusted either at their LDU or RDU. The entire system is designe d with emphasis on system reliability and availability. Certain channels, as indicated in the following text, actuate control valves on an alarm signal.
Channels monitoring Unit 1 are powered from the 480V emergency bus 1H; channels monitoring Unit 2 are powered from the 480V emer gency bus 2H; channels monitoring systems or areas common to both units are powered from the emer gency bus for either Unit 1 or Unit 2. (Letdown monitors are not pow ered from emer gency buses.)To ensure the availability of at least two of the recircula tion spray cooler service water outlet monitors per unit under accident conditions, one pair of the recirculation spray cooler service-water outlet monitors for Unit 1 is powered from the vital bus panel 1, channel I, and the second pair is supplied fr om the vital bus panel 1, channel III; one pair for Unit 2 is supplied from the vital bus panel 2, channel I, and the second pair for Unit 2 is supplied from the vital bus panel 2, channel III.
Revision 52-09/29/2016 NAPS UFSAR 11.4-4The types of detectors, sensitivity, range, b ackground radiation, and othe r information for each channel are listed in Table 11.4-1. The counting rates of limiti ng isotopes for each channel, except the letdown m onitors, are shown in Table 11.4-2. A description of each channel is included in the following text.11.4.2.2 Process Vent Particulate Monitor This channel continuously withdr aws a sample from the process vent and passes the sample through a moving filter paper having a collection ef ficiency of 99% fo r particle sizes greater than 0.3 µm. The amount of deposited activ ity is continuously scanned by a silicon diode type detector. A high-activity alarm automatically stops the discharge of gases fr om the gaseous waste disposal systems. The sample pumping system, which serves both the particulate a nd gaseous process vent monitors, includes a pump, a mass flowmeter, and isolation valves.11.4.2.3 Process Vent Gas Monitor This channel takes the contin uous process vent sample, af ter it has passed through the particulate filter paper, and dr aws them through a sealed system to the process vent gas monitor assembly. This assembly is a fi xed, lead-shielded sampler containing a silicon diode type detector.
The sample activity is measured , and then the sample is retu rned to the process vent. A high-activity alarm automatically stops the discharge of gases fr om the gaseous waste disposal systems. A purge system is integral with the gas-monitoring system for flushing the sampler with clean air for purposes of calibration.11.4.2.4 Ventilation Vent A Particulate Monitor and Ventilation Vent A Gas Monitor These two channels in ventilation vent A continuously sample for pa rticulates and gas in the same way that the tw o channels m onitor the process vent sample. All equipment is similar to that of the two process vent channels , except that multiprobe samplers are provided to obtain a representative sample in the 90-inch-diameter ventilation vent A ducts.11.4.2.5 Ventilation Vent B Particulate Monitor and Ventilation Vent B Gas MonitorThese two channels in ventilation vent B continuously sample for pa rticulates and gas in the same way that the two process vent channels monitor the proc ess vent sample, except that multiprobe samplers are provided to obtain a representative sample in the 90-inch-diameter ventilation vent B duct, and that both channels are equipped with silicon diode type detectors. An advantage that the gas detector has is a sensitivity to Kr-85, the radiologically dominant nuclide for the ventilation vent B effluent pathway, which includes e xhaust air from the Spent Fuel Pool area.
Revision 52-09/29/2016 NAPS UFSAR 11.4-511.4.2.6 Ventilation Vent Multiport Sampler Part iculate and Ventilation Vent Multiport Sampler Gas MonitorThese two channels take a samp le from any one of seven ducts and monitor particulates and gases in the same way as the two channels monito ring the process vent. All equipment is identical to that of the process vent's two channels except that:1.This system includes seven isokinetic nozzles , a manifold, and a c ontrol valve system. A control panel automatically switches the valves on a periodic basis to permit sampling from the seven different areas. A manual positioner is provided to permit locking in on any chosen area.2.The equipment has the capability to program the filter to remain in a fixed position for a specified length of time. The filter remains in a stationary position for a programmed length of time before advancing.3.The sequencing of the valves is synchronized to the step advance programmer and the operator is able to select a sampling time at each of the seven areas between 30 minutes and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.11.4.2.7 Component Cooling-Water MonitorThis channel continuously monitors the component cooling-water system. Samples from each component cooling-water heat exchanger vent are cont inuously monito red by a common detector mounted in an in-line li quid sampler. Activity is indicative of a leak into the component cooling-water system from the reactor coolant system or one of the other radioactive systems that is served by the component cooling-water syst em. A valving arrangeme nt allows the heat exchangers to be individually sampled to identify the source of activity.11.4.2.8 Component Cooling Heat Exchanger Service-Water Monitor This channel continuously mon itors the service-water ef flue nt from the four component cooling-water heat exchangers. Samples from each main discharge are individually pumped to and continuously monitored by a detector mounted in an off-line liquid sampler. A valving arrangement allows the heat excha ngers to be individually sampled to determine the source of any high activity.11.4.2.9 Service-Water Discharge to Canal MonitorThis channel continuously monitors the service-water discha rge to the discharge canal. Samples from the two 24-inch discharge lines are mixed in a common header and the common sample is continuously monitored by a detector mounted in an off-line liquid sampler. A valving arrangement allows the two discharge lines to be individually samp led to determine the source of any high activity.
Revision 52-09/29/2016 NAPS UFSAR 11.4-611.4.2.10 Service Water Discharge to S ervice Water Reservoir Monitor This channel continuously monitors the serv ice-water discharge to the Service Water Reservoir. Samples from the two 36-inch discharge lines are mixed in a common header and the common sample continuously monitored by a detector mounted in an off-line liquid sampler. A valving arrangement allows the two discharge lines to be indivi dually sampled to determine the source of any high activity.11.4.2.11 Recirculation Spray Cooler-Serv ice W ater Outlet MonitorsThe recirculation spray coolers, as part of the recirculation spray subsystem, operate only after the occurren ce of a LOCA.
There are four recirculation spray coolers per unit, and each service-water outlet line is monitored, thus giving a to tal of eight channels. Al l of thes e channels are identical. In the event that the containment spray system is placed in service, a continuous sample is drawn out of the service-water outlet line and passed through an off-line liquid sampler, where it is monitored for activity indicative of a leak in the respective recirculation spray cooler. After passing through the liquid sampler, located outside th e containment in an enclosed, he avily lead-shielded structure, the sample is returned to the service-water line.11.4.2.12 Liquid Waste Disposal System MonitorsThe liquid waste disposal system is monitored by two detectors
, each of which is located in an in-line liquid sampler. One detector is located downstream from the clarifier unit, which is the last possible point where radioactive materials can be added. It monitors the liquid being discharged from this system to the circulating water system and then to the environment. A high-activity alarm automatically stops the discharge of liquid waste effluent. The other detector, which is located between the waste disposal evaporator and the clarifier unit, is us ed for process evaluation.11.4.2.13 Condenser Air Ejector MonitorsEach of these identical channels (one channe l per unit) continuously monitors the gaseous ef fluent from the condenser air ejectors by means of a G-M tube de tector mounted in an in-line sampler. Activity is indicative of a primary to secondary system leak. On a high-activity alarm, the flow is automatically diverted to the contai nment unless the containmen t has been isolated by a Phase A containment isolation signal.These monitors, or the steam generator blowdown monitors described below, will detect radioactive contamination in th e steam supply used for buildin g heating. These monitors will warn personnel of increasi ng radioactivity levels and therefore provide early indication of system malfunctions.
Revision 52-09/29/2016 NAPS UFSAR 11.4-711.4.2.14 Steam Generator Blowdown Monitors11.4.2.14.1 Steam Generator Blowdown Sample Monitors Each of these channels (three pe r unit) monitors the liquid phase of the steam generators for radioactivity indicative of a prim ary to secondary system leak. Th e use of three channels per unit will allow continuous monitoring of the blowdown from each of the three generators. Valving exists to allow combinations of generator bl owdown flow to be used to compensate for maintenance of channels, or s hould special situations exist.After being monitored, samples pass into the steam generator blowdown tank.11.4.2.14.2 High-Capacity Steam Generator Blowdown Discharge Monitors The high-capacity steam genera tor blowdown system flash ta nk drains are continuously monitored by a radiation monitor in the ef fluent line. This monitor does not perform a safety function, but is included as added protection against radiation re lease to the environment. The high-capacity system will be isolated automatically if the effl uent radiation monitor setpoint is exceeded.The proportional sampling system provides the required cooled blowdown ef fluent monitoring capability to allow the high-capacity blowdown system to be operated when low levels of primary to se condary leakage is within Technical Sp ecification limits. The required minimum sample flow rate for th e proportional sample is 0.5 ml/gal of effluent. When the sample from the tank shows no radioactivity, drains from the sample collection tank are batch discharged to the turbine building floor drains.11.4.2.15 Reactor Coolant Letdown Gross Activity Monitors Each unit has its reactor coolant continuously monitored by means of a detector mounted adjacent to the letdown line in the Chemical and Volume Control System. In this system, large variations in activity level are possible in the event of fuel element failure. There is one such system for each unit. In the event of a fuel element failure, the activity released will be sufficient to raise the coolant activity level above 1.0
µCi/cc of gross fission produc ts. This will cause the letdown monitor to begin to indi cate activity data corresponding to th e presence of fuel failures.11.4.2.16 Circulating-Water Discharge Tunnel Monitors Each of these identical channels (one per unit) monitors the effluent (service water, condenser circulating water, and liquid waste) in the circulating-water discharge tunnel beyond the last point of possible radioact ive material addition. A gamma scintillation de tector slides into a pipe that is inserted directly into the discharge tunnel. At the top of the pipe is a waterproof support assembly that encloses a check source. The entire device is waterproof.
Revision 52-09/29/2016 NAPS UFSAR 11.4-811.4.2.17 Containment Particulate Monitors Each channel, one per containment, continuou sly withdraws a sample from the containment atmosphere into a closed, shielded system exte rior to the containment.
The sample is passed through a moving filter paper with a collection efficiency of 99% of particles greater than 0.3
µm. The amount of deposited activity is continuously scanned by a lead shielded gamm a scintillation detector with a sens itivity as shown in Table 11.4-1. This sample system , which is common to both the particulate and gas monito rs, includes a pump, a flowmeter
, a flow-regulating valve, and isolation valves. A sample point is available for taking a sample of the containment atmosphere after an accident for spectrum analysis in the laboratory. During refueling, if the particulate nuclide concentration exceeds a pr edetermined setpoint, a high-ac tivity alarm automatically trips the containment purge air supply a nd exhaust fans and closes the purge system butterfly valves, thus isolating the purge system.11.4.2.18 Containment Gas Monitors Each channel, one per containment, takes th e continuous containmen t atmosphere sample, after it has passed thro ugh the particulate filter paper, and draws it thro ugh an in-line, easily removable, charcoal cartr idge arrangement to the containment gas monitor assembly, which is a fixed-volume, lead- shielded sa mple chamber enclosing a G-M tube detector. The sensitivity of this detector is 5 x 10-6 µCi/cc for Kr-85 in a background of 0.75 mrem/hr. The sample activity is measured, an d then the sample is returned to the containment.
During refueling, if the airborne gaseous activity concentration exceeds a predetermined setpoint, a high-activity alarm automatically trips the containment purge air supply and exhaust fans and closes the purge system butterfly valves, thus isolating the purge system.A purge valve arrangement blocks the normal sample flow to permit pur ging the detector with a "clean" sample for calibration. Purged gases are discharged to the ventilation vent.11.4.2.19 Spare ChannelsTwo spare channels consist of a complete instrument chassis, one identical to that of the process vent particulate monitor and one identical to the process vent gas monitor.11.4.3 Post-Accident Monitoring The purpose of the following radiation monito rs is to provide additional instrumentation which during normal operations supplements the proces s and ef fluent radiation monitoring equipment discussed in Section 11.4.2 , and provide accurate indicati on of plant releases of noble gases and particulates during and following an accident acco rding to the requirements of NUREG-0578 (Section 2.1.8.b) as clarified by NUREG-0737 (Section II.F.1).Following the accident at TMI-2 and in response to NUREG-0578, high range ef fluent monitors were installed in potential post-accident release pathways. These include the main steam Revision 52-09/29/2016 NAPS UFSAR 11.4-9 lines and the auxiliary feedwater turbine-driven pump exhaust lines.
These monitors are discussed in Section 11.4.3.2.NUREG-0737 clarified the po st-accident radiation mon itoring requirements of NUREG-0578. In response to NUREG-0737, a dual ra nge (normal and high range) ef fluent gas monitor system manufactured by MGP Instrume nts has been installe
- d. The MGP Instruments monitoring systems are installed in the process vent and in ventilation vents A & B. These monitors are discussed in Section 11.4.3.1.11.4.3.1 Normal and High-Range Effluent Gas Monitors11.4.3.1.1 Design Basis The post-accident normal and hi gh-range noble gas ef fl uent monitors loca ted at the process vent and ventilation vents are ma nufactured by MGP Instruments. Th ey are designed to meet the requirements of NUREG-0737,Section II.F.1, Attachments 1, Noble Gas Effluent Monitor. Also, NUR EG-0737,Section II.F.1, Attachment 2, Sampling and Analysis of Plant Effluents, requires the capability to collect and analyze or measure representative samples of radioactive iodines and particulates in plant gaseous effluents during and following an accident. This capability is integrated into the MGP Instruments monitoring system. The MGP Instruments post-accident monitors are listed in Table 11.4-3.The monitors have a total ra nge extending from normal cond ition concentrations to a maximum of 1.0 x 10 5 µCi/cc (Xe-133). This exceeds the design basis maximum range of 1.0 x 10 3 µCi/cc specified in NUREG-0737, Table II.F.1-1.The process vent and ventilat ion vent ef fluents are moni tored by the MGP Instruments systems downstream of all input streams. Redundancy is not required.The MGP Instruments process and ventilation vent equipmen t and mon itors are powered from emergency (diesel-backed) buses. The 480V ac power is supplied by either MCC-1H1-4 (normal) or MCC-1J1-1 (alternate) via a manual transfer switch. The 120V ac power is supplied by 1-EP-CB-16C (semi-vital bus) and 1-EP-CB-16D distribution panels.Procedures are in place to r outinely calibrate the detectors by using an acceptable source.
Continuous display of equivale nt Xe-133 concentrations (µCi/cc) is provided in the control room. Radiation concentrations and releas e rates will be recorded by recorders.
The MGP Instruments monitors and instrument s are designed for the accident e nvironment.
Seismic qualification of the syst em is not required. However , sampling nozzles installed in seismic pipe are seismica lly qualified and supported.
Particulate and iodine collecto rs are mounted in 6-inch 4 lead shields. A similar portable shielded transfer housing is provided to protect personnel during transfer. The dose rate 1 foot from the filter assembly will be 0.1 mrem/hr assuming the de sign-basis sample (100
µCi/cc Revision 52-09/29/2016 NAPS UFSAR 11.4-10[0.5 Mev gamma] 30-minute sampling time) and flow rate of 1000 cc/min. This meets the shielding design basis speci fied in NUREG-0737, Table II.F.1-2.The iodine collector has a cartr idge with an ef fective adsorption of not less than 95%. The particulate collector is a paper filter disk with a collection efficiency of 99% for 0.3 micron particles.The post-accident monitor sampling systems are design ed to ensure representative sampling. Sampling nozzles are installed in the effluent streams.
The MGP Instruments monitors, with the exception of the process vent monitor, which has fixed sample flow, will adjust sample flow automatically in proportion with the effluent stream. Flow signal s from the ventilation vent A & B stack flow transmitters will be input to the flow c ontrollers for this function.Heat tracing is requi red on the post-accident ventilation vent and process vent sample piping to prevent condensation.
The post-accident monitors must operate contin uously in accordance with the Technical Requirements Manual when the ventilation stacks or the process vent system is discharging.
The post-accident particulate a nd iodine collectors are suffic iently shielded to minimize personnel exposure during re trieval and transport.Three-foot tongs will be used to transfer the unshielded filter to the movable shielded cart.
Control room instrumentation to meet the requirements of NUREG-0737 Section II.F.1 is installed in a common high-range ef fluent radiation monitoring pane
- l. This includes displays for the process vent, ventilation ve nt, and steam release monitors.
Common annunciators (main steam Unit 1, main steam Unit 2, process vent, ventilation vents) are used to reduce the number of additions to the main control panel. These a nnunciators direct the operator to the high-range effluent radiation monitoring panel. Minimizi ng the number of annuncia tors, and grouping of related displays into a common panel is consistent with current human factors analysis standards and will serve to reduce the amount of confusion to the operator.11.4.3.1.2 Description Each MGP Instruments post-acci dent monitoring system is mo unted on a skid and consists of a noble gas monitor , particulate and iodine collectors, sample extractor, control room displays, local displays, electronics, pipi ng, valves, pumps, and a microcomputer controller. Flow elements and transmitters for ventilation st acks A and B, and the process vent flow transmitter supply linear signals to the normal- and high-range microcomputer controller.
The process vent normal-range monitor serves a control function when alarm setpoints are reac hed. A high activity alarm on the particulate or normal range gaseous channel automatically stops the discharge of gases from the gaseous waste disposal systems.
The MGP Instruments process vent monitors are located in the normal switchgear room of the service building to minimize post-accident background radiation and allow for personnel access to retrieve iodine and particulate filters for laboratory analysis.
Revision 52-09/29/2016 NAPS UFSAR 11.4-11 The process vent system is part of the gaseous waste disposal system as sh own in Reference Drawing 1. The MGP Instruments monitor sampling lines ru n from a sample nozzle installed in the discharge line of the process vent system (6-inch-GW 154) on th e 291-ft. 10-in. elevation of the auxiliary building, thro ugh the auxiliary building to the normal switchgear room of the service building. An effluent sa mple return line runs a similar path back to the process vent discharge pipe.
The MGP Instruments ventilation vent monitors are mounted on the operating floor of the turbine building near the condensate polishing system control panel.
The ef fluent sample lines run from a sample nozzle installed in th e vertical section of vent stack A and B in the turbine building and the respective monitors.
The normal operation process ve nt and ventilation vent ef fluent radiation monitoring systems described in Section 11.4.2 are installed and operationa l to satisfy the Technical Specification requirement for co ntinuous monitoring and recording of gase ous and particulate releases. The particulate monitors contain a moving filter paper with monitor to provide "real time" indication of particulate releases during no rmal operation. The po st-accident high-range MGP Instruments monitors contain shielded part iculate filters designed to minimize personnel exposure during retrieval and laboratory analysis. This meet s the requirements of NUREG-0737 Section II.F.1 since continuous monitoring of accident le vel particulate releases is not considered practical at this time.
The MGP Instruments post-acci dent process vent and ven tilation vent monitors are common to Units 1 and 2. The monitors ar e supplied with 480V ac power from the 1H1-4 or 1J1-1, emergency, motor contro l center via a transfer switch.
Local and remote display un its are supplie d with 120V ac power from 1-EP-CB-16C, semi-vital bus distribution panel.
Instrument cables are routed from each monitor skid to it s corresponding local display unit and to a corresponding remote display unit located in the control room.Instrument cables are routed from the existin g process vent flow transmitter and the flow transmitters are mounted in ventilation vent stacks A and B, near the sample nozzles to the respective remote display unit for computing effluent release concentrations
µCi/cc (Xe-133) and release rates Ci/sec (Xe-133).
Ambient air is supplied to the monitors for pur ging the monitors and sample piping.
Sample piping is 1-inch Class ICN8, welded stainless stee
- l. Connections to the MGP Instruments monitor skids are compression fitti ngs. Sample tubing for the ventilation vent monitors that runs outside of the turbine bui lding is heat traced to prevent condensation.
Each microcomputer provides for complete cont rol of the associated monitor. It can be controlled locally or remotely through the remote display unit in the control room. Alarms are Revision 52-09/29/2016 NAPS UFSAR 11.4-12 provided at the microcomputer and remote disp lay unit. In addition, a common annunciator and alarm is provided on the control board for the MGP Instruments process vent and ventilation vent high-range monitors. Continuous di splay of radiation readings an d recording of concentrations
(µCi/cc) and release rates (Ci/sec) by recorders is provided.11.4.3.1.3 Operation The normal operation process vent and ventilation vent system s must be operational during any mode (modes 1 through 6) of station operation. Gaseous and particulate monitoring and recording is required by T echnical Specification whenever an effluent release occurs.
The MGP Instruments post-accident high-range nobl e gas ef fluent monitors will operate to provide continuous monitoring a nd recording of noble gas and pa rticulate releases. The MGP Instruments monitors are also used during normal operation to monitor effluent releases.
The MGP Instruments post-accide nt high-range monitors are re quired to operate during and after an accident to provide continuous monitoring of high-level releases of noble gases, and continuous sampling of iodine and particulate releases.The MGP Instruments post-accident and norma l operation process ve nt and ventilation stack A and B monitoring systems may be operate d independently of each other
.11.4.3.2 High-Range Effluent Monitors Prior to the addition of the MGP Instruments system described above , several post-accident high-range ef fluent radiation monitors were installed in response to NUREG-0578. These monitors are listed in Table 11.4-4.The high-range effluent monitors consist of the detector and the control unit. The detector has a 9-decade range of 10
-2 to 10 7 mR/hr and is comprised of an ion chamber and a built-in radioactive source that provides a reference si gnal for testing purposes. The components are enclosed in a box that protects them from expected operating environments. The detector is enclosed in a lead shield to reduce background radiation, except in the main steam valve house detectors where the shield is used to reduce background radiatio n and permit collimation of the release path radiation field. The detectors are intended to monitor release paths. Eight paths of two types are monitored. The detectors are located at the following effluent points.Main Steam Lines.These detectors are intended to m eas ure activity that might be re leased via main steam safety valves or atmospheric dump and decay heat release valves. The detectors and their associated shields are mounted on the Unit 1 and 2 main steam valve house s outh interior walls facing the 32-inch safety valve rise r , SHP-22, 23, or 24 for Unit 1 and SHP-422, 423, or 424 for Unit 2. These shields collimate the ra diation field from the center line of the pipe. As each main steam header is a possib le independent release path, each safety valve riser is monitored.
Revision 52-09/29/2016 NAPS UFSAR 11.4-13Turbine-Driven Auxiliary Fe edwater Pump Exhaust Lines.
These detectors are intended to monitor the steam exhaust from the turbine-driven auxiliary feedwater pump. The detector for Unit 1 is located in the auxi liary feedwater pumphouse on a platform which permits access to the detectors for main tenance. The Unit 2 detectors are located on the auxiliary feedwate r pumphouse roof facing one of the two dischar ge lines. The discharge lines were rerouted to allow for adequate shielding of the detector from background radiation.The control unit for each detector contains the electronics necessary to interpret and display detector readings. These units ar e housed in boxes and have connect ions for the detector , remote readout, and power. Visual alarms for failure alert, and high ra diation are included. One control unit is required for each detector. Three of the four control units are located in the Quench Spray Pump House of each respective Un it and one control unit is located in the Auxiliary Feedwater Pump House of its respective Unit.
The monitors are powered from a reliable, dies el backed source (Semi-Vital bus of the respective Unit).
Although not required to function after a seis mic event, each detect or and its associated shield is seismically constrained.11.4.4 Sampling11.4.4.1 Liquid SystemsLiquid samples for determination of levels of radioactivity are periodically taken.Normally, high-level waste drain tanks are pr ocessed via the IEFS system. The influents and effluents of these filters and demineralizers are sampled periodically, generally daily. The low-level waste drain tanks are normally sampled weekly. If high concentration liquids are being processed, or are anticipated, th e sampling frequency of the low-level waste drain tanks is evaluated and adjusted accordingly.
Concentrations may approach 0.15
µCi/ml of mixed fission and activation products in the high-level waste drain tanks. Low-level waste drain tank samples de termine if the tank contents may be discharged or require further treatment. Concentrations generally will be between 10
-4and 10-8 µCi/ml.Contaminated waste drain tanks are normally sampled weekly. The boron recovery test tanks and the boron recovery tanks are normally sampled prior to release. If the clarifier demin is bypassed, the boron recovery test tank and the boron recovery tank will be sampled prior to release. The contents of the tank are discharged to the environment through the clarifier package.
Concentrations of mixe d fission and activation products (exc luding Noble Gases) in these tanks will generally be between 10
-3 µCi/ml and 10-6
µCi/ml. Sampling determines if the tanks may be discharged or require further processing.
Revision 52-09/29/2016 NAPS UFSAR 11.4-14Treated effluent is monitored by a radiation monitor before its release to the discharge canal. In addition, treated clarifier effluent is continuously sample d in proportion to the rate of flow of the effluent stream.The clarifier effluent line contains a manual regulating valve whic h continuously samples effluent discharge that is collected in the clarifier effluent proportional tank, thus fulfilling the sampling requirements of NRC Regulatory Guide 1.21. A sample is drawn from the clarifier ef fluent proportional tank for analys is as required. A commercially available, motor-driven mixer is installed in the tank, and be fore samples are taken, the conten ts will be mixed for at least 10 minutes. The minimum ratio of the sample rate to the ef fluent rate for the 125 gpm to 300 gpm range is 1:7826. The minimum and maximum flow limitations established is between 125 gpm and 300 gpm respectively.The control system for the clarifier effluent line sampling system is as follows:1.1-LW-SOV-121 is controlled fro m a locally mounted control swit ch. In the "Auto" mode the SOV is open whenever 1-LW-PCV-115 is not fully closed thus allowing discharge effluent to the manual regulating valve 1-LW-1130.2.The control system is fed from the process control cabinet, which is fed from the nonvital bus. The SOV is fed from 120V ac Waste Disposal Building distri bution panel, which in turn is fed from Motor Control Center (MCC) 1B1-1A.
Operating Procedures require system flow to be maintained between the specified range, so that a proportional sample is provided. If reduced flow is required, hold-up capacity is provided, such that sufficient volume to provide the required flow, can be obtained by stopping flow for a period of time.
The instrumentation of the continuous sampli ng system is calibrated and checked every 18 months. Periodic cl arifier samples that are ta ken act as a chec k on this monitor and are also used to determine demineralization requirements. Radioactive co ncentrations in the clarifier samples normally will be lower than 10
-6 µCi/ml.The sampling program is ba sed on gamma counting, using a multi-channel spectral analyzer.A sample is taken from the tank to be potentially dischar ged. The tank is recirculated before sampling to ensure a representative sample. Part of the sample is then analyzed. If measured activity permits, the tank is then discharged, and an amount of the sa mple proportional to the volume discharged is transfer red to a weekly and/or monthly composite for future isotopic analyses for effluent release reporting.
If a multi-channel spectral analyzer is not available, a gross gamma counter can be used to assess the beta-gamma activity of the waste stream be ing dischar ged. The gr oss gamma counter is periodically calibrated. The mi nimum sensitivity of the gamm a counter is approximately Revision 52-09/29/2016 NAPS UFSAR 11.4-15 10-6 µCi/ml. Isotopic analysis empl oys a high-resolution gamma spectrometer, supplemented with radiochemical separation and analysis if required. Analytical sensitivities are approximately 50 pCi per nuclide per sample.
Gross beta-gamma counting of waste samples typically has a sensitivity of approximately 10 pCi per sample.
Calculated levels of activity in the liquid waste disposal system, assuming the conditions presented in Section 11.1, are presented in Section 11.2.5. Surveillance requirements for the liquid waste sampling and monito ring system are contained in the Offsite Dose Calculation Manual (ODCM).11.4.4.2 Gaseous SystemsWaste gas decay tanks and the containments are sampled befo re discharge or purging, and an isotopic analysis is made using a high-resolution gamma detector such as germanium. All significant peaks are identified and quantified. A tritium determination is made for all containment purges and waste gas decay tank releases.
Sampling of the containment atmosphere fo r purging data is pe rformed inside the containment vessel using particulate and charcoal filters with known flow rates. Tritium vapors are collected and analyzed usin g liquid scintillation. Known volume s of gases are collected in thin-walled containers and gamma-counted directly.Local sample points are availa ble on waste gas decay tanks, wh ich allows the passing of known volumes through fil ters fo r laboratory analysis. Gas sa mples are collected in small sampling vessels so that appropriate volumes can be tested for the noble gases.Ventilation exhausts are monito red by gas and particulate monitors as described in Sections 11.4.2 , and 11.4.3. In addition, area monitors are used, as described in Section 12.1.4 , to monitor radiation levels in sel ected portions of the station. In addition, health physics personnel routinely take air samples in vent ilated areas of the station where airborne activity could exist and be discharged to the environment through the ventilation systems. Isotopic analyses of these air samples are performed.Measured concentrations of gaseous activity, especially in the reactor containments and waste gas decay tanks, are expected to fluctuate over a wide range.
Maximum expected levels of airborne ac tivity in the station are presented in Section 12.2.3; the original estimates of the maximum expected levels of radioactivity in the waste gas decay tanks are presented in Section 11.3.5. Should measured values of airborne activity show an unexpected increase to or above levels that could potentially cau se a violation of the Of fsite Dose Calculation Manual (ODCM) limits, measures will be taken, as requi red, to identify the cause of the increase and to reduce the amount of radioact ivity released. Should ai rborne activity exceed limiting values in areas of the st ation not being ventilated, radiat ion control procedures will be implemented as required by the ODCM.
Revision 52-09/29/2016 NAPS UFSAR 11.4-16Surveillance requirements for gaseous waste sampling and monitoring are contained in the ODC M.11.4.5 Calibration and MaintenanceChannel checks, channel operational tests, and channel ca librations are specified in the ODCM.The channel check uses an installed check s ource that can be remo tely positioned from the control room. Fo r the MGP Instruments monitors on the ef fluent gas channels, their local processing units (LPUs) perform various self-checks automatically. Their electrical self-check introduces a known and fixed level of pulses into the electronics excluding the detector and verifies that the respons e is correct or a faul t is generated. Additionally, the electronics continuously monitor the detector for a minimum count rate otherw ise a fault alarm is generated.
The channel operational test is used to verify th e functionality of alarms and, when applicable, the functionality of automatic functi ons. The channel calibration uses a test source to observe the response of the detector and related components.11.4 REFERENCE DRAWINGSThe list of Station Drawings below is provided fo r information only. The referenced drawings are not part of the UFSAR. This is not intended to be a complete listing of all Station Drawings referenced from this section of the UFSAR. The contents of St ation Drawings are controlled by station procedure.
Drawing Number Description 1.11715-FM-097BFlow/Valve Operating Number s Diagram: Gaseous Waste Disposal System, Unit 1
Revision 52-09/29/2016 NAPS UFSAR 11.4-17Table 11.4-1 PROCESS AND EFFLUENT RADIATION MONITORING SYSTEM a NORMAL OPERATIONMonitorNo.Type of DetectorMedium Relevant Isotopes Sensitivity
(µCi/cc)Minimum Range (decades)Maximum Area Background (mrem/hr)Process vent particulate (1-GW-RM-178-1)1Silicon diodeGas, airI-1315 x 10-10 (I-131)30.75 Process vent gas (1-GW-RM-178-1)1Silicon diodeGas, airXe-133, Kr-855 x 10-5 (Kr-85)40.75Ventilation vent A particulate (1-VG-RM-179-1)1Silicon diodeAirI-1315 x 10-10 (I-131)30.75Ventilation vent A gas (1-VG-RM-179-1)1Silicon diodeAirXe-133, Kr-855 x 10-6 (Kr-85)30.75Ventilation vent B particulate (1-VG-RM-180-1)1Silicon diodeAirCo-60, Cs-1375 x 10-10 (I-131)30.75Ventilation vent B gas (1-VG-RM-180-1)1Silicon diodeAirXe-133, Kr-855 x 10-6 (Kr-85)30.75Ventilation vent multiport sampler particulate (1-VG-RM-105)1Gamma scintillatorAirI-1315 x 10-10 (I-131)30.75Ventilation vent multiport sampler gas (1-VG-RM-106)1Geiger-MuellerAirXe-133, Kr-855 x 10-6 (Kr-85)30.75 Containment particulate b (1/2-RM-RMS-159/259)2Gamma scintillatorAirI-1315 x 10-10 (I-131)30.75a.This table contains information based on the requirements for the various specifications for the listed monitors. The actual monitors meet or exceed these requirements.b.Also have local readout and alarm.
Revision 52-09/29/2016 NAPS UFSAR 11.4-18 Containment gas b (1/2-RM-RMS-160/260)2Geiger-Mueller tubeAirXe-133, Kr-855 x 10-6 (Kr-85)30.75 Component cooling water (1-CC-RM-120)1Gamma scintillatorWaterCo-60, Cs-1371 x 10-5 (Cs-137)30.75 Component cooling heat exchanger service water (1-SW-RM-107)1Gamma scintillatorWaterCo-60, Cs-1371 x 10-5 (Cs-137)30.75Service-water discharge to
tunnel (1-SW-RM-108)1Gamma scintillatorWaterCo-60, Cs-1371 x 10-5 (Cs-137)30.75Service-water discharge to Service-Water Reservoir b (1-SW-RM-109)1Gamma scintillatorWaterCo-60, Cs-137, I-131 1 x 10-6 (Cs-137)5100.0Recirculating spray cooler
service water (1/2-SW-RM-124/224, 125/225, 126/226, 127/227)8Gamma scintillatorWaterCo-60, Cs-1373 x 10-4 (Cs-137)25.0 Liquid waste disposal b (1-LW-RM-110,111)2Gamma scintillatorWaterCo-60, Cs-137, I-131 1 x 10-6 (Cs-137)40.75 Condenser air ejector (1/2-SV-RM-121/221)2Geiger-Mueller tubeVaporXe-133, Kr-853 x 10-3 (Kr-85)30.75Table 11.4-1 (continued)PROCESS AND EFFLUENT RADIATION MONITORING SYSTEM a NORMAL OPERATIONMonitorNo.Type of DetectorMedium Relevant Isotopes Sensitivity
(µCi/cc)Minimum Range (decades)Maximum Area Background (mrem/hr)a.This table contains information based on the requirements for the various specifications for the listed monitors. The actual monitors meet or exceed these requirements.b.Also have local readout and alarm.
Revision 52-09/29/2016 NAPS UFSAR 11.4-19Steam generator blowdown b (1/2-SS-RM-122/222, 123/223, 124/224)6Gamma scintillatorWaterCo-60, Cs-1374 x 10-6 (Cs-137)30.75 Reactor coolant letdown b (1/2-CH-RM-128/228)2Geiger-Mueller tubeWatermixed fission products 2 x 10 14200Circulating-water discharge
tunnel (1/2-SW-RM-130/230)2Gamma scintillatorWaterCo-60, Cs-1372 x 10-7 (Cs-137)30.05 High capacity SG blowdown discharge monitor (1/2-SS-RM-125/225)2Gamma scintillatorWaterCo-60, Cs-1371 x 10-6 (Cs-137)40.05Table 11.4-1 (continued)PROCESS AND EFFLUENT RADIATION MONITORING SYSTEM a NORMAL OPERATIONMonitorNo.Type of DetectorMedium Relevant Isotopes Sensitivity
(µCi/cc)Minimum Range (decades)Maximum Area Background (mrem/hr)a.This table contains information based on the requirements for the various specifications for the listed monitors. The actual monitors meet or exceed these requirements.b.Also have local readout and alarm.
Revision 52-09/29/2016 NAPS UFSAR 11.4-20Table 11.4-2 PROCESS RADIATION MONITORING SYSTEM COUNT ING RATES OF RELEVANT ISOTOPES (cpm/Ci/cc)MonitorI-131Xe-133Kr-85Cs-137Co-60 Process vent particulate a1.04E+9--1.15E+9-Process vent gas b-1.17E-62.92E -Ventilation vent A particulate a1.04E+9--1.15E+9-Ventilation vent A gas b-1.17E-62.92E -Ventilation vent B particulate a1.04E+9--1.15E+97.10E+8Ventilation vent B gas b--2.92E-6--Ventilation vent multiport sample, particulate1.7E+12-
-1.5E+12-Ventilation vent multipor t sample, gas
-1.9E+63.5E+7-
-Containment particulate1.7E+12--1.5E+12-Containment gas
-1.9E+63.5E+7-
-Component-cooling water2.5E+6--2.2E+65.2E+6 Component-cooling heat exchanger service water2.5E+6-
-2.2E+65.2E+6Service-water discharge to tunnel2.5E+6--2.2E+65.2E+6Service-water discharge to Service Water Reservoir1.1E+8-
-7.7E+71.7E+8 Liquid waste disposal2.5E+6--2.2E+65.2E+6 Condenser air ejector
-4.00E+21.16E+4-
-Steam generator blowdown2.5E+6--2.2E+65.2E+6 Recirculating spray cooler2.5E+6--2.2E+65.2E+6 Circulating-water discharge tunnel5.6E+8--5.0E+81.2E+9High-capacity SG blowdown discharge
---6.8E+81.8E+9a.These counting rates are in cps/
µCi/cc from the particulate monitor Monte Carlo Analysis Report.b.These counting rates are in cps/Bq/m 3 from the noble gas monitor Monte Carlo Analysis Report.
Revision 52-09/29/2016 NAPS UFSAR 11.4-21Table 11.4-3POST-ACCIDENT RADIATION MONITORING SYSTEM NORMAL AND HIGH-RANGE NOBLE GAS EFFLUENT MONITORS (PER NUREG-0737, SECTION II.F.1)Normal-Range Noble Gas Effluent Monitors Process Vent (1-GW-RM-178-1)Ventilation Vent A (1-VG-RM-179-1)Ventilation Vent B (1-VG-RM-180-1)High Range Noble Gas Effluent MonitorsProcess Vent (1-GW-RM-178-2)
Ventilation Vent A (1-VG-RM-179-2)Ventilation Vent B (1-VG-RM-180-2)Table 11.4-4POST-ACCIDENT RADIATION MO NITORING SYSTEM HIGH-RANGE EF FLUENT MONITORS (PER NUREG-0578, SECTION 2.1.8.B)Main Steam Lines (in Main Steam Valve House) 1A (1-MS-RM-170)
1B (1-MS-RM-171)
1C (1-MS-RM-172) 2A (2-MS-RM-270) 2B (2-MS-RM-271) 2C (2-MS-RM-272)Auxiliary Feedwater Turbine Exhaust (1-MS-RM-176) (2-MS-RM-276)
Revision 52-09/29/2016 NAPS UFSAR 11.4-22 Intentionally Blank Revision 52-09/29/2016 NAPS UFSAR 11.5-111.5 SOLID WASTE SYSTEMThe estimated solid waste volumes were based on typical industry assumptions and experience for nuclear power plants available at the time of original plant licensing. These assumptions and estimates were developed to dem onstrate the ability of the plant design to accommodate and dispose of solid radioactive waste. These assump tions were intended to be representative of the plant operation. In some instances, this is not the case since various system process parameters have proven to be different from the initial assumptions and estimated values. These original estimates represente d the basis for demonstrating the ability to properly dispose of this waste in accordance with the NRC requirements in the original licensing basis. Adherence to the solid waste disposal requirements is monitored by procedures in accordance with the approved Process Control Program (PCP).
As originally designed, the wa ste solidification system us ed urea formaldehyde as a solidification agent, as did numerous other nuclear plants such as Trojan and Palisades. However, experience throughout the industry has demonstrated that this system needs further development to assure reliable solidificat ion, elimination of free water, and no unacceptable leaching. Consequently, the system is not used. Waste is now being processed for shipment by dewatering
and shipment in high-integrity cont ainers, or steel liners. Final sh ipment preparati ons (inspection, health physics approval, etc.) remain the responsibility of VEPCO.The following discussion describes the basic pr ocedures for dispos ing of various types of waste, all within regulations of the NRC, the Department of Transporta tion, and the receiving burial site.11.5.1 Design Objectives The solid waste disposal system provides hol dup, packaging, and storage facilities for the eventual shipment off the site and the ultimate di sposal of radioactive wa ste. Materials that may be handled as solid waste incl ude spent resin slurries; spent filter cartridges; and other miscellaneous solid radioactive material re sulting from station operation and maintenance.
11.5.2 System Inputs The solid waste handling ope rations are described in Section 11.5.3. The volume activity level estimated for each of these streams is shown on Figures 11.5-1 and 11.5-2.11.5.2.1 Spent Resins The spent resin system is shown on Reference Drawing
- 3. It was originally estimated that 1500 ft 3/yr/unit of resin would require disposal based on th e original plant system design. This material will be transferred as sl urry to be dewatered and shippe d, in disposal containers, which are placed in shielded shipping casks as required, for offsite shipping and disposal. The shielded shipping casks are generally reused.
Revision 52-09/29/2016 NAPS UFSAR 11.5-211.5.2.2 Evaporator Bottoms The liquid waste bottom piping is shown on Reference Drawing
- 2. The waste disposal evaporator is abandoned in place.
The boron recovery bottom piping is shown on Figure 9.3-6 and Reference Drawing 1.11.5.2.3 Clarifier Sludge The clarifiers are no longer operated in a manner which generates sludge. They serve only as hold-up tanks to provide additional decay time.11.5.2.4 Miscellaneous Solid Waste Rags, gloves, boots, brooms, filter cartridges, and other miscellaneous t ools and apparel that become contaminated during no rmal operation and cleanup will be handled as described in Section 11.5.3; original estimates indicated the amount may be approximately 1500 ft 3/yr/unit.
Original estimates also indicated that spent f ilters may be changed at expected rates of 175 ft 3/yr/unit. Those filters that are highly radioactive will be processed as described in Section 11.5.3.4.11.5.3 Equipment and OperationTable 11.5-1 presents a summary of the design pa rameters for the equipment. When solidification operations are nece ssary, acceptable vendors supply th is service which must adhere to the requirements of the Process Control Program.11.5.3.1 Solidification Operation It is not expected that solid ification will be used on-site. If solidification operations are necessary, acceptable vendors supply this service as stated in Section 11.5.3.11.5.3.2 Baling Operation Compaction/baling of dry active waste (DAW), such as absorbent paper, cloth, rubber, and plastic items, was originally us ed to volume reduce waste. Baling operat ions are no longer performed at North Anna. The processing of DAW for volume reduction prior to disposal is performed of fsite by approved vendors.11.5.3.3 Spent Resin Handling Operation Spent resin facilities are locat ed below grade in the decontam ination building. This portion of the decontamination building is designed to Seismic Class I criteria.
A shielded resin holdup tank accumulates spen t resin from ion exch angers. A transfer system permits the spent resin to be flushed from the hold tank to be dewatered and shipped.The resin in an ion exchanger is cons idered to be spent wh en the decontamination factor drops below a predetermined value, the dose rate on the outside of the ion exchanger approaches a Revision 52-09/29/2016 NAPS UFSAR 11.5-3predetermined value, or the pr essure drop across the ion excha nger becomes excessive. The unit is then is olated and primary-grade water or recycled resin flush water is used to flush the spent resin into the spent resin hold up tank. The spent resin remains in the holdup tank and flushed liquid passes through a filter and discharges by way of the spent resin dewa tering tank and the vent and drain system to one of the waste drain tanks.
There is no significant temperature increase in the spent resin holdup tank due to decay heat. A conservative analysis show s that the maximum conceivable temperature rise in the resin is 45°F.11.5.3.4 Spent Filter Cartridge Hand ling Operation Filters in radioactive liquid se rv ice are removed from service wh en the pressure drop across the filter becomes excessive or the radiation le vel approaches the tran sport cask shielding capabilities. To remove the expe nded cartridges from filters that are located in limited access, shielded cubicles, the filter removal shield is positioned on the shield floor over the filter vessel after removal of the shield plug.
The filter cover is opened remote ly and the cartr idges are drawn up into the shield. The spent filter and shield are transferred to the waste solids area. The spent filter is lowered into a shielded disposable container (High Integrity Container - HIC) in preparation for disposal. Filter s located in limited access, shielded cubicles, that present a low radiological risk, may be removed without use of the filter remova l shield prior to being lowered into a disposal container in preparation for disposal. Filters that present a low radiological risk are defined based on ALARA considerat ions and described in the provi sions of specific procedures.
Other filters that are not located in limited access, shield ed cubicl es, are removed without the use of the filter removal shield. These filters are removed and transported to Waste Solids under the provisions of specific proc edures and ALARA considerations.11.5.4 Estimated Volumes Estimated design volumes of solid waste are given in Section 11.5.2. The total amount of waste (originally estimated at th e time of plant licensing) to be processed by the system in one year is shown in Figure 11.5-1. The design quantities of waste and the content of this waste (in microcuries per cubic ce ntimeter) are shown on Figure 11.5-2. The specific is otope breakdown within any one container cannot be ascertained.
However, the isotope breakdown over a year's operation for a given set of condi tions can be de termined. The curies wi thin any one container will comply with radioactive material transporta tion regulations. The design total curies per year by isotope to the solid waste system fr om the station sources is shown in Table 11.5-2.Design was based on the following assumptions:1.Failed fuel is at 1%.2.Source activity is the prim ary coolant activity per Table 11.1-6. This activity is collected on the mixed-bed demineralizers for 1 year.
Revision 52-09/29/2016 NAPS UFSAR 11.5-43.The flow rate to the mi xed-bed demineralizer is 60 gpm.4.Collection efficiencies for this demineralizer are as follows:a.Twenty percent for corrosion products.b.Eighty percent for cesium.c.Ninety percent for molybdenum and yttrium.d.Zero percent for n oble gases and tritium.e.Ninety-nine percent for all other isotopes.5.Decay credit is taken for th e buildup time on the resin bed.6.No decay credit is taken for holdup in the resin hold tank, the waste solidification system, or the solid waste storage area.7.The total activity is based on the assumption that all resins are at the same concentration as those in the mixed-bed demineralizer
.11.5.5 Packaging Material handled as radioactiv e solid waste may include spent resin, spent filter cartridges, sludges, and miscellaneous solid materials result ing from station operation and maintenance, such as contaminated rags, paper, and equipment parts.
For ultimate disposal, these wastes are packaged and sh ipped of f the site to approved radwaste processors. These pro cessors minimize the amount of waste prior to shipment to specifically approved burial grounds. The packaging meets all applicable NRC and U.S. Department of Transporta tion (DOT) regulations (10 CFR 71 and 49 CFR 170 through 179) for transportation of radioactive materials.Originally, all waste was to be pack aged in either 55-gallon drums (7.5 ft 3) or in cylindrical containers of 50-ft 3 capacity. However, various types of strong tight cont ainers of varying shapes and capacities are currently available for use. Containers vary from large seavans to the original 55-gallon drum containers. The choice of container size depends on the type, size and shape, radioactivity, etc., of the waste. The total quantity of waste to be shipped in the containers is a function of the ratio of materials, the waste activity, and the shippi ng shield to be used to meet transportation regulations.
VEPCO contracts for waste dis posal transportation and buria l services. Since there are variations in overpacks between contractors, specific details of their construction are not incorporated herein. These details of construction, packing, and permissible levels of activity, and a copy of required special permit for overpacks, are maintained on file by VEPCO. VEPCO uses only approved containers for sh ipment, in accordance with th e requirements of applicable regulations.
Revision 52-09/29/2016 NAPS UFSAR 11.5-5The radioactivity level on contact with the surface of the disposal liner or shipping shield is measured, recorded, and attached to the outside surface in accordance with applicable Federal regulations. The shipping containers are stored until such time as they are shipped off the site for ultimate disposal.11.5.6 Shipment The normal mode of shipment of ra dioactive wastes from the North Anna Power Stations is by truck; however, shipment by rail is also po ssible. All shipments will conform to applicable DOT and NRC regulations.
The ultimate solid waste dis posal site is dependent on sp ecific contract requirements formulated for waste disposal.11.5 REFERENCE DRAWINGSThe list of Station Drawings below is provided fo r information only. The referenced drawings are not part of the UFSAR. This is not intended to be a complete listing of all Station Drawings referenced from this section of the UFSAR. The contents of St ation Drawings are controlled by station procedure.
Drawing Number Description 1.11715-FM-086BFlow/Valve Operating Number s Diagram: Boron Recovery System, Unit 1 2.11715-FM-087AFlow/Valve Operating Number s Diagram: Waste Disposal System, Unit 1 3.11715-FM-087DFlow/Valve Operating Number s Diagram: Waste Disposal System, Unit 1 Revision 52-09/29/2016 NAPS UFSAR 11.5-6Table 11.5-1 SOLID WASTE DISPOSAL EQUIPMENT DESIGN DATASpent Resin Holdup Tank Number 1Capacity 1800 gal Design pressure 90 psig and full vacuum Design temperature 250°F Operating pressure 50 psig Operating temperature 120°F Material SS 316L Design Code ASME VIII, Division 1, 1968Spent Resin Dewatering Tank Number 1Capacity 500 gal Design pressure 90 psig and full vacuum Design temperature 200°F Operating pressure Atmospheric Operating temperature 120°F Material SS 316L Design Code ASME VIII, Division 1, 1968Spent Resin Dewatering Tank Pump Number 1Type Horizontal centrifugalMotor horsepower 10 Seal type MechanicalCapacity 50 gpm Head at rated capacity 184 ft Design pressure 220 psig Materials Pump casing SS 316 Shaft SS 316Impeller SS 316Resin Recirculation Pump Number 1Type Centrifugal Seal type Double mechanicalMotor horsepower 7.5Capacity 70 gpm Head at rated capacity 50 ft Design pressure 100 psig Revision 52-09/29/2016 NAPS UFSAR 11.5-7Resin Recirculation Pump (continued)
Materials Pump casing SS 316 Shaft SS 316Impeller SS 316Radioactive Waste Metering Pump Number 1Type Centrifugal, Recessed Impeller Seal type MechanicalMotor horsepower 2.0Capacity 28 gpm Head at rated capacity 10 ft Design pressure 150 psig Materials Pump casing CD4Mcu Shaft DURCO DC8Impeller CD4McuTable 11.5-1 (continued)
SOLID WASTE DISPOSAL EQUIPMENT DESIGN DATA Revision 52-09/29/2016 NAPS UFSAR 11.5-8Table 11.5-2 SOLID WASTE ESTIMATESCuries per Year to Solid Waste System Principal IsotopesLiquid Waste Evaporator a , b Boron Recovery Evaporator a Ion Exchange Spent Resin a I-131 4.8+01 1.3+01 3.7+05 I-132 5.3+00 4.3-01 1.7+04 I-133 2.1+01 5.1-01 6.4+02 I-134 7.5-02 1.2-19 3.9+02 I-135 2.4+00 2.6-03 1.1+04Sr-89 4.2-01 1.0-01 3.5+03Sr-90 2.0-02 6.5-03 6.4+02Sr-91 3.4-02 1.7-05 1.4+01Y-90 2.0-02 6.5-05 6.4+02Y-91 7.1-01 1.8-01 6.2+03Y-92 4.8-04 2.2-08 3.3+00Zr-95 8.2-02 2.1-02 8.2+00 Nb-95 7.6-02 2.7-02 1.3+03Mo-99 8.7+02 6.9+00 2.5+05Tc-99 8.2+01 6.6+00 2.4+05Tel-32 5.0+00 4.2-01 1.6+04 Cs-134 3.6+01 1.2+01 8.6+05 Cs-136 9.7-01 4.8-02 2.8+02 Cs-137 1.8+02 6.2+01 4.5+05 Ba-140 2.8-01 3.7-02 1.0+03 La-140 2.9-01 4.4-02 1.0+03 Ce-144 4.3-02 1.4-02 1.0+03Cr-51 6.3+00 1.6-02 9.4+01Mn-54 1.7+01 3.1-02 4.8+02Mn-56 1.7-02 3.4-09 1.1+01 Co-58 1.3+01 7.4-01 6.2+03 Fe-59 2.4+02 2.5-02 1.7+02 Co-60 1.4+01 3.3+00 6.4+02a.Based on original evaporator/clarifier/UF system.b.Abandoned in-place.
Revision 52-09/29/2016 NAPS UFSAR 11.5-9Figure 11.5-1FLOW CHART-ESTIMATED QUANTITIES SOLID WASTE DISPOSAL SYSTEM-EXPECTED Revision 52-09/29/2016 NAPS UFSAR 11.5-10Figure 11.5-2FLOW CHART-ESTIMATED QUANTITIES SOLID WASTE DISPOSAL SYSTEM-DESIGN Revision 52-09/29/2016 NAPS UFSAR 11.6-111.6 OFFSITE RADIOLOGICAL MONITORING PROGRAM11.6.1 BackgroundActual background radiation and radioactivity levels in the environment surrounding the North Anna site were measured and recorded during the pr eoperational Environmental Radiological Monitoring Program , which commenced in early 1973. Analysis and periodic reports were done by Teledyne Isotopes. With the advent of power operations, an operational Radiological Environmental Monitoring Program (REMP) was instituted. These programs and their relationship are discussed in Section 11.6.3.11.6.2 Critical Pathways The pathways of human exposure from plant operation likely to account for most of the exposure, and the mathematical models used to evaluate these pathways, are given in Appendix 11B. In evaluating the effects of actual radioa ctive releases after the commencement of station operation, the math ematical models in Appendix 11B , or analogous models, are used.11.6.3 Sampling Media, Locations, and Frequency The environmental radiological monitoring sampling frequencies and sampling locations are presented in Table 11.6-1 and Figure 11.6-1 for the pre-operational stage of the monitoring program. The operational Radiologi cal Environmental Monitoring Program (REMP) is based on NUREG-0472 and the Branch T e chnical Position Revision 1, Acceptable Radiological Environmental Monitoring Program, and is implemented in the Offsite Dose Calculation Manual (ODCM). The pre-operational and operational monitoring program in corporates measurements to evaluate the possible effects from plant operation and ensure that changes in the environmental radioactivity can be detected.
Measurements obtained during station operation are compared with background data collected before station operation. The sensitiviti es of the various samp ling techniques and the sampling frequencies allow the dete ction of any changes in backgr ound levels that could possibly be attributed to station operation and that would be of si gnificance to the health and safety of the public. The pre-operational en vironmental radiological moni toring program commenced in February 1973.Periodically, the radiological e nvironmental monitoring program is evaluated for adequacy in light of program resu lts and changes in technology. Any necessary changes are incorporated into the program. Additional details on the pre-operational and opera tional radiological environmental monitoring program samples are given in the sections that follow.11.6.3.1 Air Monitoring - Radiogas and Air ParticulateNormally, during operational m onitoring, the gaseous wastes di schar ged from the station consist almost entirely of the noble gases, xenon and krypton. The radiati on hazard from these Revision 52-09/29/2016 NAPS UFSAR 11.6-2 gases, due to their inertness, is external exposur
- e. Radiation surveillance is maintained by using ther moluminescent dosimeters to measure total radiation levels in the station environs. The dosimeters are read periodically to optimize statistical sensitivity an d document seasonal fluctuations.
Continuous duty air particulate samplers mon itor airborne activity in accordance with the Offsite Dose Calculation Manual. These samples are indicative of radioactiv ity levels and reflect any transient conditions that may arise.11.6.3.2 MilkMilk is sampled in accordance wi th the Offsite Dose Calculation Manual. Milk is one of the best and most direct biosam plers for determining the radi ocesium, radiostrontium, and radioiodine levels in the environment. Since th e levels of radiostrontium and cesium are well below protection standard levels, and radioiodine was essentially nonexistent in the samples, the samples were adequate to establish bac kground levels and document future trends.
Milk continues to be sampled during the opera tional REMP. Milk samp les are obtained at a predetermined frequency from selected locations surr ounding the site.11.6.3.3 Vegetation, Crops, and FeedVegetation samples are collected during the preoperational envir onmental radiological monitoring program and continue to be collected during the oper ational REMP. They reflect the uptake of radionuc lides from the soil. However, the actual relationship of activity uptake to population doses is unpredictable because of the many variables involved.Under the REMP, crops (such as corn), feed (such as alfalfa), and/or edible broad leaf vegetation are collected during the growing seasons and can be used as indicators of potential increases in doses to humans through the food chain.11.6.3.4 Soil, Surface Water, and WellsThe pre-operational environmental radiological monitoring program samples reflected the radiological state of the environm ent. Gamma isotopic analysis of soil gives evidence of the original source of any increased contamination that may be found. These samples are intended as long-range indicators.11.6.3.5 PrecipitationDuring the environmental ra diological monitoring program, rainwater samples indicated widespread or global activity concentrations and were one method of detecting activity not attributable to station operation. Monthly samples were obtained during this period.
Rainwater continues to be sampled during the operationa l REMP. The frequency and location of the sampling is sufficient to keep the program current yet practical.
Revision 52-09/29/2016 NAPS UFSAR 11.6-311.6.3.6 Silt and Fish These samples (in addition to Lake Anna water samples) act as indicators in that they have the property to concentrate certain nuclides. One of the first signs of lake buildup of activity will be increased levels in fish.11.6.4 Analytical SensitivityDetails of sample analysis and detection capabil ity are given in the Of fsite Dose Calculation Manual and in the Annua l Radiological Environmental Opera ting Report. The determination of the activity levels of the samples collected in the REMP may be determined by forwarding the samples to a consultant.
During the initial year of the environmental radiological monitoring program the analyses was performed by a consultant. The equipment used by the consultant for the first year of the monitoring program is listed in Table 11.6-2. Similar equipment has been use d in the succeeding years.
11.6.5 Data Analysis and Presentation The results of the REMP samp ling program are summarized in quarterly and annual reports.
These reports include a professional evaluation of the results. Results are normally reported in tabular form and include 1 or 2 sigma counting error.Statistical analyses are performed on these sample s, such as air particulate, with sufficient data and/or levels above background radiati on levels to be stat istically meaningful.11.6.6 Program Statistical SensitivitySufficient background statistical data were obtained on air partic ulate samples, in the pre-operational monitoring program that was completed before the commencement of station operation. This, in conjunction with the selection and analysis of environmental samples known to concentrate radionuclides and ra dioassay of radioactive gaseous and liquid waste released from the station, will allow an estimate of the probable exposure to man from station operation.It is anticipated that the results obtained from the e nvironmental sa mpling program, together with source activity release data, will show relatively little or no increase in the background activity of the environs. Sections 11.2.5.1 and 11.3.8 discuss the anticipated release and dose potential in more detail.
Revision 52-09/29/2016 NAPS UFSAR 11.6-4Table 11.6-1 NORTH ANNA POWER STATIONRADIOLOGICAL MONITORING PROGRAM (PREOPERATIONAL)SampleStation No.TypeFrequencyAnalysisAir particulate1 through 7Continuous (2 hr on, 1 hr off)
Biweekly Quarterly Gross alpha, gross beta Isotopic gamma scan (composite)
Iodine-131 (charc oal cartridges)Radiogas1 through 7ContinuousQuarterlyMrem exposureMilk12 through 15GrabQuarterlySr-90, Cs-137, I-131, total Ca isotopic gamma scanFish8 through 10GrabQuarterlyFlesh gross beta, and K-40 isotopic gamma scan, Sr-89, Sr-90Surface water8 through 11GrabQuarterlyGross betaSemiannual H-3, isotopic gamma scan on quarterly compositesSoil1 through 7GrabAnnualIsotopic gamma scan Crop (corn)19 and 20GrabThree-year annual Isotopic gamma scan Sr-90 (on mature corn)Crop (leaf)13, 15, 18GrabSemiannualIsotopic gamma scan, Sr-89, Sr-90Wells1, 3, 16, 17GrabSemiannualGross al pha, gross beta, H-3 isotopic gamma scanVegetationAt 3 air particulate
monitoring stationsGrab3 per yearIsotopic gamma scan Aquatic vegetationTwo stations where and if availableGrabSemiannual annual composite Isotopic gamma scan Sr-89, Sr-90 Revision 52-09/29/2016 NAPS UFSAR 11.6-5Benthic organisms8 through 11 (if available)GrabQuarterly annual composite Isotopic gamma scan Sr-89, Sr-90Precipitation1ContinuousMonthlyGross betaSemiannualH-3, isotopic gamma scan on compositeSilt8 through 11GrabSemiannualIsotopic gamma scan, Sr-89, Sr-90Table 11.6-1 (continued)NORTH ANNA POWER STATIONRADIOLOGICAL MONITORING PROGRAM (PREOPERATIONAL)SampleStation No.TypeFrequencyAnalysis Revision 52-09/29/2016 NAPS UFSAR 11.6-6Table 11.6-2 NORTH ANNA POWER STATION ENVIRONMEN TAL RADIOLOGICAL MONITORING PROGRAM MEASURING EQUIPMENT, MARCH 1973 TO MARCH 1974 Equipment RemarksGamma spectrometry Consists of 4096 multichannel analyzer equipped with a nuclear diodes soli d-state Ge(Li) detector having 2.34-keV resolution, a peak to Compton ratio of 22.1, and a relative ef ficiency at 1.33 MeV of 4.3%. Equipped with teletype and punch tape readout as well as x-y recorder spectrum representation capability.Gamma spectrometry system Nuclear Data Computer based type system with a
solid-state Ge(Li) detector having 2.34-keV resolution. System equipped with ND812 computer , teletype, and punch tape re adout as well as x-y recorder spectrum representation capability.
Alpha spectrometry systemConsists of silicon surf ace barrier detectors with 30-keV resolution coupled to a pulse height analyzer with teletype and x-y readout.Liquid scintillation systemHas 65% tritium efficiency and 90% carbon-14 efficiency.Gross alpha counting system Consists of two windowless gas flow detectors with an alpha ef ficiency of 55% with a background of less than 0.1 cpm.
Low background gas proportional Beckman wide beta II (2-inch planchet) counting system Has 2.5 cpm beta background and 0.1 cpm alpha background Low beta gas proportional (1-inch
planchet) counting system Has 0.5 cpm beta background and detector
ef ficiency of 50% for strontium-90.
Revision 52-09/29/2016 NAPS UFSAR 11.6-7Figure 11.6-1 PREOPERATIONAL RADIOL OGICAL ENVIRONMENTAL SAMPLING PROGRAM SAMPLE STATION LOCATIONS Revision 52-09/29/2016 NAPS UFSAR 11.6-8 Intentionally Blank Revision 52-09/29/2016 NAPS UFSAR 11A-iAppendix 11ATritium Control Revision 52-09/29/2016 NAPS UFSAR 11A-ii Intentionally Blank Revision 52-09/29/2016 NAPS UFSAR 11A-1 APPENDIX 11A TRITIUM CONTROL The release of tritium to the environment from operating Westinghouse pressurized water reactors (PWR) has alwa ys been well below 10 CFR 20 limits. This section discusses the reduced tritium production in the North Anna plant as a result of employi ng Zirconium alloy-clad fuel and silver-indium-cadmium control rods.11A.1 SYSTEM SOURCES The principal contributors to tr itium production within the PWR system are: (1) the ternary fission source, (2) the dissolved boron in the reactor coolant, and (3) sec ondary source assemblies.
Additional small contri butions are made by Li 6 , Li 7, and deuterium in the reactor coolant. Tritium source terms used in the reactor system design are shown in Table 11A-1.11A.1.1 The Fission SourceThis tritium is formed within the fuel material and may:1.Remain in the fuel rod uranium matrix.2.Diffuse into the cladding and become hydrided and fixed there.
3.Diffuse through the clad for release into the reactor coolant.4.Release to the coolant through macroscopic cracks or failures in the fuel cladding.Previous Westinghouse designs have conservatively assumed that the ratio of fission tritium released into the coolant to the total fissi on tritium formed was approximately 30% for Zircaloy-clad fuel. The operating experience at the R. E. Ginna plant of the Rochester Gas and Electric Company, and at other operating reactors using Zircaloy-clad fuel, has shown that the tritium release through the Zircaloy fuel cladding is substantially le ss than predicted by the earlier estimates. Consequently, the release fraction has been revised downward from 30% to 1% on the basis of these data (Reference 1). Like Zircaloy, ZI RLO and M5 are about 98% Zirconium, so their properties relative to tritium release are not expected to differ si gnificantly from Zircaloy (References 2 & 3).The control rods for this plan t are silver-indium-cadmium. There are no reactions in these absorber materials that would pr oduce tritium, thus eliminating a ny contribution from this source.11A.1.2 Boric Acid Source A direct contribution to the reactor cool ant tritium concentration is made by neutron reaction with the boron in solution. Th e concentration of boric acid va ries with core life so that this is a steadily decreasing s ource during core life. The prin cipal boron reactions are the B 10 (n, 2) H 3 and B 10 (n, ) Li 7 (n, ) H 3 reactions.
Revision 52-09/29/2016 NAPS UFSAR 11A-2 The Li 7 reaction is controlled by limiting the maximum overall lithium concentration. Li 6 is essentially excluded from the system by using Li enriched to 99.9% Li 7.11A.1.3 Secondary Source Assemblies In a Secondary Source rod, the primary source of tritium generation is the irradiation of Beryllium. The neutron reactions that result in the production of tritium are:
Be 9 (n, ) He 6 () Li 6 (n, ) T Be 9 (n, ) Be 10 (n) Li 8 + T Be 9 (n) Li 7 + T Li 7 (n, n ) TOf the above reactions, the first reaction is the primary source of tritium production from the sources. The permeability of the secondary source pellets and cladding (stainless steel) to tritium is high. Secondary sources we re not explicitly analyzed as a source of tritium in the reactor for the original plant design and are therefore not described in Table 11A-1. As stated in Section 11A.1.1 , conservative assumptions regarding the releas e of tritium from the fuel were made in the original analyses. The original anal yses, with this assumpti on, account for potential tritium release from the source rods.11A.1.4 Burnable Poison Rod Source Burnable poison rods were in the core during the first operating cycle and during subsequent cycles. Because the poison is fully encapsulated in se aled rods, the burnable poisons do not contribute significant amount s of tritium to the coolant.11A.1.5 Minor Sources Lithium and deuterium reactions contribute onl y minor quantities to the tritium inventory.11A.2 DESIGN BASESThe design intent is to reduce the tritium sources in the reactor coolant system to a practical minimum. The reduction of so urce terms is provided by using silver-indium-cadmium control rods and the determination that th e quantity of tritium released from the fuel rods with Zirconium alloy cladding is less than originally expected.11A.3 DESIGN EVALUATIONTable 11A-1 is a comparison of a typical design-ba sis tritium production that was used to establish system and operational requirements of the plant, as we ll as expected tritium release values. The criteria used for de sign basis accidents (DBA) retain their original definitions based Revision 52-09/29/2016 NAPS UFSAR 11A-3 on the old 10 CFR 20 and therefore DBA analyses do not need to be recalculated based on the criteria of the revised 10 CFR 20 rule. (
Reference:
First Set of NRC Question/Answer
- 14.) The principal contributors to tritium production are: (1) the tern ary fission source, (2) the dissolved boron in the reactor coolant, and (3) secondary source assemblies.Because of the importance of this source on the operation of the plant, Westinghouse initially closely foll owed operating plant data for cores with Zircaloy-clad fuel. Furthermore, a program was conducted at the R. E. Gi nna plant to follow this in detail.The R. E. Ginna plant operated with a Zir caloy-clad core with silver-indium-cadmium control rods and primary and secondary source assemblies. Th e operating levels of boron concentration during the st art-up of the plant were approximately 1100 to 1200 ppm of boron. In addition, burnable poison rods in the core contain boron that may contribute some tritium to the coolant. Data collected during th e operation of the plant indicate d very clearly that the design sources were conservative. The tritium released was essentially from the boron dissolved in the coolant, a ternary fission source, and the installe d source assemblies. Less than 10% of the tritium was from ternary fission. In ad dition to the R. E. Ginna data, other operating plants with Zirconium alloy-clad cores have also reported very low tritium concentrations in the reactor coolant system after considerably longer operation.For a leakage from the reacto r coolant system into the r eactor building atmosphere of 50 lb/day with an assumed tritium concentration of 3.5
µCi/g, the tritium concentration in the reactor building atmosphere woul d be low enough to permit access with no reactor building purge and without protective equipm ent by plant maintenance pers onnel for an average of 2 hr/week.During refueling operations, a refueli ng wa ter concentration activity of 2.5
µCi/g is expected to result in reactor building air concentrations at or below the 10 CFR 20 occupational maximum permissible concentration (M PC) value. This concentration would permit 40 hr/week access to the reactor building.
Although the actual relationship between reactor coolant activities and reactor building air concentrations will be determin ed by the particular operating conditions inside the reactor building (temperature, relative humid ity, ventilation purge rate, etc.
), field measurements indicate that the design objective of 3.5
µCi/g in the reactor coolant and 2.5
µCi/g in the refueling water are reasonable values.The concentration of tritium in the reactor coolant system can be controlled by the release of tritium to the environment vi a the boron recovery and waste disposal systems as discussed in Section 11.2.5. Since containment tritium concentration during normal operati on is a function of reactor coolant tritium concentrat ion, the tritium concentration in the containment can also be controlled. Controlling this concentration to twice the MPC value requires the release of 680,000 gal/yr for both units vi a the boron recovery syst em to discharge the 1065 Ci of tritium Revision 52-09/29/2016 NAPS UFSAR 11A-4 produced. During refueling, the tritium concentration in th e containment atmosphere is maintained at a safe level by the containment pur ge system.Since there is no forced mixing between the wate r in the reactor refueling cavity and in the spent-fuel pit, evaporative tritium losses from the spent-fuel pit will be minimal.Based on the above, the following conclusions were reached:1.The tritium levels in plants operating with Zi rconium alloy-clad cores are substantially lower than original design predictions.2.The tritium source in the plants is reduced from the values in the original design analysis by using silver-indium-cad mium control rods.
Revision 52-09/29/2016 NAPS UFSAR 11A-511A REFERENCES 1.Source Term Data for Westinghouse Pressurized Water Reactors , WCAP-8253, Revision 1, July 1975.2.Davidson, S. L. and Nuhfer, D. L. (Eds.), VANTAGE+ Fuel Assembly Reference Core Report , WCAP-12610-P-A, April 1995.3.BAW-10227P-A, Evaluation of Advanced Cladding and S t ructural Material (M5) in PWR Reactor Fuel, February 2000.
Revision 52-09/29/2016 NAPS UFSAR 11A-6Table 11A-1TRITIUM SOURCE TERMS FOR SYSTEM DESIGN aTritium SourceTotal Produced (Ci/yr)
Expected Release to Reactor Coolant (Ci/yr)Ternary fission 8560 856 Burnable poison rods (initial cycle) b 631 63 Soluble boron (initial cycle)
(equilibrium cycle) 195 250 195 250 Lithium and deuterium
reactions 86 86Total initial cycle 9472 1200Total equilibrium cycle 88961190a.Tritium source terms were calculated using the following bases:Power level2900 MWt Load factor0.8Release fraction from fuel10%Release fraction from burnable poison rods10%Burnable poison rod B-10 mass2374g Reactor coolant boron con centration (initial cycle)860 ppm Reactor coolant boron concen tration (equilibrium cycle)1100 ppm b.Although these system design values assumed that burnable poisons would be used only in the initial operat
-ing cycle, in practice burnable absorbers have also been used in reload cycles at North Anna. As discussed in Sections 11A.1.4 and 11A.3, it has since been determ ined that the burnable poison rods do not significantly contribute to reactor coolant system (RCS) tritium levels, and that tritium production in general is well below the equilibrium cycle design values shown.
Revision 52-09/29/2016 NAPS UFSAR 11B-i Appendix 11BRadiation Exposure Evaluation fo r Estimated Radioactive Effluents Revision 52-09/29/2016 NAPS UFSAR 11B-ii Intentionally Blank Revision 52-09/29/2016 NAPS UFSAR 11B-1 APPENDIX 11B RADIATION EXPOSURE EVALUATION FORESTIMATED RADIOA CTIVE EFFLUENTS11B.1 INTRODUCTION Units 1 and 2 of the North Anna Power Station ar e situated approxima tely midway between the cities of Washington, D.C., and Richmond, Virginia. The immediat e site area is characterized by its low population density and supports a mostly agricultural economy. The North Anna Reservoir is expected to be the focal point of recreational activitie s for a population within 50 miles of the site that is projected to total about 1,364,000 by the year 2000.
During normal operation, small quantities of radioactive liquids and gases will be dischar ged on a controlled basis to the environment. These discharges will be kept within the limits set by 10 CFR 20 and will be in conformance with th e Of fsite Dose Calculation Manual and applicable Technical Specifications that govern plant operations. It is the purpose of this section to quantify and evaluate the po tential radiological impact of these releases. The evaluation considers maximum potential indivi dual radiation exposure rates as well as the total integrated population exposure within a 50-mile radius of the site. Exposure pa thways considered include all known significant envir onmental and biological mechanisms through which activity released from the station could conceivably reach the public. Figure 11B-1 illustrates those exposure pathways of greatest significa nce for central stat ion nuclear generati ng plants such as North Anna. Table 11B-1 gives the distance from the Unit 1 containment to the location of various pathways, including milk cows, meat an imals, milk goats, the nearest residences, vegetable gardens, and the nearest site boundary
.Since the applicable regulations are based on a consideration of average annual dose, this study is directed at determining the doses averaged over a ye ar. The estimated doses to individuals and population are compared to existing and proposed dose guidelines, to normal background radiation doses, and to other ordinarily acceptable radiation exposure levels.Throughout this section, many assumptions have been made b ecause of the lack of more precise knowledge. In each case, an attempt has been made to ensu re that, whatever assumptions are made, they tend to overestimate the resulting exposure. In many instances, the numerical results presented do not reflect an accurate result, but rather an upper limit, a maximum potential dose.11B.2
SUMMARY
AND CONCLUSIONS This appendix evaluates the maximum expected radiation exposure to the general public or to individuals thereof resulti ng from the operation of North Anna Units 1 and 2, for cores using a Revision 52-09/29/2016 NAPS UFSAR 11B-2 15 x 15 fuel assembly array. The qua ntities of the various radioisot opes released from the station in gaseous or liquid form we re obtained from an assumed combination of plant operating conditions that would provide maximum expected annual average releases. These assumptions included significant fuel cladding failure and various system leakages in each unit. In addition, conservative environmental dilution and concentration factors have been used so that the annual average doses calculated in this appendix are the maximum values that could reasonably be expected to occur during the normal operation of North Anna Units 1 and 2.All incremental human exposure levels re sulting fr om the combined operation of North Anna Units 1 and 2 have been found to be within the normally accepted levels of radiation exp osure.11B.2.1 Maximum Individual Exposure Of all the exposure pathways considered, the greatest potential whole-body exposure results from the external irradiation of an individual at the exclusion radius from th e released noble gases, krypton and xenon. The maximum potential dose from the source is calculated to be 0.62 mrem/yr. To derive this entire dose, an individual would have to continually remain outdoors at a particular position at the exclusion radius in an unshielded condition. An adult so situated
would also receive a thyr oid inhalation dose of 0.070 mrem/yr from the released radioiodines.
If an individual were to depend continually and exclusively on the Waste Heat Treatment Facility for his source of potable water, he would receive an a nnual whole-body dose of 0.27 mrem. The associated maximum organ dose from this source is calculated to be 0.54 mrem/yr to the adult thyroid. If the water were obtained from the North Anna Reservoir, the whole-body dose would decrease slightly to 0.20 mrem/yr, while the thyr oid dose would decrease to 0.21 mrem/yr.If an adult individual were to eat an average of 50g daily of fish taken from the Waste Heat Treatment Facility, he would rece ive an annual whole-body dose of 1.9 mrem and a maximum or gan dose of 2.6 mrem to the liver. If the fish were obtained from the North Anna Reservoir, the whole-body dose woul d be reduced to 1.4 mrem/yr, and the maximu m organ dose would be reduced to 1.9 mrem/yr.In general, the maximum extern al exposure rates due to liquid releases are insignificant in comparison to maximum internal exposure rates due to the ingestion of wate r or fish. Swimming 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> in the Waste Heat Tr eatment Facility yields a whole-body dose of only 3.42 x 10-4 mrem. The skin dose is 4.38 x 10-4 mrem. Swimming 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> in the North Anna Reservoir yields reduced doses of 1.86 x 10-4 mrem to the whole body and 2.34 x 10-4 mrem to the skin. Exposure due to boating is based on an annual exposure period of 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> and amounts to 4.27 x 10-4 mrem/yr in the Waste Heat Treatment Facility and 2.33 x 10-4 mrem/yr in the reservoir
.
Revision 52-09/29/2016 NAPS UFSAR 11B-3 The highest potential external exposure due to liquid releases come s from sunbathing on beaches where the radioactivity may con centrate. An annual exposure period of 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> yields a conservatively calculated 0.061 mrem/yr based on concentrati ons inside the Waste Heat Treatment Facility. The dose rate from sunbathing 300 hr/yr in the much mo re likely locations along the North Anna Reservoir is 0.046 mrem/yr.A potentially significant exposur e pathway involves th e transfer of released radioiodines to milk, which is then ingested by a young child. Ga seous radioiodine releas es may be deposited on grass, ingested by a grazing co w, and subsequently secreted in commercially available milk supplies. The maximum dose from this source occurs if the receptor is a young child. Assuming no delay between production and consumption an d no dilution with other milk supplies, the potential annual thyroid dose from this source is calculated to be 1.21 mrem/yr for iodine dep osition at the nearest Grade A dairy farm.
If it were possible for an a dult individual to simultaneously receive the maximum exposure from all the above sources, he w ould receive a w hole-body dose of 2.8 mrem/yr and a maximum or gan dose of 3.5 mrem/yr to the liver. This includes th e maximum potential exposure from water ingestion, fish inge stion, swimming (200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />), boating (500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />), and sunbathing (300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />), as well as external exposur e from the released radiogases.
In comparison, the annual whole-body expos ure from naturally occurring background radiation in the United S tates is about 130 mrem (Reference 2). The maximum potential individual dose rates are also sma ll in comparison with other or dinary and acceptable individual radiation exposure levels.
The dose delivered to an individual from a single chest X-ray may be as much as 170 mrem (Reference 2). Wearing a particular kind of watch ma y yield an incrementa l annual whole-body dose of 4 mrem (Reference 2). The inhabitation of a stone or masonry dwel ling rather than a frame house has been calculated to yield an average addition al annual whole-body dose of 40 mrem and a maximum annual incr emental exposu re of over 500 mrem (Reference 3). Thus, the maximum potential incremen tal exposure to man from plan t-contributed radioactivity represents only a small fraction of exposure increments common to ordinary experience.11B.2.2 Population Exposure The total integrated annual population exposure to all indi viduals within 50 miles, by all pathways, is estimated to amount 12.7 man-rem in the year 2000. Di stributed over the 50-mile population, these exposure rates amount to only 9.32 x 10-3 mrem per capita in the year 2000. For comparison, the total population exposure in 50 miles from natural backgr ound radiation, at about 125 mrem/yr, amounts to 170,500 man-rem in the year 2000.
Revision 52-09/29/2016 NAPS UFSAR 11B-4 In the year 2000, the population exposure du e to gaseous releases is estimated at 5.07 man-rem/yr. Population exposure due to liquid releases, stemming wholly from exposure of persons using the North Anna Reservoir is projected to be 7.64 man-rem/yr in the year 2000.
The maximum potential population expos ure due to the use of the North Anna Reservoir and the Waste Heat Treatment Faci lity has been evaluated for two sources of internal exposure and three modes of external e xposure. Assuming that all persons living around the reservoir and all visitors drink water from the reservoir, the estimated population exposure amounts to 3.0 man-rem in the year 2000, for all reservoir usage.
The ingestion of fish caught in the North Anna Reservoir and Waste Heat Treatment Facility at an assumed rate of 24.9 lb/acre-yr amounts to a to tal annual exposure of 4.15 man-rem.Assuming that the average visitor spe nds 25% of his ti me at the N orth Anna Reservoir boating, 15% of his time sunbathing or walking along the beach, and 10% of his time swimming, the following conservative estimates of whole-body population exposure result:All possible sources of population exposu re due to the normal operation of North Anna Units 1 and 2 are insignificant in comparison to exposure levels comm on to ordinary experience, either from natural background radiat ion or from other man-made sources.11B.2.3 Conclusions The maximum potential radiati on exposure of the general public or any individual thereof due to the normal operation of Units 1 and 2 of North Anna has been evaluated. The combined whole-body dose to the maximally e xposed individual from all signifi cant sources is estimated at less than 3 mrem/yr, amounting to only about 2.3%
of the naturally oc curring whole-body exposure rate. The popula tion exposure within 50 miles due to station oper ation will amount to 12.7 man-rem in 2000. This is less than 0.01% of th e total exposure to the same population from natural background radiatio
- n. The potential exposu re due to station oper ation also amounts to only small fractions of other commonly experienced sources of radiation exposure such as medical X-rays and commercial air travel. It can be safely concluded that the of fsite radiation exposure from North Anna Units 1 and 2 will be an insignificant sour ce of risk in comparison to those already commonly accepted.
Exposure SourceMan-rem per Year, 2000 Boating 2.40 x 10-3 Sunbathing 0.48 Swimming 2.00 x 10-3 Revision 52-09/29/2016 NAPS UFSAR 11B-511B.3 RADIATION EXPOSURE FR OM GASEOUS EFFLUENTS There are a number of pathways through which of fsite pers ons may be exposed to the gaseous radioactivity released from nuclear power plants. From Figure 11B-1 , three general pathways may be identified: direct radiation exposure, inhalation expos ure, and exposure through food chains. The relative impor tance of these exposure pathways is determined by the radionuclide spectrum, the quantit ies of the released radiogase s, and the site environment.11B.3.1 Projected Gaseous EffluentsThe expected quantities of activity rele ases in gaseous form are presented in Table 11B-2. These releases represent the ma ximum annual average release rates expected to occur and are denoted hereafter as maximum expected values. These release rates include the effects of significant failed fuel cladding, r eactor coolant system to steam system leak age, reactor coolant leakage inside and outside of the containment building, and steam leak age to the turbine and auxiliary buildings.
Approximately 70% of the releases result from the assumed system leakages, almost 2900 Ci/yr resulting from steam ge nerator tube leakage alone.11B.3.2 External Exposure Fr om Gaseous Effluents From Table 11B-2 , it can be observed that the chemi cal composition of the anticipated gaseous releases will be essentially 100% noble gases, with only trace quantities of iodine present. Since the noble gases do not react chemically with other substances under normal conditions, there is no physi cal basis for either transport thr ough food chains or reconcentration within the human body for these ga ses. Thus, the most significant exposure pathway for released noble gases is direct external irradiation of the whole body
.The opposite is true of the released radi oiodines, for which inhalation and food chain transport are the critical pathways. External radiation from iodine is generally in significant in comparison to the internal dose derived through inhalation.11B.3.2.1 Maximum Individual External Exposure The maximum potential external dose rate de pends in general on the source terms, the applicable atmospheric diffusion, and the receptor characteristic
- s. The distance to the nearest unrestricted land area from the release point near the re actor building is nearly 1 mile at North Anna. For the purpose of estimating the pot ential annual exposure, a hypothetical "maximally exposed individual" will be assumed to remain continuously at the worst possible location over the full period of 1 year. The individual will be a ssumed to be unshielded by housing or clothing, which normally provides a dose reduction factor of two or more.
The calculational model used is the infinite-sphere model su ggested by the International Commission on Radiological Protection (ICRP) (Reference 5) and the International Atomic Energy Agency (IAEA) (Reference 6). The basic assumption of the model is that the absorbed Revision 52-09/29/2016 NAPS UFSAR 11B-6 dose rate at any point inside an infinite sphere of homogeneous material of uniform radioactivity con centration is equal to the dose rate at any ot her point. The dose rate to a ground-level receptor from a surrounding cloud of radioactivity is taken to be one-half that assumed by the infinite-sphere approach. This is because the receptor is only ir radiated from one-half the total available solid angle. Th e dose rate is also adjusted upward by a factor of 1.13 to account for the increased stopping power of human tissue relati ve to air (Reference 5). The use of this model leads to conservative result s for the following reasons:1.The surrounding cloud of radioactivity is never infinite in dimension.2.The substantial capacity of the human body fo r self-shielding agains t fission product beta radiation is not accounted for
.With regard to item 2 above, it can be shown th at the average range of the beta radiations of concern here are on the order of 1 cm or less in the human body a nd there is little reason to consider beta radiation as c ontributing to the whole-body dose.
The dose rate depends directly on the applicable value of /Q, the atmospheric dispersion parameter. By means of the NUS Corporation computer code WINDVANE , meteorological data were reduced and summarized, yielding tables of annual average values of /Q. Along the station exclusion boundary, the highest value of /Q overland occurs at 5000 feet to the south-southeast and is equal to 1.83 x 10-6 sec/m 3.Dose calculations based on this value of /Q, the source terms and disintegration ener gies presented in Table 11B-2, and the mathematical equations presented in Section 11B.6 yield an external whole-body exposure rate of 0.62 mrem/yr. Virtually all of this exposure is due to the released noble gases krypton and xenon.11B.3.2.2 External Population Exposure The population distribution within 50 miles of the site is presented in the form of a population wheel. The wheel gives the number of pe ople residing in each of 160 different land segments, a segment being defined as that area within a 22.5-degree sector (centered on one of the 16 compass points) and within one of the 10 annuli into which the area wi thin a 50-mile radius is sub divided.The total exposure occurring with in any one segment is the pr oduct of the average dose rate for the segment and the segment population. The total population exposure within 50 miles of the site is then the sum of the population exposures within each of the 160 population segments. The segment average dose rate was taken to be the dose rate of the geometric midpoint of the segment.
Following this general procedure, the NUS Corporation co mputer code GASDOS performed the necessary calculations. Results were obtained not only fo r the estimated 1970 population distribution but for the projected population distributi ons for the years 1 980, 1990, 2 000, 2010, and 2020. The results are summarized below
.
Revision 52-09/29/2016 NAPS UFSAR 11B-711B.3.3 Internal Exposure Fr om Gaseous Effluents Released radiogases (or their radioactive daughter products) mu st be either inhaled or ingested in order to yield intern al radiation exposure. Ingestion requires the physical transport of the radioactive gases through some form of food chain. This is possi ble for the isotopes of iodine and for the noble gas particulate daughter products. Inhalation is a significant pathway only for radioiodine.11B.3.3.1 Internal Exposure From Released Noble GasesSince the noble gases do not r eact chemically with other s ubstances, there is no physical basis for either food chain transport or reconcentration within the human body.
In terms of continued inhalation and ab sorption in the body , both krypton and xenon may develop in physical solution, chiefly in the body water and fat (Reference 7). Several human exposure experiments have revealed that inhalation of relatively large amounts of radioactive noble gases result in very lo w tissue exposures (References 8 & 9). In general, it may be estimated that the internal dos e from radioactive noble gases di ssolved in body tissue following inhalation from a cloud is negligib le (i.e., less than 1% of the associated external whole-body dose) (Reference 10). The resultant doses from exposure to noble gases, th erefore, are considered to be external whole-body doses only.11B.3.3.2 Internal Exposure From Released Radioiodine A small amount of radioactive iodine in add ition to the noble gases is expected to be released with the gases fr om the station. Iodine is an insignificant cont ributor to the external whole-body dose but may produce potentially significant internal doses as a result of the accumulation of iodine in the human thyroid gl and. Iodine may enter th e body by either inhalation or ingestion. The most critical pathway for the environmental tran sport of the routine release of radioiodine is the pasture-cow-milk-man pathway.Year Population Within 50 MilesTotal Man-rem Within 50 Miles of the Site Mrem per Capita 1970 836,2503.115 0.00373 1980 998,408 3.709 0.00371 1990 1,176,590 4.373 0.00372 2000 1,363,945 5.066 0.00371 2010 1,566,731 5.820 0.00371 2020 1,795,944 6.655 0.00370 Revision 52-09/29/2016 NAPS UFSAR 11B-811B.3.3.2.1 Iodine Inhalation Thyroid Dose As can be seen in Table 11B-2 , the total annual release of all radioactive isotopes of iodine is estimated to be much less than 1 Ci/yr. The annual induced t hyroid inhalation exposure to iodine resulting from conti nuous residence at a location 1 mile south-southeast of the reactors has been calculated to be 0.070 mrem/yr.The largest portion of this expos ure is due to the single isot ope I-131. This reflects its relative abundance in comparison to the other released isotopes of iodine and its greater-dose effectiveness, which is best illustrated by the following figures:The greater dose effectiveness of I-131 is prim arily because of its relatively long 8.05-day half life. The calculational model used to de rive doses from this so urce is presented in Section 11B.6.11B.3.3.2.2 Iodine Ingestion Thyroid Dose Although the radioiodine released will be in gaseous form init ially , it may be deposited on pasture that is subsequently inge sted by grazing cows. The cows will then transfer the radioiodine to milk, which is consumed as human foodstuff.
The exposure is inversely proporti onal to the mass of the thyr oid gland. The most sensitive receptor in the population, in te rms of total thyroid dose per unit intake, is thus an infant or a young child, who would have a very small thyroid. Also, th e relative radiosensitivity of the thyroid decreases markedly with age (Reference 12). Since the rate of milk ingestion is important in determining the dose, the most critical receptor is not a newborn infant, but is more likely to be a child 6 months to 1 year in age.
The nearest Grade A commercial dairy farm is located about 3.6 miles south-southwest of the station. The /Q value applicable at this loca tion was determined from the WINDV ANE output to be equal to 1.20 x 10-7 sec/m 3. Using dose conversion para meters recommended by the International Commission on Radiological Protection (Reference 5) and the Federal Radiation Council (Reference 12), the potential thyroid dose to a child from this source was computed to be Iodine Isotopes Rem per Curie Inhaled (Reference 11) I-131 1.48 x 10 6 I-132 5.35 x 10 4 I-133 4.00 x 10 5 I-134 2.50 x 10 4 I-135 1.24 x 10 5 Revision 52-09/29/2016 NAPS UFSAR 11B-9 1.21 mrem/yr. It was conservatively assumed that th e cows graze on grass the entire year and that a child may drink an average of 1 liter/day of milk.The effect of delay between the production and consumption of the milk was not included, nor was the ef fect of possible dilution by other milk supplies. The details of the calculational model employed are presented in Section 11B.6.11B.3.3.3 Internal Exposure From Particulates One of the gaseous radionuclides has a particul ate daughter (Cs-135) that can enter the food chain and be transported to man. The de cay chain of interest is as follows:
The amount of Xe-135 estimated to be released, as shown in Table 11B-2, is relatively small (70 Ci/yr). Assuming that all of this activity decay ed immediat ely to Cs-135, the equivalent Cs-135 release rate is 3.7 x 10-8 Ci/yr. The potential dose contribu tion from this route of exposure is insignificant.11B.4 RADIATION EXPOSURE FR OM LIQUID EFFLUENTS This section of the report is directed at an evaluation of th e potential radiation exposure occurring as a result of the expected releas e of radioactive liquid waste from the North Anna Power Station. Liquid radwaste will be discharged via the discharge tunnel to the Waste Heat Treatment Facility and will then enter the main North Anna Reservoir. Th us, the Waste Heat Treatment Facility and the reservoir, which together constitute the cooling water storage system, will both contain radioactive liquid waste from the North Anna station. The anticipated maximum equilibrium concentrations of all signi ficant radionuclides are presented in Table 11B-3 for both the Waste Heat Treatment Facility and the reservoir. The assu mptions regarding system leakages, failed fuel cladding, etc., are the same as for gaseous source terms.11B.4.1 Maximum Individual Ra diation Exposure From Liquid EffluentsAt this time, it is planned that the North Anna Reservoir will become a center for recreational activities in the regi on of the site. Activities that will bring the public into close contact with the waters of the reservoir , such as fishing, swim ming, and boating, will cause some amount of radiation exposure. In order to evaluate the maximum potential individual radiation Xe-135 9.2 hour-----------
-Cs-135 210 6xyear-----------------Ba-135 Revision 52-09/29/2016 NAPS UFSAR 11B-10 exposure due to North Anna Units 1 and 2, a "maximally exposed i ndividual" is hypothesized.
This individual does the following:1.He consumes 1.2 liters of water daily fr om the Waste Heat Treatment Facility. This water ingestion represents the total direct daily water intake that will adequately sustain an average adult male, as determined by the Interna tional Commission on Radiological Protection (Reference 5).2.He consumes an average of 50 g/day of fish taken from the Waste Heat Treatment Facility.3.He swims 200 hr/yr, boats 500 hr/yr, and sunbathes 300 hr/yr at the Waste Heat Treatment Facility.Other less significant exposure pathways are also considered.11B.4.1.1 Internal Exposure From Water Ingestion It is not presently planned that any individual will use either the North Anna Reservoir or the Waste Heat Treatment Facility as a source of potable water. At this time, there are ample ground-water supplies to serve the needs of the community for the foreseeable future. Putting aside all reasons for not doing so, it is assumed that an individual drinks daily from the cooling water storage system.
The ingestion of radionuclides will generally cause an uneven distribution of radioactivity within the human body. Some elements, hydrogen in particular, beco me rather evenly distributed. Others, such as iodine or cesium, are preferentially taken up by certain body organs. This phenomenon produces particular body-organ doses, which can be either higher or lower than the associated whole-body dose.
The array of particular body-or gan doses due to the hypothesi zed water ingestion has been calculated using the SWEC computer code IND1 109E. The results of this calculation are summarized in Table 11B-4. Calculational methods used in IND1 109E are those from Regulatory Guide 1.109, Revision 1, Calculation of Doses to Man fr om Routine Releas es or Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I. Section 11B.7 contains a detailed description of the mathemati cal model employed.11B.4.1.2 Internal Exposure From Fish IngestionAquatic organisms, through bi ological processes, have the ability to concentrate radionuclides released from the plant. This conc entration of activity in aquatic organisms, which may be ingested by man, must be considered in determining the possible dos e to man. The ratio of the concentration of a radionuclide in an aquatic organism to th at in the ambient water is known as the concentration factor. The concentration factor varies among the differ ent species of aquatic life and, for a given species, varies with the differen t radionuclides. Also, th e activity distribution may vary considerably between different organs of an organism. For the dose calculation in this Revision 52-09/29/2016 NAPS UFSAR 11B-11 report, appropriate concentration factors were used for the edible portions of the fish, as shown in Table 11B-5.In order to determine the dose to humans, the quantity of fish eaten must be estimated. The dose model used postulates that the maximally exposed indivi dual consumes 50g/day of fish flesh. This is about e qual to the seafood consumption re ported for commercial fisherman (Reference 14) and about four time s the annual per capita consump tion of seafood in the United States (Reference 15).The various maximum doses to an individual have been calc ulated by the SWEC computer code IND1 109E and are presented in Table 11B-6. The ingested fish was assumed to have concentrations of all radionuclid es in the edible flesh equal to the applicable equilibrium concentrations times the appropriate con centration factors, as presented in Table 11B-5. The calculational model empl oyed is described in Section 11B.7.11B.4.1.3 External Exposure From Swimming or Boating The external exposure of an individual by submersi on in waters containing the radioactive ef fluents of the North Anna Power Station is only a minor exposure pathway. The radionuclide that will be present in the highest concentration is tritium, which yields only weak beta radiation upon decay. The beta particles em itted from decaying tritium nuclei do not have sufficient energy to penetrate the human skin and, therefore, cannot contribute to an exte rnal whole-body dose. All other nuclides are assumed to irradiate the whole body.
The external exposure to swi mmers may be conservatively estimated by assuming that the swimmer is completely im mersed in an infinite medium of uniform concentration and receives the same dose as the water itself. The expression for the dose rate is given for each radionuclide by the following equation:
Raipj = U pa D aipj where: Raipj = the radiation dose from nuclide i for either swimming or boating pathway to organ j for age group a (mrem/yr)
C iw = concentration in water of radionuclide i, (pCi/liter)
U pa = the swimming or boating use factor for age group a (hr/yr)
Daipj = the dose conversion factor for age group a (mrem/yr per pCi/liter)
K p = geometry factor equal to 1 for swimming and 2 for boating.Table 11B-7 presents the computational results for exposure due to swimming. Also included are estimated exposure ra tes for boaters. The calculatio nal model above, with slight C iw K p---------
Revision 52-09/29/2016 NAPS UFSAR 11B-12modifications, was used to comput e boating exposure. Since a man in a boat is always at the surface of the water, the geometry factor for gamma radiation was take n to be 2.0; that is, radiation is received from only half the total solid angle.11B.4.1.4 External Exposure From Sunbathing A potential external exposure pathway exists for persons sunbathing or walking along the shores of the cooling water stor age system. The effluent radionuclides in the liquid wastes can be expected to accumulate to some degree in botto m sediments and shoreline sands. The affected beach area would be limited to approximately the area of th e beach between the low- and high-water marks.
The concentrations of the radi onuclides on the shore will be influenced by the chemical composition of the ef fluent, the aquatic environment, and the sorptive capacity of the shoreline.
The ability of soils to concentrate radioactive materials differs widely from one element to another. Radionuclides are removed from solutio n primarily by adsorption and ion exchange. Generally, the fine-grained bottom sediments are more effective sorbers of radionuclides than are the coarser-grained shoreline sands.
It was assumed that an individual lying on th e shore would receive ha lf the dose that he would receive if he were completely immersed in the sand. The geometry factor is taken to be 0.5 from this source. A calculation si milar to the swimming dose calculat ion with sand as the infinite medium results in a w hole-body dose rate of 2.0 x 10-7 rem/hr for sunbathing along the shore of the Waste Heat Treatment Facility. At the North Anna Reservoir, the dose rate is reduced to 1.5 x 10-7 rem/hr. Assuming an exposure period of 300 hr/yr, the annual dose to a sunbather would be 6.1 x 10-5 rem at the Waste Heat Treatment Facility and 4.6 x 10-5 rem at the reservoir.11B.4.1.5 Radiation Exposure From Other Sources Several exposure pathways have been consid ered in addition to those discussed above.
They are not discussed in great detail because of their relative insignificance. For instance, the possible uptake of radioactivity fr om the reservoir by land animals, and its subsequent transfer to man, is not as potentially hazar dous as the direct ingestion of reservoir water already evaluated.
For similar reasons, the potential hazard involved in the ingestion by man of crops irrigated with reservoir water is also ignored.11B.4.2 Population Radiation Exposure From Liquid Effluents There are currently no withdrawals of North Anna River waters for public or private water supplies within the immediate re gion of the site. The Environmen tal Report prepared to support the licensing of North Anna concluded that there are no known potable water withdrawals along the entire co urse at the North Anna River downstream to West Point, about 65 miles southeast of the site. Hence, all significant sources of populat ion exposure due to th e liquid ef fluents of North Anna Units 1 and 2 involve the public use of the coo ling water storage system. Potential Revision 52-09/29/2016 NAPS UFSAR 11B-13 sources of exposure considered signi ficant are the use of the system as a source of potable water and fish and its use as a location for the recreational activities of swimming, boating, and sunbathing.11B.4.2.1 Population Exposure From Water Ingestion Although it is not currently planned that the North Anna Reservoir will be used as a water source for the surrounding community, there are no physical impediments to such use in the future. Because of this, it is assumed that a community development in the immediate area of the reservoir will use the reservoir as a water source. This developm ent is expected to include a permanent-resident population of up to 4000 in the year 2000.
Summer residents can be acc ounted for by conservatively as suming that for each vacation residence in the area there are four persons present for one quarter of the year. This is equivalent to one permanent resident per vacation dwelling. The number of vacation homes expected ranges
up to 6000 by the year 2000 (Reference 19). This represents a buildi ng rate of about 1200 for each 5-year period based on a 1975 to 2000 building program.
The visitors to the North Anna Reservoir must also be consid ered. It has been es timated that as many as 3.5 million "visits" will occur in the year 2000 (Reference 19). Assuming that during each visit an individual consumes half his required daily drinking water (1.2 liters), this yields the annual volume of water consumptio n that can be equated to an equivalent number of permanent residents. The water ingestion due to visitors in 2000 is that wh ich would be exp ected for about 4795 permanent residents.
Considering all potential sources of water ingestion, the maximum population exposure that might occur from this source is estimated to be 3.0 man-rem/yr. in the year 2000. These values should be regarded only as upper limits of the actual exposure, which will in a ll probability be much lower.11B.4.2.2 Population Exposure From Fish Ingestion In order to calculate the eventual total annual fish catch from the proposed North Anna Reservoir and Waste Heat Treatment Facility, a figure of 24.9 lb/acre-yr (Reference 20) was applied. This figure, abstracted from a survey undertaken by th e National Reservoir Research Program, represents the average harvest of 103 major reservoirs within the continental United States. The average size of the reservoirs from which this numbe r was deduced is 14,650 acres, roughly equal to the area of the North Anna Reservoir. The total catc h per year over the reservoir water surface area of 13,000 acres is thus estimated at 324,000 lb. For fish, it is estimated that only about one-third of th e gross (landed) weight is edible as food (Reference 21). Therefore, the total edible amount of fish was obtained by mu ltiplying the gross pounds of edible fish by this conversion factor. It was conservatively assumed that 73% of the fish were caught in the reservoir and 27% in the Waste Heat Treatment Facility, based on the relative surface areas.
Revision 52-09/29/2016 NAPS UFSAR 11B-14 On this basis, the total a nnual whole-body popu lation exposure from fish ingestion is estimated at 4.2 man-rem. Since this exposur e depends only on how much fish is eaten and not on the population, the population exposure should re main relatively constant in time.11B.4.2.3 Population Exposure From Swimming, Boating, and Sunbathing The exposure of the public from recr eational activities at the North Anna Reservoir can be computed with the aid of the estimated number of recreational visits per year and a few assumptions. It is necessary to determine the total number of ma n-hours per year spent at the various activities. Then these va lues can be multiplie d by the dose per hour to obtain the annual population exposure. The following arbi trary assumptions have been used:1.About 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> per visit will be spent at the reservoir
.2.Half of this time will be spent on land-based activities involving no exposure, such as picnicking, hiking, and camping.3.The remaining time will be divided (on the average) between boating (50%), swimming (20%), and sunbathing (30%).
Using these assumptions and the previous ly obtained maximum individual dose rates applicable to activities in the reservoir, the annual population exposu res for the activities of concern were established. The values are given below:Of the three sources considered, only the exposure derived from sunbathing is of any importance.11B.5 DOSE TOTALS AND COMPARISON WI TH FEDERAL REGULATIONS AND NATURAL BACKGROUND The doses calculated to occur as a result of the op eration of Units 1 and 2 of the North Anna Power Station may best be brought into perspective by a comparison with exposure levels already present from naturally o ccurring background radiation.
The Environmental Protection Agency (Reference 2) has conducted a state-by-state survey of natural background radi ation levels and has made the result s available to the public. The report Annual Population Exposure (man-rem)
Activity 2000 Swimming 2.00 x 10-3 Boating 2.40 x 10-3 Sunbathing 0.48 Revision 52-09/29/2016 NAPS UFSAR 11B-15issued through the Special Studi es Group of the Division of Crit eria and Standards, Office of Radiation Programs, lists statewide average whole-body radiatio n doses from three sources:
(1) cosmic ray radiation, (2) naturally occurring terres trial radiation, and (3) internal radiation from naturally occurring radioisotopes incorporated into the human body. For the State of Virginia, the respective annual doses from these three sources are (1) 45 mrem, (2) 55 mrem, and (3) 25 mrem (Reference 2). Thus in Virginia, the aver age whole-body do se from natural background radiation amounts to 125 mrem/yr, slightly lower th an the national average of 130 mrem/yr (Reference 2).In other states, the annual whole-body background dose is re ported to range upward from 100 mrem/yr in Louisiana to 250 mrem/yr in Colorado. The Specia l Studies Group has also found that medical exposure in the United States averaged 90 mrem/yr in 1970 (Reference 2). The annual average exposure from televi sion sets is reported to be 0.1 mrem (Reference 2). The total whole-body population exposure occurring as a result of increased cos mic radiation during commercial air travel is estimated at 90,000 man-rem in the United States during 1969 (Reference 22).The evaluation of populat ion doses reported in Table 11B-8 is based on the member of the public dose criteria in the original 10 CFR 20 dated 1960. In the revised rule dated May 21, 1991 the annual dose limit to a memb er of the public wa s changed from 500-mrem whole body to 100-mrem Total Effective Dose Equivalent (TEDE). NRC guidanc e indicates that evaluations performed under the old 10 CFR 20 criteria do not require recalc ulation. Historical operational data demonstrates doses to members of the public are maintained below the new federal limits.Whole-body and body-organ doses to the maximall y exposed individual for all significant or gans from all significant sour ces are presented and totaled in Table 11B-9. It is extremely improbable that any of these ma ximum individual exposure rates wi ll ever occur. The probability that a single individual will experience them all simultaneously is ne gligible. The totals are presented only as certain upper li mits of the potential exposure.11B.6 COMPUTATIONAL METHODS FOR DOSES RESULTING FR OM GASEOUS EFFLUENTS11B.6.1 Whole-Body Noble Gas Immersion Dose As indicated in the body of the report, the gase ous radioactive ef fluent s consist primarily of the noble gases krypton and xeno
- n. Exposure of a man to an atmosphere contaminated with radioactive isotopes of these elements result s only in an external , whole-body dose from submersion in the radioactive cl oud. Since these elements are not incorporated into the human body to a significant degree, there are no resulting internal doses.
Revision 52-09/29/2016 NAPS UFSAR 11B-16 For releases at ground level, the resulti ng dose is proportional to the ground-level concentration of radioa ctivity and can be computed usin g the International Commission on Radiological Protection (I CRP) recommended semi-inf inite sphere model (Reference 5). The following relationship was used to de termine the dose rate from this source:
D (rem/yr) = 0.259 x (/Q) x E i Q i where:/Q = applicable annual average atmospheric dispersion parameter, sec/m 3 E i = average total disintegration energy of the ith radionuclide 1 Q i = annual average activity release for the ith radionuclide, Ci/yr 0.259 = constant necessary to yield the dose rate in rem/yr The normalization constant, 0.259, is given by the following equation:
where: 1/2 = geometry factor accounting for the fact that the receptor is not irradiated from the total available solid angle 1.13 = a factor to account for the increased st opping power of tissue relative to air for s and secondary electrons produced by x- and -radiation (Reference 1)The above formula for the external whole-body dose rate was used for maximum individual exposure and for population exposure. The es timated population distributions within 50 miles of the station for the years 1970, 1980, 1990, 2000, 2010 a nd 2020 were used for this purpose. For each of the 160 populat ion segments (16 sectors, 10 annuli) into which the 50-mile population is distributed, an annual average segment dose rate was established. This wa s taken to be the dose rate at the geometric midpoint of the segment. The annual segment population exposure is thus the product of the segment populat ion and the segment average dos e rate. Summing the individual segment population e xposures over all 160 segments yields the tota l population exposure within 50 miles of the station.The average value of /Q for a specific segment was taken to be that for the distance of the midpoint of that segment from the station. For example, the average /Q for a sector 10 to 20 miles in a given direction was taken to be that for a distance of 15 miles in the given direction.
The numerical values for /Q used in this evaluation were obtained from the onsite 1.The value of E i for each radionuclide of interest was obtained from Meek and Gilbert (Reference 4).
0.259 1 2---1.610 6-ergsMeV
-xx10 2-grradserg-()1remrad()=1.13 ()3.710 10xxdis Ci-sec-----------------
11293.gm 3 air----------------------------------
-
Revision 52-09/29/2016 NAPS UFSAR 11B-17meteorological data collected during the period September 16, 1971, through September 15, 1972. The necessary data reduction was perf ormed with the NUS computer code WINDVANE.11B.6.2 Thyroid Inhalation Dose A small amount of radioactive iodine will be released during normal operation. The external whole-body dose resulting from submersion in a cloud of radioactive iodine is negligible; however , iodine taken into the body produces an internal dose as the iodine is preferentially concentrated in the thyroid gland. The thyroid dose was calcul ated by the following equation:D (rem/yr) = (/Q) x (B R) x (DCF) x (S)where:/Q = applicable annual average atmospheric diffusion factor, sec/m 3 S = total I-131 "dose equivalent" release rate, Ci/yr 1 BR = breathing rate for the "standard man," 2.31 x 10-4 m 3/secDCF = dose conversion factor, 1.48 x 10 6 rem/Ci I-131 inhaled (Reference 11)11B.6.3 Child Thyroid Milk Ingestion Dose Model The critical pathway for iodine inges tion following gaseous releases is the pasture-cow-milk-man pathway, with the thyr oid being the critical organ. The most sensitive receptor in the population in te rms of a thyroid dose from milk ingestion is a young child 6 months to 1 year of age. The foll owing model (References 23 & 24) was used to compute the child thyroid milk dose from I-131:D (rem/yr) = (/Q)(V g K c I d)(D/A T)(S/g)where:
/Q = applicable annual average atmospheric diffusion factor V g = 0.01 m/sec: deposition velocity of iodine onto pasture (Reference 24)
K c = 0.09: milk/grass activity ratio, (µCi/l)/(µCi/m 2) (Reference 24)
I d = 1.0 liter/day: child's milk ingestion rate (Reference 25)
D/A T = 13.97 x 10 6 rem/Ci: dose/activity ratio for child's I-131 ingestion 2 (References 12 & 26)
(g)-1 = 7.19 days: mean lifetime for I-131 on the ground S = annual average I-131 release rate, Ci/yr1.For iodine isotopes other than I-131, a "dose equivalent" release rate of I-131 is obtained by the method outlined by DiNunno (Reference 11).2.In the case of an adult, the value of D/A T is 1.530 x 10 6 rem/Ci of I-131 ingested (References 11 & 12).
Revision 52-09/29/2016 NAPS UFSAR 11B-1811B.7 COMPUTATIONAL METHODS FOR DOSES RESULTING FR OM LIQUID EFFLUENTS11B.7.1 Whole-Body and Body-Organ Exposure From Water Ingestion The International Commission on Radiological Pr otection (ICRP) ha s established the maximum daily average drinking water intake of the standard man at 1.2 liters (Reference 5).The annual dose from the ingestion of wate r is calculated using the following equation:
Rapj = 1100 Q i D aipj exp(-ip)where: Rapj is the annual dose to organ j of an individual of age group a, via pathway p (mrem/year).
U ap is the intake rate (usage) associated wi th pathway p for age group a (liters/year).
M p is the mixing ratio (reciprocal of the dilution factor) at the point of exposure.F is the flow rate of the liquid effluent (ft 3/sec).Q i is the release rate of nuclide i (Ci/yr).
Daipj is the dose factor, specific to age group a, radioisotope i, pathway p and organ j (mrem/pCi).i is the decay constant of nuclide i (hr
-1).p is the elapsed time be tween release of the nucli des and injestion (hours).The dose factors used are from Regulatory Guide 1.109, Revision 1, Tables E-11, 12, 13 and 14.The resultant doses are given in Table 11B-11.11B.7.2 Whole-Body and Body-Organ Exposure From Fish Ingestion Aquatic life forms will concen trate various elements within their bodies in proportion to the con centration of the element in the water in which they live. The ratio of the concentration of the element in the organism to the c oncentration in water is defined as the concentration factor. The concentration factor generally depends on the element being concentrated, the species of organism, and the environment in which it lives. Maximum concentration factors for fresh water fish have been tabulated in Table 11B-5 and are used here to estimate the maximum activity of individual radioisotopes in fish.
For the purpose of estimating the maximum dos e an individual might obtain from eating fish, it was assumed that an individual might consume a maximum average of 50g/day of fish.
U ap M p F----------------
- i Revision 52-09/29/2016 NAPS UFSAR 11B-19 The annual internal dose resultin g from human consumption of aquatic foods is calculated using the following equation.
Rapj = 1100 Q i B ip D aipj exp(-ip)where all of the variables are as defined in Section 11B.7.1 except: B ip which is the equilibrium bio accumulation factor for nuclide i in pathway p (liters/kg).
The resultant doses are given in Table 11B-6.U ap M p F----------------
- i Revision 52-09/29/2016 NAPS UFSAR 11B-2011B REFERENCES 1.Standards for Protecti on Against Radiation (Part 20) in Code of Federal Regulations, Title 10.2.U. S. Environmental Protection Agency, Special Studies Group, Office of Radiation Programs, Estimates of Ionizing Radiation Doses in the United States, 1960-2000 , 2nd printing.3.H. Blatz, Radiation Hygiene Handbook , McGraw-Hill, 1959.4.M. E. Meek and R. S. Gilbert, Summary of Gamma and Beta Ener gy and Intensity Data , NEDO-12037, Nucleonics Laboratory, General Electric Company, 1970.5.International Commission on Radiological Protection, Publication 2: Report of Committee II on Permissible Dose for Internal Radiation , Pergamon Press, New York, 1959.6.International Atomic Energy Agency, Radioactive W aste Dis posal into the Sea, Safety Series No. 5, Vienna, 1961.7.R. E. Hytten, K. Taylor, and N. Taggart, Measurement of Total Body Fat in Man by Absorption of Kr-35, Clinical Science, Vol.
31, 1966.8.C. A. Tobias, H. B. Jones, J. H. Lawrence, and J. G. Hamilton, The Uptake and Elimination of Kr ypton and Other Inert Gases by the Human Body, Journal of Clinical Investigation, Vol. 28, pp. 1375-1385.9.N. A. Lassen, Assessment of Tissue Radi ation Dose in Clinical Use of Radioactive Inert Gases, with Examples of Absorbed Doses from 3 H, 85 Kr , and 133 Xe , Minerva-Nucleare, Vol. 8, 1964.10.M. M. Hendrickson, "The Dose from 85 Kr Released to the Earth's Atmosphere," in Environmental Aspects of Nuclear Power Stations, IAEA Symposium, New York, August 1970.11.J. J. DiNunno, et al., Calculation of Distance Factors for Power and Test Reactor Sites , TID-14844, U. S. Atomic Energy Commission, 1962.12.Federal Radiation Council, Backgr ound Material for the Development of Radiation Protection Standards , Report No.
5, July 1964.13.W. H. Chapman et al., Concentration Factors of Chemical Elements in, Edible Aquatic Or ganisms , UCRL-50564, December 1968.14.K. W. Cowser and W. S. Snyder, Safety Analysis of Radionuclide Release to the Clinch River , ORNL-3721, Supplement 3, 1966.
Revision 52-09/29/2016 NAPS UFSAR 11B-2115.F. Riley, Fisheries of the United States , NMFS-5600, National Oceanic and Atmospheric Administration, U. S. Department of Commerce, March 1971.16.W. H. Laugham and E. A. Pinson, Physiology and Toxicology of Tritium in Man , Journal of Applied Physiology
, Vol. 10, January-May 1957.17.A. Preston and D. F. Jeffer ies, "A quatic Aspects in Ch ronic and Acute Contamination Situations," in Environmental Contaminati on by Radioactive Materials , IAEA Symposium, Vienna, 1969.18.E. Clueckauf, editor, Atomic Energy Waste, Interscience Publishers, Inc., New York, 1961.19.Theodore J. Wirth and Associates; North Anna Reservoir , prepared for the Virginia Commission of Out door Recreation, 1971.20.R. M. Jenkins and D. T. Mora is, "Reservoir Sport Fishing Ef fort and Harvest in Relation to Environmental Variables," Reservoir Fisheries and Limnology , No. 8, American Fisheries Society, Washington, D. C., 1971.21.Letter from R. H. Wheeland, Statistics and Marketing News Di vision, National Marine Fisheries Service, Washington, D. C., dated August 11, 1971.22.M. I. Goldman, Statement by Dr. Morton I. Goldman on Behalf of the Cons olidated Utility Group in the U. S. Atomic Energy Commission Rulemaking Hearing on Proposed Appendix I , Germantown, Md., March 17, 1972.23.A. P. Hull, "Comments on a Derivati on of the 'Factor of 700' for I-131,"
Health Physics , Vol. 19, No. 5, November 1970.24.K. D. George, "I-131 Re concentration Factor
," Health Physics, Vol. 19, No. 5, November 1970.25.J. J. Burnett, "A Derivation of the 'Factor of 700' for I-131,"
He alth Physics, Vol. 18, No. 1, January 1970.26.P. M. Bryant, "Data for Asse ssments Concerning Controlled and Accidental Releases of I-131 and Cs-137 to Atmosphere," Health Physics, Vol. 17, No. 1, July 1969.27.W. S. Spector, Handbook of Biological Data , W. B. Saunders Company, 1961.
Revision 52-09/29/2016 NAPS UFSAR 11B-22Table 11B-1 RADIATION EXPOSURE PATHWAY LOCATIONS Sector Milk Cow Meat Animal Milk Goa tNearest ResidenceVegetable GardenNearest Site Boundary N 3.25 km 3.00 km 2.50 km 3.25 km 1.40 km 2.02 mi 1.86 mi 1.55 mi 2.02 mi 0.87 mi NNE 6.75 km 5.25 km 2.25 km 4.25 km 1.36 km 4.19 mi 3.26 mi 1.40 mi 2.64 mi 0.85 mi NE 2.25 km 2.00 km 2.00 km 1.32 km 1.40 mi 1.24 mi 1.24 mi 0.82 mi ENE 4.00 km 4.00 km 3.25 km 3.50 km 1.31 km 2.49 mi 2.49 mi 2.02 mi 2.18 mi 0.81 mi E 3.00 km 5.00 km 2.00 km 3.00 km 1.33 km 1.86 mi3.11 mi 1.24 mi 1.86 mi 0.83 mi ESE 7.75 km 2.75 km 3.00 km 1.37 km 4.82 mi 1.71 mi 1.86 mi 0.85 mi SE 2.25 km 7.00 km 2.25 km 2.25 km 1.41 km 1.40 mi 4.35 mi 1.40 mi 1.40 mi 0.88 mi SSE 2.25 km 3.25 km 3.25 km 1.47 km 1.40 mi 2.02 mi 2.02 mi 0.91 mi S 2.50 km 1.75 km 2.50 km 1.52 km 1.55 mi 1.09 mi 1.55 mi 0.94 mi SSW 4.80 km 3.25 km 2.25 km 2.25 km 1.62 km 3.00 mi 2.02 mi 1.40 mi 1.40 mi 1.01 mi SW 2.50 km 2.25 km 2.25 km 1.70 km 1.55 mi 1.40 mi 1.40 mi 1.06 mi WSW 4.75 km 2.75 km 2.25 km 2.75 km 1.75 km 2.95 mi 1.71 mi 1.40 mi 1.71 mi 1.09 mi W 6.75 km 2.75 km 4.25 km 1.71 km 4.19 mi 1.71 mi 2.64 mi 1.06 mi WNW 5.00 km 6.25 km 1.75 km 5.00 km 1.64 km3.11 mi 3.88 mi 1.09 mi3.11 mi 1.02 mi NW 4.00 km 1.75 km 3.25 km 1.56 km 2.49 mi 1.09 mi 2.02 mi 0.97 mi NNW 3.50 km 3.75 km 3.50 km 3.50 km 1.45 km 2.18 mi 2.33 mi 2.18 mi 2.18 mi 0.90 mi Revision 52-09/29/2016 NAPS UFSAR 11B-23Table 11B-2ESTIMATED GASEOUS EFFLUENTS AND IS OTOPIC DISINTEGRATION ENER GIES Isotope Units 1 and 2 Release Rate (Ci/yr) a a.Reference 5.AverageDisintegrationEnergy(MeV) bb.Reference 6.
Noble gasesKr-85m 24 0.257Kr-85 1900 0.2301Kr-87 13 1.870Kr-88 42 2.307 Xe-131m 1.9 0.157 Xe-133m 35 0.215 Xe-133 3400 0.1988 Xe-135m 2.8 0.530 Xe-135 70 0.551 Xe-138 7.5 1.497 Halogens I-131 0.086 0.584 I-132 0.0122.711 I-133 0.083 1.039 I-134 0.002 3.066 I-135 0.024 1.932 Revision 52-09/29/2016 NAPS UFSAR 11B-24Table 11B-3 MAXIMUM EXPECTED RADIOACTIVITY CONCENTRATIONS IN THE NORTH ANNA WASTE HEAT TREATMENT FACILITY AND RESERVOIR Isotope Equilibrium Concentration (µCi/cc) Waste Heat Treatment Facility Reservoir H-3 5.3 x 10-6 4.1 x 10-6Cr-51 3.2 x 10-12 7.4 x 10-13 Mn-54 2.8 x 10-12 1.8 x 10-12 Co-58 5.1 x 10-11 2.1 x 10-11 Co-60 2.2 x 10-11 1.7 x 10-11 Fe-59 2.9 x 10-12 9.1 x 10-13Sr-89 1.0 x 10-12 3.5 x 10-13Sr-90 9.7 x 10-14 7.6 x 10-14Sr-91 1.4 x 10-14 6.3 x 10-17Y-90 8.7 x 10-14 7.4 x 10-14Y-91 1.9 x 10-13 7.0 x 10-14Y-93 7.6 x 10-16 3.7 x 10-18 Nb-95 5.0 x 10-13 2.1 x 10-13Zr-95 4.2 x 10-13 1.6 x 10-13 Mo-99 2.3 x 10-11 7.1 x 10-13Tc-99m 2.1 x 10-11 6.3 x 10-13 I-131 3.4 x 10-10 2.9 x 10-11 I-132 7.2 x 10-12 2.4 x 10-13 I-133 5.2 x 10-11 5.3 x 10-13 I-134 4.8 x 10-14 2.0 x 10-17 I-135 5.8 x 10-12 1.9 x 10-14Te-132 6.6 x 10-12 2.4 x 10-13 Cs-134 2.7 x 10-10 1.9 x 10-10 Cs-136 1.7 x 10-11 2.2 x 10-12 Cs-137 2.7 x 10-10 2.2 x 10-10 Ba-140 2.2 x 10-13 2.8 x 10-14 La-140 2.3 x 10-13 2.8 x 10-14 Ce-144 1.6 x 10-12 9.9 x 10-13Total 5.3 x 10-6 4.1 x 10-6Non-Tritium Total 1.4 x 10-9 7.0 x 10-10 Revision 52-09/29/2016 NAPS UFSAR 11B-25Table 11B-4 MAXIMUM INDIVIDUAL INTERNAL BODY-ORGAN EXPOSURE FROM INGESTION OF WATERExposure by Water Source (mrem/yr)Body OrganWaste Heat Treatment FacilityNorth Anna Reservoir Whole body 0.27 0.20 Lungs 0.25 0.19 Kidney 0.25 0.20 Bone 0.018 0.013 Thyroid 0.54 0.21Lower large intestine 0.24 0.19 Revision 52-09/29/2016 NAPS UFSAR 11B-26Table 11B-5CONCENTRATION FACTOR FOR EFFLUENT RADIONUCLIDES IN FISH Aa.Concentration factors used in this report for fresh water are from Table A-1, Regulatory Guide 1.109, Rev. 1, Page 1.109-13.
Element Concentration Factor in Fresh Water Fish H 0.90 Cr 200 Mn 400 Co 50 Fe 100 Sr 30 Y 25 Nb 30,000 Zr 3.3 Mo 10 I 15 Te 400 Ba 4 La 25 Ce 1 Br 420 Rb 2000 Tc 15 Ru 10 Cs 2000 Pr 25 Np 10 Revision 52-09/29/2016 NAPS UFSAR 11B-27Table 11B-6MAXIMUM INDIVIDUAL INTERNAL BODY-ORGAN EXPOSURE FROM INGESTION OF FISHExposure by Water Source (mrem/yr)Body OrganWaste Heat Treatment FacilityNorth Anna Reservoir Whole body 1.9 1.4 Lungs 0.29 0.22 Liver 2.6 1.9 Kidney 0.86 0.64 Bone 1.4 1.1 Thyroid 0.20 0.022Lower large intestine 0.070 0.046 Revision 52-09/29/2016 NAPS UFSAR 11B-28Table 11B-7MAXIMUM INDIVIDUAL EXPOSURE FROM SWIMMING AND BOATING Swimming ExposureBoating Exposure Exposure CategoryWaste Heat Treatment FacilityNorth Anna ReservoirWaste Heat Treatment FacilityNorth Anna Reservoir Whole-body exposure, rem/hr 6.84 x 10-10 9.30 x 10-10 8.54 x 10-10 1.17 x 10-9Maximum hr/yr for this activity 200 200 500 500 Annual whole-body exposure, rem/yr 3.42 x 10-7 1.86 x 10-7 4.29 x 10-7 2.33 x 10-7 Annual skin exposure, rem/yr 4.38 x 10-7 2.34 x 10-7 5.47 x 10-7 2.93 x 10-7 Revision 52-09/29/2016 NAPS UFSAR 11B-29Table 11B-8POPULATION EXPOSURE TOTALS: COMPARISON WITH FEDERAL REGULATIONS AND NATURAL BACKGROUND Exposure Category Population Exposure in 50 Miles (man-rem/yr)
In 2000 Exposure due to gaseous releases 5.066 Exposure due to liquid releases:
From water ingestion 3.0 From fish ingestion 4.2 From boating 2.4 x 10-3 From swimming 2.0 x 10-3 From sunbathing 0.48 Exposure totals:
From the operation of North Anna Units 1 & 2 12.7 From natural background (125 mrem/person) 1.705 x 10 5 Maximum allowable under 10 CFR 20 (170 mrem/person) 2.319 x 10 5 Revision 52-09/29/2016 NAPS UFSAR 11B-30Table 11B-9MAXIMUM INDIVIDUAL WHOLE-BODY AND BODY-OR GAN DOSE TOTALS (mrem/yr)
Exposure Category Whole Body Liver Bone Thyroid Exposure due to gaseous releases From noble gas immersion 0.616 0.616 0.616 0.616 From radioiodine inhalation n aa.n = negligible.
n n 0.0697 From radioiodine ingestion via cow-milk-man pathway bb.The thyroid exposure that would be received by a child at the nearest Grade A dairy farm is presented here.
n n n 1.21 Exposure due to liquid releases, Waste Heat Treatment Facility From the ingestion of water 0.27 0.27 0.018 0.54 From the ingestion of fish 1.9 2.6 1.4 0.20 From boating, 500 hr 0.0004 0.0004 0.0004 0.0004 From swimming, 200 hr 0.0003 0.0003 0.0003 0.0003 From sunbathing, 300 hr 0.061 0.061 0.061 0.61 Dose totals from above sources 2.23 2.93 1.48 0.80 Exposure due to liquid releases, North Anna Reservoir From the ingestion of water 0.20 0.21 0.013 0.21 From the ingestion of fish 1.4 1.9 1.1 0.022 From boating, 500 hr 0.0002 0.0002 0.0002 0.0002 From swimming, 200 hr 0.0002 0.0002 0.0002 0.0002 From sunbathing, 300 hr 0.046 0.046 0.046 0.046 Revision 52-09/29/2016 NAPS UFSAR 11B-31Table 11B-10ORGANS OF INTEREST FOR EFFLUENT RADIONUCLIDES Element Whole BodyBody Water Lungs Liver Spleen Kidney Bone Muscle Pacreas Thyroid Testes Ovaries Prostate Stomach Small Intestine Upper Large Intestine Lower Large IntestineTritium X X Chromium X X X X X X Manganese X X X X X Cobalt X X X X X X Iron X X X X XStrontium X X X X Yttrium X X X X Niobium X X X Zirconium X X X Molybdenum X X X X Iodine X X X X X X X X X XTellurium X X X X X X X X Cesium X X X X X X X X Barium X X X X X X X X X X Lanthanum X X X X Cerium X X X X Revision 52-09/29/2016 NAPS UFSAR 11B-32Table 11B-11DOSE CONVERSION FACTORS FOR SWIMMING (MREM/HR PER pCi/LITER)
Isotope SkinT. Body Isotope SkinT.BodyCr51 6.4E-08 5.2E-08Te127 1.7E-07 2.8E-07 Mn54 1.8E-06 1.5E-06Te129m 7.4E-07 2.1E-07Fe55 3.6E-106.4E-11Te129 7.0E-07 1.7E-07Fe59 2.6E-06 2.2E-06Te131m 2.7E-06 2.2E-06 Co58 2.3E-06 1.8E-06Te131 1.6E-06 7.4E-07 Co60 5.4E-06 4.6E-06Te132 4.8E-07 4.0E-07Br83 3.1E-07 1.7E-08I130 4.8E-06 3.9E-06Br84 5.3E-06 3.5E-06I131 7.3E-07 6.8E-07Br85 1.1E-06 1.4E-08I132 5.5E-06 4.4E-06 Rb86 8.5E-07 1.7E-07I133 1.5E-06 9.6E-07 Rb88 3.6E-06 1.2E-06I134 5.5E-06 4.2E-06Sr89 5.4E-07 4.6E-09I135 4.0E-06 3.3E-06Sr90 1.5E-07 5.4E-10 Cs134 3.5E-06 2.9E-06Sr91 2.9E-06 1.9E-06 Cs136 4.8E-06 4.1E-06 Y90 9.6E-07 1.3E-08 Cs137 1.4E-06 1.0E-06 Y91m 1.2E-06 1.0E-06 Ba140 7.6E-07 4.9E-07 Y91 5.7E-07 6.7E-09 La140 5.3E-06 4.1E-06 Y93 1.4E-06 1.9E-07 Ce141 2.4E-07 1.3E-07 Zr95 1.8E-06 1.5E-06 Ce143 1.0E-06 5.7E-07Nb95 1.6E-06 1.4E-06 Ce144 1.4E-06 8.6E-08 Mo99 9.1E-07 4.7E-07 Pr143 2.8E-07 1.6E-09 TC99m 2.7E-07 2.4E-07 Pr144 1.3E-06 5.6E-08 Ru103 1.1E-06 8.9E-09 Np239 3.7E-07 2.4E-07 Ru106 1.9E-06 3.8E-07 H3 0.0 0.0 TE125m 1.5E-08 3.6E-09Te127m 1.8E-09 2.6E-10 Revision 52-09/29/2016 NAPS UFSAR 11B-33Figure 11B-1 EXPOSURE PATHWAYS Revision 52-09/29/2016 NAPS UFSAR 11B-34 Intentionally Blank Revision 52-09/29/2016 NAPS UFSAR 11C-iAppendix 11CEvaluation of Compliance With Proposed 10 CFR 50, Appendix INote:The information contained in Appendix 11C is HISTORICAL and was provided as part of the North Anna Operating License a pplication as a one-time ev aluation of compliance to the requirements of the "Proposed" 10 CFR 50, Appendix I. It was accurate at the time the plant was originally licensed but was not intended or expect ed to be upd ated for the life of the plant. C ontinued compliance with 10 CFR 50, Appendix I is ensured through the Technical Specifications which require the Offsite Dose Calculation Manual (ODCM) and the Radioactive Effluent Controls Program. The ODCM contains the Radiological Environmental Monitoring Program which includes a Land Use Census.
Sections 11.2 , 11.3 , and Appendix 11B of the UFSAR maintain a current description of the expected liquid and gaseous releases a nd dose assessments to demonstrate continued compliance with federa l regulations including 10 CFR 50 Appendix I.The original Appendix 11C in the North Anna FSAR included data for the proposed Units 3 and 4. This is consistent with the E nvironmental Report subm itted as part of the North Anna Power Station licensing process. This information is retained as historical information in Appendix 11C even though Units 3 and 4 were never built.
Revision 52-09/29/2016 NAPS UFSAR 11C-ii Intentionally Blank Revision 52-09/29/2016 NAPS UFSAR 11C-1The following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
APPENDIX 11C EVALUATION OF COMPLI ANCE WITH PR OPOSED 10 CFR 50, APPENDIX I11C.1
SUMMARY
AND CONCLUSIONSThe Nuclear Regulato ry Commission (NRC) letter of February 19, 1976, provided guidance to evaluate the North Anna Power Station with respec t to its ability to meet the requirements of proposed Appendix I to 10 CFR 50. This guidance substituted the requirements of RM 50-2 (issued on February 20, 1974) for those of Section II.D of Appendix I.Section II of RM 50-2 sets forth the following design objectives:1.For radioactive material a bove background in liquid ef fluent s released to unrestricted areas:a.The calculated annual tota l quantity of all radioact ive material from all light-water-cooled nuclear power reactors at a site should not result in an annual dose or dose commitment to the total body or to any organ of an individual in an unrestricted area from all pathways of exposure in excess of 5 mrem.b.Five curies of radioactive material release per reactor.2.For radioactive material abov e background in gaseous ef fluents released to the atmosphere by all light-water-cooled nuclear power reactors at a single site:a.The calculated annual dose due to gamma radiation at a ny location near ground level that could be occupied by individuals at or beyond the boundary of the site should not exceed 10 mrads.b.The calculated annual air dose due to beta radiation at any location near ground level that could be occupied by individuals at or beyond the boundary of the site should not exceed 20 mrads.c.Notwithstanding the guidance in item 2, for a particular site:1)The NRC may specify, as guidance on design objectives, a lower quantity of radioactive material above background in ga seous ef fluents to be released to the atmosphere if it appears that the use of the design objectives described in item 2 is likely to result in an annua l dose to an individual in an unrestricted area in excess of 5 mrem to the total body or 15 mrem to the skin.
Revision 52-09/29/2016 NAPS UFSAR 11C-23.For radioactive iodine and radioactive ma terial in particulate form above background released to the atmosphere:a.The calculated annual total quant ity of all radioactive iodine and radioactive material in particulate form from all light-water-cooled nuclear power reactors at a site should not result in an annual dose or dose commitment to any organ of an individual in an unrestricted area from all pathwa ys of exposure in excess of 15 mrem. In determining the dose or dose commitment, the portion thereo f due to intake of radioactive material via the food pathways may be evaluated at the locati ons where the food pathways actually exist.b.The calculated annual total quantity of iodine
-131 in gaseous ef fluents should not exceed 1 Ci for each light-water-cooled nuc lear power reactor at a site.
The evaluation shows th at potentia l releases and doses are within thes e objectives. A comparison of the above design objectives with the numerical results of this analysis is provided in Table 11.C-1. Three sets of results have been obtained for (1)
Units 1 and 2 together, (2)
Units 3 and 4 together, and (3)
Units 1, 2, 3, and 4 together.
Radioactive release estimates for this analysis are provided in Section 11C.5 for Units 1 and 2 (based on the guidance of Regulatory Guide 1.112, except as noted
). Release rates for Units 3 and 4 were obtained from the North Anna Final Environmenta l S tatement (FES) of April 1973 (Reference 1).Meteorological dispersion and deposition anal yses were based on models, assumptions, and parameter values as provided in Regulatory Guide 1.111 (March 1976). Liquid pathway doses were based on equilibrium activity concentrations for La ke Anna and the waste heat treatment facility calculated us ing the model given in Appendix 3.1 of the FES. Hydrologic data describing average flows and evapor ation rates were obtained from Table 3.13 of the FES (pp. 3-52).All dose calculations were performed using models and assumptions consistent with Regulatory Guide 1.109 (March 1976). The NRC LADTAP and GAS PAR codes were used for liquid and gaseous dose calculations, respectively. The NUS Corpora tion FIDOS code was used for determining ground-level gamma doses from elevated noble gas releases.
All results indicate that plant operation will not result in ra diation exposure in excess of the design objectives of proposed Appendix I even considering opera tion of all four units.
Compliance with the per
-unit dose limits of RM 50-2 as implemente d has also been established.The following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
Revision 52-09/29/2016 NAPS UFSAR 11C-311C.2 DOSES FROM LIQUID EFFLUENTS Maximum individual doses from liquid effluents were calculated using the NRC LADTAP computer code, using mo dels given in Regulatory Guide 1.109 (March 1976). Dose factors, bioaccumulation factors, and the s hore-width factors as given in Regulatory Guide 1.109 and in the LADTAP code were used, as we re use factors for water and fish ingestion and water-related activities.
The source-term data provided in Section 11C.5 were used in conj unction with equations for equilibrium concentrat ions given in Appendix 3.1 of the North Anna FES to determine the equilibrium concentratio n estimates pr ovided in Table 11.C-2. The hydrologic data entering into the concentration calculati ons were obtained from Table 3.13 of the FES. Table 11.C-2 provides estimates for equilibri um conditions of concentrations in the discharge canal (including recirculation effects), in the waste heat treatment facility, and in Lake Anna.
Maximum individual doses were calculated for water and fish ingestion and for external exposure for shoreline use, sw imming, and boating. The nearest potential pot able water intake was considered to be Lake A nna, although it appears likely th at the area ground-water supply will be sufficient for all local requirements for many years (Reference 2). There is also some doubt as to the capability of Lake Anna to support any sizable supply system (Reference 2). All other dose pathways were conservatively ev aluated at dischar ge canal concentrations.Because the analysis was based on equilibriu m concentrations, all dilution factors were input into the LADT AP code as ones; transit times were inpu t as zeros. Whereas source terms are normally input to LADTAP in units of curies per year, the source terms in this analysis were input in microcuries per cubic centimeter, as presented in Table 11.C-2. The input values of the variables for constant source-ter m multiplier (UML) and discharge flow (cfs) were adjusted so that the code routines that normally convert curies per year per cubic feet per second to picocuries per liter would convert the input concentrations in microcuries per cubic centimeter to picocuries per liter.Table 11.C-3 lists the pertinent LADT AP dose results.The following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
Revision 52-09/29/2016 NAPS UFSAR 11C-411C.3 DOSES FROM GASEOUS EFFLUENTS Maximum individual doses fr om gaseous ef fluents were evaluated using the NRC GASPAR and NUS Corporation FIDO S computer codes, using m odels given in Regulatory Guide 1.109 (March 1976). The FIDOS code was used to calculate external gamma dose rates at ground level resulting from elevated activity releases. All other dose calculations were performed using the GASPAR code. The source-ter m data entering into the calculations are provided in Section 11C.4. The meteorological da ta are provided in Section 11C.4.3 (/Q and D/Q values: used in GASPAR) and in Section 11C.4.4 (joint frequency da ta: used in FIDOS).
Calculations of maximu m individual doses fr om gaseous ef fluents have been made for the following exposure pathways:1.External gamma doses at ground level to air and tissue.2.External beta doses at ground level to air and tissue.
3.External exposure to materials deposited at ground level.
4.Internal exposure via food chain pathways , including vegetation, meat, cow milk, and goat milk.5.Internal exposure via inhalation.The GASPAR code was used exclusively for pathways 2, 3, 4, and 5, above. All standard or default GASP AR parameter va lues were used, including dose c onversion factors, food intake rates, stable element transfer coefficients, and time delays.Both the GASPAR and FIDOS c odes were used to calculate external gamma dose rates at ground level. The process vents, located on top of the containment structures, were considered as mixed-mode release points. Proc ess vent releases were thus c onsidered as partially elevated and partially ground level. The GASPAR code was used to compute gamma doses at ground level (based on ground-level air c oncentrations) for all releases.
The external gamma doses at ground level due to the elevated portion of the mixe d-mode releases were calculated separately by the FIDOS code and added to the GASPAR results. Thus, for external gamma doses, GASPAR results account for all strictly ground-le vel releases and the ground-level portion of the mixed-mode releases. The total external gamma dose is therefore the sum of the GASPAR and FIDOS results. Table 11.C-4 lists the gaseous sour ce terms used in th e analysis, indicating release rates and release mode.The following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
Revision 52-09/29/2016 NAPS UFSAR 11C-5 The locations of the existence of the va rious exposure pathways, provided in Section 11C.4, were analyzed to determine the indi vidual location where each pathway would result in the maximum dose. For each specifi c pathway, the location where the maximum dose occurs, for the combined releases of all four units, is as given below:
The maximum gamma air dose due to the elev ated portion of the mixed-mode releases for all four units combined was determined to be 0.304 mrad/yr, occurring at 1351 m northeast.
Of this total, the Units 1 and 2 contribution is 0.303 mrad/yr, with Units 3 and 4 contributing the remaining 0.001 mrad/yr.The maximum gamma air dose due to ground-level releases and the ground-level portion of the mixed-mode releases was determined to be 1.44 mrad/yr for all four units combined, occurring at 1377 m east-southeast. Of this total, 0.88 mrad/yr is from Units 1 and 2 while 0.56 mrad/yr is from Units 3 and 4. At this location, the gamma air dose from the elevated portion of the mixed-mode releases is 0.211 mrad/yr, essentially all from Units 1 and 2. Maximum total gamma ai r doses are thus 1.09 mrad/yr from Units 1 and 2, 0.56 mrad/yr from Units 3 and 4, and 1.65 mrad/yr from all four units combined.The maximum beta air dose due to all releases from all four units was determined to be 2.67 mrad/yr (1.65 mrad/yr from Units 1 and 2 and 1.02 mrad/yr from Units 3 and 4), occurring at 1377 m east-southeast.
Maximum doses for each separate pathwa y of human exposure are provided in Table 11.C-5. A grazing season length of 7 months per year has been assumed (Reference 1).The following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
Exposure Pathway Location of Maximum ExposureDistance (m)DirectionGamma air dose, elevated portion of mixed-mode releases1351NE Gamma air dose, ground level and ground-level portion of mixed-mode releases1377ESE Beta air dose, all releases1377ESEPlume, all releases1750S Vegetation2000NEMeat2250NECow milk3250N Goat milk4000ENEInhalation2000E Revision 52-09/29/2016 NAPS UFSAR 11C-6The maximum organ dose to an individual from all exposure pathways existing at any single location has been determined to be the t hyroid dose to an infant at the location of the maximum cow milk exposure pathway dose, 3250 m north. The internal exposure pathways of vegetation and meat ingestio n have also been assumed to exist at this location. Table 11.C-6 provides a summary of doses at this location.
Maximum total body and sk in doses occur at 1750 m south, arising most ly from external exposure to the passing plume and from exte rnal exposure to materials deposited on the ground. Table 11.C-7 provides a summary of doses at this location.11C.4 DATA AND METHODOLOGY11C.4.1 Plant CharacteristicsThe plant characteristics needed for th e radiological evaluation of North Anna are presented below , as requested in Appendix D of Draft Regulatory Guide 1.BB.11C.4.1.1 General1.The maximum core thermal power evaluated for safety considerations in the safety analysis report (SAR): 2900 MWt.2.a.The total mass of uranium and pl utonium in an e quilibrium core: 181,205 lb UO 2 , no plutonium.b.The percent enrichment of uranium in reload fuel: varies-2.10, 2.60, and 3.10 weight percent.c.The percent of fissile plutonium in reload fuel: none.3.The methods and parameters used in estimati ng the source terms in the primary coolant are the same as those given in Regulatory Guide 1.BB.4.The quantity of tritium released in liquid and gaseous ef fluents: 0.4 x 2900 MWt = 1160 Ci/yr/unit.11C.4.1.2 Primary System1.The total mass of coolant in the primary system, excluding the pr essurizer and primary coolant purification system, at full power: 4.34 x 10 5 lb.2.The average primary system letdown rate to the primary coolant purification system:
60 gpm.The following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
Revision 52-09/29/2016 NAPS UFSAR 11C-73.The average flow rate through the primary coolant purification system cation demineralizers: 6 gpm.4.The average shim bleed flow: 6.9 gpm.11C.4.1.3 Secondary System1.Each unit has three U-tube st eam generators. Carryover factor s of 1% for iodine and 0.1%
for non-volatiles were used per draft Regulatory Guide 1.BB, p. B58.2.The total steam flow in the secondary system: 12.2 x 10 6 lb/hr.3.The mass of steam in each st eam generator at full power: 4238.6 lb.4.The mass of liquid in each steam generator at full power: 1.67 x 10 5 lb.5.The total mass of coolant in the secondary system at full power excluding the coolant in the condenser hotwell: 1.0685 x 10 6 lb.6.The primary-to-secondary system leakage: 100 lb/day per draft Regulatory Guide 1.BB, p. B57.7.The average steam generator blowdown rate: 30,000 lb/hr.Each steam generator is provided with blowdow n connections for the control of the solids concentration on the shell (secondary) side of the steam generator
.Each blowdown line contains th ree normally open trip valves:
two inside the containment and one outside. The steam generator blowdown system is divided into two parallel systems. Either can be isolated from the other or both can be operated simultaneously. The first of these systems is called the low-capacity system, in which th e rate of blowdown is manually regulated by hand control valves and the utilities blowdown tank BD-TK-1.
Blowdown from any or all of the three steam generators passes to and flashes in the blowdown tank. The blowdown tank is equipped wi th a vent condenser that condenses the vapor discharged from the tank. Condensate from the blowdo wn tank and vent condenser is drained to the liquid waste disposal system, and noncondensibles are vented to the atmosphere.
Using the low-capacity system, the thr ee steam generators can blow down 10,900 lb/hr of water to the blowdown tank and subsequently to the liquid waste disposal system.The following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
Revision 52-09/29/2016 NAPS UFSAR 11C-8 The other blowdown system is called the hi gh-capacity blowdown sy stem, in which the rate of blowdown is contro lled by flow control valves an d the utilit ies flash tank BD-TK-2. It is used in conjunction with the chemical feed portion of the feedwater system and the condensate polishing system to control the chem ical composition and solids concentration of the feedwater supply to the steam generators. The design of this system allows for heat recovery by use of a flash tank that returns steam to the third-point feedwater heaters and condensate to the condenser hotwell.Normal blowdown will be approximately 30,000 lb/hr with a system design rate of 100,000 lb/hr.
During blowdown, the liq uid passes to the flash tank, where the steam is drawn of f to the third-point feedwater heaters and the liqui d is drained to the condenser hotwell.
A manual bypass is provided around the flash tank for use during tank and control valve maintenance. A pressure control valve on the flash tank vent line is provided to keep a minimum backpressure on the tank to limit the amount of flashing during reduced load operation.
The blowdown from each steam generator is individually monitored for radioactivity. If the radiation monitor detects contamination exceeding a set li mit in the blowdown sample, an alarm is initiated in the main control room.
Blowdown is automatically terminated for any of the following abnormal conditions:a.High-high flash tank level.b.High liquid level in the third-point feedwater heaters.c.High flash tank pressure.d.High condenser pressure.e.Turbine trip.f.Containment isolation signal.8.The fraction of the steam generator fe edwater processed th rough the condensate demineralizers: 0.6593.
The decontamination factors fo r the condensate demineralizer system: 10 for iodine, 2 for Cs and Rb, and 10 for others.The following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
Revision 52-09/29/2016 NAPS UFSAR 11C-99.Condensate demineralizers:a.Average flow rate 8.1+06 lb/hr.b.Demineralizer type: powdered resin type.c.There are five vessels, each containing 300 to 400 lb of resin.
Tank capacity: 2200 gallons = 300 ft 3.d.Regeneration frequency: 20 days per vessel, normal operation.e.Ultrasonic resin cleaning is not used.f.Regenerant volume: 15,000 gallons of water per event. Th ere is no activity associated with the liquid, most of which is fi ltered and returned to the hotwell.11C.4.1.4 Liquid Waste Processing System 1.a.Source, flow rates, and expected activities (fraction of primary coolant activity) for all inputs to each system: Table 11.C-8.b.Holdup times associated with collecti on, processing, and dischar ge of all liquid streams: Table 11.C-8.c.Capacities of all tanks and processing equipment considered in calculating holdup times: Table 11.C-8 and Figure 11C-1.d.Decontamination factors for each processing step: Table 11.C-8.e.Fraction of each processing str eam expected to be dischar ged over the life of the plant: Table 11.C-8.f.Demineralizer regeneration:
time between regenerations-60 days; regenerant volumes-15,000 gallons of water and 300 lb of resin; regenera nt activities-most of the water is filtered and returned to the hotwell with no significant activity. 200 gallons of water slurry is sent to solid waste.g.Liquid source term by radionuclide fo r normal operation including anticipated occupational occurrences: Table 11.C-9.2.North Anna Figures 9.3.5-1 through 9.3.5-4 and 11.2.2-1 through 11.2.2-5 (original FSAR).11C.4.1.5 Gaseous Waste Processing SystemThe following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
Revision 52-09/29/2016 NAPS UFSAR 11C-101.The volumes of gases stripped from the primary coolant: 2 x 10 4 ft 3/yr.2.Section 11.3.3 (original FSAR
), T able 11.3-1 (original FSAR
), and Figure 11.3.2-1 (original FSAR
).3.The gaseous waste disposal system consists primarily of a closed loop of two waste gas compressors, two waste decay tanks, one catal yst recombiner , and co nnecting piping to collect and filter vapors from tanks containing radioactive li quids. The recombiner system, containing two catalyst beds, reduces the hydrogen content of the gas to be stored, thereby reducing the storage volume as well as the hazard inherent in storing hydrogen. A holdup time of 60 days was used.4.Decontamination factor for HEPA filter: 100.5.No charcoal delay system.6.Figures 11.3.2-1 and 11.3.2-2 (original FSAR
).11C.4.1.6 Ventilation and Exhaust Systems1.The steam generator blowdown system vent exhaust is equipped with a vent condenser
.The discharge from the gaseous waste system , the containment pur ge system, and the containment vacuum system, is mixed with filter air from th e auxiliary building and is drawn through charcoal and HEPA filters.2.Charcoal filter dec ontamination factor: 10.
HEPA filter decontam ination factor: 100.3.Release rates for radioiodine, noble gases, a nd radioactive particul ates, and the bases:
Tables 11.C-10 and 11.C-11.The following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
Revision 52-09/29/2016 NAPS UFSAR 11C-115.Containment building free volume: 1.84 + 06 ft 3. Recirculation rate: 4000 cfm.Two 2-inch layers with an air space between, per tray.Mixing efficiency: 70%.
Four cold purges per year of 6 weeks duration.11C.4.1.7 Solid Waste Processing Systems1.Refer to Section 11.5.4 (original FSAR
).2.Refer to Section 11.5.6 (original FSAR
).3.Refer to Figure 11.5-3 (original FSAR
).11C.4.2 Distances to Radiologicall y Significant LocationsTable 11.C-12 provides the distances from the cent erline of the first nuclear unit to the following for each of the 22.5-de gree radial sectors centered on the 16 cardinal compass directions:1.Nearest milk cow (to a distance of 5 miles).
2.Nearest meat animal (to a distance of 5 miles).3.Nearest milk goat (to a distance of 5 miles).4.Nearest residence (to a distance of 5 miles).The following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
4.Height Height Adjacent BuildingFlow RateVelocity (ft/sec)Size Dia.(in.)ShapeProcess ventEl. 428 ft. 6 in.407 ft. 6 in.330 cfm1003CircularVentilation ventsEl. 386 ft. 9 in.376 ft. 2 in.
143,900 108,700 55 41 90 90Circular CircularTurbine building ventsEl. 380 ft.325 ft. 8 in.
10 at 70,000 cfm each, 1 at 8000 cfm 28 377 in 2 SquareTemperature: Ambient.
Revision 52-09/29/2016 NAPS UFSAR 11C-125.Nearest vegetable garden greater than 500 ft 2 (to a distance of 5 miles).6.Nearest site boundary.Elevation data for each specific location are also provided.11C.4.3 Atmospheric Dilution (/Q) and Deposition (D/Q) Parameters The annual average /Q and D/Q values were computed for the North Anna site based on onsite delta T150 ft-35 ft , 35-foot and 150-foot wi nd data. Calculations were made at three release points, two of which were assumed to be at ground level, an d one assumed to be a mixed-release mode. The delta T and 150-foot wi nd data were recorded on the main 150-foot meteorological tower located approximately 1000 feet north-northeast of the nearest containment unit. The 35-foot wind data were recorded on a satellite tower located just north of the main tower. The data period is May 1, 1974, through April 30, 1975. A more detailed description of this facili ty , including sensor accuracy , is contained in Section 2.3 (original FSAR).The distances used in the calculation of /Q and D/Q values are given by exposure direction in Table 11.C-12. The /Q and D/Q values for the tw o ground-level release points are presented in Table 11.C-13. Since the results are iden tical for both releas e points, only one set of tables is presented. The /Q and D/Q values for the mixed release mode are presented in Table 11.C-14.The straight-line airflow model outlined in Regulatory Guide 1.111 (March 1976), which assumes a uniform horizontal dist ribution of the ef fluent within a 22.5-degree sector width, was used to compute annual average /Q values. The open terrain adju stment factors were applied to the /Q values as recommended in Regulatory Guide 1.111. The site region is characterized by gently rolling terrain, so open terrain correc tion factors are considered most appropriate.The ground-level release mode ca lculation was based on de lta T150 ft-35 ft and 35-foot wind data. The mixed-release mode was determined as a function of th e ratio of vent exit velocity and wind speed at th e 150-foot level such that /Q and D/Q values were determined from two different sets of join t frequency distributions of wind speed, direction, and stability class. The portions of the re lease characterized as ground-level were based on delta T 150 ft-35 ft and 35-foot wind data, and the portions characterized as elevated were based on delta T150 ft-35 ft and 150-foot wind data.The following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
Revision 52-09/29/2016 NAPS UFSAR 11C-13The ground-level release calculations contain a building wake factor for a containment height of 136.5 feet; no building wake is a pplied to elevated releases. The effective release height used in the elevated release calculations wa s based on a vent re lease height of 157.5 feet and plume rise due to momentum for a vent diameter of 3 inches and plume exit velocity of 100 ft/sec with appropriate adjustments for terrai n rise and stack downw ash as per Regulatory Guide 1.111 guidance. The process vent rele ase stack is located atop the Unit 1 containment, well removed from higher solid structures.
For the mixed release m ode, the annual average /Q value for each downwind distance is based on the sum of contri butions from elevated and ground release levels.The onsite wind and differential te mperature data for the period May 1, 1974, through Ap ril 30, 1975, were reviewed for their representativeness as compared to the previously reported onsi te data for September 16, 1971, through September 15, 1972 [Section 2.3.2 (original FSAR
)] and Richmond, Virginia, lo cal climatological data (Reference 1) for the current period.The onsite differential temperatur e monthly averages indicated more stable values for the months of February, March, and April. For the remainder of the year, the current onsite monthly differential temperature values indicate more unstable c onditions than for the previous period. This is reflected in an increased annual frequency of occurrence of stability classes A and B with a corresponding annual decrease in the frequency of occurrence of stability classes E and D.A review of the temperatur e data for Richmond, Virginia , for the two period shows a 0.9°F lower annual average temp erature for the period May 1975 through April 1976 than that for the September 1971 to September 1972 period. This is reflected in cooler seasonal averages for winter , spring, and fall for the more rece nt period. The summer av erage was higher by 0.8°F than the previous period. The Richmond annual average temperature for the current period was also 1.3°F cooler than the annual climatological norm of 57.8°F.
The annual average wind speed of 6.8 mph for the 35-foot low-th reshold wind sensor is 0.4 mph less than the 7.2 mph reported for the period of September 16, 1971, to September 15, 1972. The onsite current period average of 6.8 mph compares favorably with the Richmond, Virginia, annual average of 7.0 mph for the same period. It should be noted that the Richmond annual average was 0.6 mph lower than the climatological normal 7.6 mph, and was 0.5 mph lower than the Richmond annual average for September 1971 to September 1972.The following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
Revision 52-09/29/2016 NAPS UFSAR 11C-14 The annual wind direction di stribution from the 35-foot wind sensor for the May 1974 through April 1975 period compared fa vorably with the onsit e distribution for the September 1971 to September 1972 period and the Richmond, Virginia, monthly climatological prevailing wind directions. The current period onsite data show a prevailing southerly wind flow with an almost equivalent northerly flow. The we sterly components of these cardinal directions were more prevalent than the easter ly components. This same wind flow pattern was seen in th e onsite data for September 1971 to September 1972. On an annual basis, the more recent period shows a slight incr ease of the occurrence of south-southwest and southwest winds over the earlier period. The annual prevailing climatological wind flow at Richmond, Virginia, is southerly.
The annual average wind speed and the annual wind direction distribut ion of the 150-foot wind sensor agree favorably with the 35-foot sensor. The wind di rection distribution showed a slightly stronger north-south orientation than the lower level. The annual wind speed was 7.2 mph.Based upon the above analysis, the May 1974 through April 1975 onsite wind speed and wind direction data are re presentative of the onsite conditions. The onsite data reflect the same decrease in average wind speed, when compared to the onsite September 1971 to September 1972 data, as observed in the Richmond data for the same periods. The May 1974 through April 1975 onsite data maintain the same prevailing wind directions found in the earlier onsite data and agree with th e prevailing normal flow at Richmond.
The representativeness of the differential temperature data is also representative of the onsite conditions for the period May 1974 through April 1975. The increased occurr ence of stability Class A is attributed to potential increased influences of plant construction and land-lake interaction than that experienced in the earlier repor ting period. With the installation of the upgraded meteorological sy stem as described in Section 2.3.3.2 (original FSAR
), it is anticipated that all significant influences of permanent and temporar y plant structures and continuing construction activities will be elimina ted from the meteor ological monitoring system.11C.4.4 Meteorological DataThe annual and monthly joint frequency distributions of wind speed and wind direction by atmospheric stability class for the period May 1, 1974, through April 30, 1975, are provided in Table 11.C-15. The stability classes were determined from differential temperature between the 35-foot and 150-foot instrume nt levels of the current meteorological tower. The lower-level wind sensor is the 35-foot low-threshold sensor located on the satellite wind mast. The upper-level wind sensor is the 150-foot sensor located on the current tower.The following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
Revision 52-09/29/2016 NAPS UFSAR 11C-15The onsite and near-site atmo spheric transport and diffusio n conditions at the plant are primarily related to synoptic weather systems and local microscale effects. Since the meteorological tower is located between the plant and the lake [see the location of the met tower, Figure 2.3.3.2-1 (original FSAR
)], the data obtained from th e meteorological system are re presentative, within the limits of the instrumentation accuracies, of the onsite diffusion conditions. The data may include the occurrences of weak lake breezes that may form during weak synoptic wind conditions. Since the lake adjacent to the plant site is narrow (distance to opposite shore varies from approximately 5400 feet toward the north, 2800 feet toward the northeast, to 7200 feet toward the east), and considering its complex configur ation and size, it is not expected that the lake breeze that may be experienced at the plant site would extend inland to any great extent. See Section 2.3.2.3 (original FSAR) for additional discussion. The predominant westerly flow at th e 35-foot level for F and G stab ilities during light wind speeds reflects drainage flow from the hi gher terrain (maximum elevation 400 feet MSL) south through northwest of the plant. This drainage is to be expected and was discussed previously in Sec tion 2.3.2.4 (original FSAR
).The wind speed and wind direction data collect ed from the meteorol ogical tower site are also representative of the near-site area since the area consists ma inly of gently rolling terrain that allows synoptic scale weather conditions to predominate over local terrain influences for all conditions except light wind speeds and temperature extremes. Wi thin a 5-mile radius of the plant, the greatest variation of ground elevation a bove the surface of the lake along the centerline of each 22.5-degree wind sector centered on north, is 190 feet. As discussed in Sec tion 2.3.2.4 (original FSAR
), this is typical of the area.The near-site representativeness of the differ ential temperature data may decrease as the distance between the point of interest and the lake increases. Potential influences from the temporary construction buildings a nd storage yard to the southeast of the tower may also affect the representativeness of the differential temperature data for the near-site area. This potential influence will not exist at th e upgraded meteorological system discussed in Section 2.3.3.2 (original FSAR
).The wind speed and wind direction data being re ported are expected to be representative of the general long-term conditions at and near the pow er station. Future plant additions of Units 3 and 4 will not alter the representa tiveness of the differential temperature data for the area near the plant site. The new structures will alter the microscal e flow in the vicinity of the current structures, but these influen ces should not be significant beyond 1365 feet of each new containment.The following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
Revision 52-09/29/2016 NAPS UFSAR 11C-16 The location of the onsite meteorological tower is discussed in Section 2.3.3.1.1 (original FSAR) and shown in Figure 2.3.3.2-1 (original FSAR
). The accuracy of the instrumentation used is discussed in Section 2.3.3.1.1 (original FSAR
).The data were collected on st rip-chart recorders at the base of the tower. These strip charts were later digitized in to 1-hour averages by manually averaging the signal trace for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with the time period centered on the hour.
The data being submitted were collected by the original onsite meteorological program.
An upgraded, onsite meteorological monitoring system is currently under operation and is discussed in Section 2.3.3.2 (original FSAR
). The upgraded system meets the recommendations and intent of Regulatory Guide 1.23, dated February 17, 1972.Table 11.C-15 presents the monthly and annual joint frequenc y distributions of wind speed and direction by atmosphere stability class (based on delta T measurements) for the ground (35-foot) and elevated (150-foot) levels derived from onsite measurements at North Anna during the period May 1, 1974, to April 30, 1975.11C.4.5 TopographyWith a plant elevation of 271 feet MSL, the maximu m variation of terr ain elevation from this level, along the radials for whic h dose calculations were made, is 129 feet, and is found in the west-southwest sector. Of the remaining sectors, six have terrain va riations from the 271-foot level of less than or equal to 40 feet, six have variations between 40 feet and 60 feet, and three have variations between 80 feet and 100 feet. The higher terrain variations occur in the north-northeast, west-southwest, west, an d west-northwest sector
- s. As discussed in Section 2.3.2.4 (original FSAR
), in the Central Piedmont area of Virginia, the terrain varies between 200 to 500 feet MSL. With the exception of the lake, the near-site area does not have topographic features significantly different from the general area.Of the 16 trajectories, those into the west-sou thwest and southwest do not pass ove r water. Of the remaining trajectories, five have over-water segments totaling less than or equal to 0.5 miles, four have over-water se gments totaling between 0.5 and 1 mile, three have over-water segments totaling 1 mile to 1.5 miles, and two, thos e into the ea st-southeast and southeast sectors, have over-wate r segments totaling from 2 to 2.5 miles. It should be noted that many of these over-water segment totals consist of several shorter segments that are separated by terrain.The following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
Revision 52-09/29/2016 NAPS UFSAR 11C-17 For the annual period, the prevailing wind flow was southerly with a secondary major flow from the north. The westerly components of both of these directions were more prevalent than the easterly. This pattern is in good agreem ent with the expected synoptic flow and with the prevailing wind direction patter n reported for the period September 16, 1971, through September 15, 1972.The Regulatory Guide 1.111 open-terrain correction factor as determined by Figure 2 of the Regulatory Guide was used based upon the gen tly rolling characteristi c of the terrain, the shortness of the majority of the over-water trajectory se gments, and the good agreement between the onsite wind flow and the expected synoptic flow (except during low wind speeds).
Three sets of origin al U. S. Geographic Survey (U SGS) maps showing detailed topographic features within a 10-mile radius have been submitted separately. Elevation data pertaining to specific locations where doses are calculated have been included in Table 11.C-12. The maximum elevation, by sector , within 1-mile increments out to 10 miles, is provided in Table 11.C-16.11C.5 SOURCE-TERM INFORMATION The Appendix I evaluation presented in Section 11C.1 is based on radioactive release rates for Units 3 and 4 as presented in the North Anna FES (Reference 1). The following discussion pertains to the calcul ation of new source te rms for Units 1 and 2 based on revised calculational models and re lated guidance as contained in Draft Regulatory Guide 1.BB.The source terms (primary c oolant and secondary-side liqui d and steam radioactivities) and the resulting radioactive releases (liquid and gaseous) are calculated using the basic assumptions and approaches contai ned in Draft Regulatory Guide 1BB.The PWR-GALE code used by the NRC staff is not used in these analyses. However , the procedures that are used provide essentially the same mathematical treatments. Values of parameters, such as flow ra tes, are based on the North Anna Units 1 and 2 design as described in the main body of the FSAR. In some instances, standard NRC staf f assumptions are used in lieu of the designer's values in orde r to fit the Draft Regulatory Guide 1.BB analysis for North Anna Units 1 and 2 as closely as possibl e to the NRC staff's an alytical approach. The staff's model is inflexib le in some respects an d is expected to lead necessarily to slightly different results than t hose from this analysis.
VEPCO has reported expected liquid and gaseous release values in the main body of the FSAR. The data described herein represent an attempt to anal yze the releases using the NRC model and assumptions as closely as VEPCO could configure them.The following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
Revision 52-09/29/2016 NAPS UFSAR 11C-18Table 11.C-17 contains the parameters used in determining source terms; Table 11.C-18 lists the source terms.
In Section 11C.4 , Table 11.C-10 contains the parameters us ed in determining gaseous releases; Table 11.C-11 lists the gaseous re leases. As shown in Table 11.C-10 , the gaseous releases from the cont ainment are based on four cold pur ges per year. Also, before purging, the two 4000-cfm recirculation fans are run for a period of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> with a HEPA filter efficiency of 99%, a charcoal adsorber efficiency of 90%, and a mixing efficiency of 70%. The purges are at a rate of 22,000 cfm and are passed through HEPA filte rs and charcoal adsorbers with efficiencies of 99% and 90%, respectively.The calculated gaseous releases from the turbine building, the auxiliary building, and the main condenser air ejector are based on the as sumption that gaseous releases are unfiltered.Table 11.C-8 contains the parameters used in determining liquid releases, and Table 11.C-9 lists the liquid releases.
Figure 11C-1 is a diagram of the liquid waste s ystem that augments Table 11.C-8.11C REFERENCES1.U. S. Atomic Energy Commission, Final Environmental Statement Related to the Continuation of Construction and the Operation of Units 1 and 2 and the Construction of Units 3 and 4 , North Anna Power Station, Virginia Electric and Power Company , Docket Nos. 50-338, 50-339, 50-404, and 50-405, Directorate of Licensing, 1973.2.T. J. Wirth and Associates, A Land Use Plan for North Anna Reservoir, Virginia , Chevy Chase, Md., 1971.3.National Oceanic and At mospheric Administration, Local Climatological Data , 1975, Richmond, Virginia , Environmental Data Service, National Climatic Center, Asheville, N.C., 1975.The following information is HISTORICAL and is not intended or expec ted to be updated for the life of the plant.
Revision 52-09/29/2016 NAPS UFSAR 11C-19The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-1COMPARISON OF RESULTS WITH DESIGN OBJECTIVES CONTAINED IN RM 50-2 Applicable Section ofRM 50-2Evaluation Design Objective sAnalysis Results Units 1 and 2 Units 3 and 4 Units 1-4 aA.1Maximum dose from liquid effluents: any organ (mrem/yr)50.823.214.05A.2Quantity of liquid effluent (Ci/yr less H 3 and gases)50.221.01.22B.1Maximum gamma air dose (mrad/yr) 101.090.561.65B.2Maximum beta air dose (mrad/yr)201.651.022.67B.3Maximum doses from gaseous effluents: Total body (mrem/yr) 51.930.092.03 Skin (mrem/yr) 152.580.262.84C.1Maximum dose from iodine and particulates in gaseous effluents: any organ (mrem/yr) 157.461.288.74C.2 Maximum I-131 gaseous release (Ci/yr/reactor)10.0970.018--a.Slight discrepancies in totals for all four units because of round-off error.
Revision 52-09/29/2016 NAPS UFSAR 11C-20The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-2 RADIOACTIVITY CONCENTRATIONS DUE TO LIQUID EFFLUENTS (µCi/cc)IsotopeUnits 1 and 2 CombinedUnits 3 and 4 CombinedUnits 1-4 CombinedDischargeWHTFLake AnnaDischargeWHTFLake AnnaDischargeWHTFLake AnnaCr-511.86-131.54-131.35-132.35-141.96-141.73-141.81-131.74-131.53-13Mn-543.82-133.66-133.54-138.63-148.28-148.00-144.51-134.49-134.34-13 Fe-558.24-137.98-137.76-132.50-132.42-132.36-131.04-121.04-121.01-12 Fe-591.73-131.51-131.38-133.49-143.07-142.81-141.87-131.82-131.66-13 Co-583.50-123.18-122.97-121.33-121.21-121.13-124.46-124.39-124.11-12 Co-603.77-123.66-123.56-121.19-131.15-131.12-133.78-123.77-123.67-12 Sr-895.81-145.13-144.73-144.04-143.59-143.31-148.94-148.73-148.03-14 Sr-904.75-154.62-154.51-155.06-154.93-154.81-159.56-159.55-159.31-15 Sr-918.22-161.06-161.19-175.81-167.78-178.71-187.11-161.84-162.06-17 Y-902.59-161.07-164.86-170.00.00.01.52-161.07-164.86-17 Y-91m5.03-167.31-188.01-202.29-163.46-183.79-203.64-161.08-171.18-19 Y-913.16-132.83-132.62-135.07-154.57-154.24-152.93-132.87-132.66-13 Y-933.52-164.79-175.71-184.23-175.98-187.14-191.98-165.39-176.42-18 Zr-951.64-131.48-131.38-137.79-157.07-156.59-151.58-131.55-131.44-13 Nb-951.54-131.31-131.18-135.46-154.69-154.21-151.40-131.36-131.22-13 Mo-993.75-111.56-117.24-124.55-131.96-139.05-142.24-111.58-117.33-12 Tc-99m1.96-111.75-121.30-133.67-133.41-142.53-159.88-121.79-121.33-13 Ru-1031.61-141.39-141.26-144.19-153.64-153.30-151.81-141.76-141.59-14 Ru-1065.76-135.53-135.35-133.78-153.64-153.52-155.59-135.57-135.39-13 Rh-103m3.30-155.38-176.63-199.37-161.59-171.96-192.10-156.97-178.59-19 Revision 52-09/29/2016 NAPS UFSAR 11C-21Rh-1064.43-146.64-187.36-222.60-164.05-204.49-242.19-146.68-187.40-22Te-125m2.06-141.85-141.71-144.73-144.26-143.95-146.23-146.11-145.66-14 Te-127m5.04-134.68-134.45-135.47-135.11-134.85-139.91-139.79-139.30-13 Te-1277.67-149.82-151.09-156.87-149.12-151.01-157.38-141.89-142.10-15 Te-129m1.36-121.15-121.03-122.43-122.08-121.86-123.34-123.23-122.88-12 Te-1292.05-134.15-156.37-173.90-138.20-151.26-163.00-131.23-141.89-16 Te-131m3.46-139.65-142.74-148.50-152.45-156.96-161.89-139.89-142.81-14 Te-1315.94-144.41-162.44-181.46-141.12-166.20-193.67-145.53-163.06-18 Te-1325.73-172.57-121.30-122.85-121.32-126.64-135.25-123.89-121.96-12 Ba-137m1.08-128.28-164.70-194.94-133.93-162.23-197.83-131.22-156.93-19 Ba-1401.23-148.81-156.94-151.94-141.41-141.11-142.50-142.29-141.80-14 La-1404.39-151.44-154.97-167.66-152.59-158.98-166.76-154.03-151.39-15 Ce-1419.40-157.93-157.08-155.42-154.61-154.11-151.30-141.25-141.12-14 Ce-1433.98-161.17-163.55-171.72-165.24-171.59-173.09-161.69-165.14-17 Ce-1441.12-121.07-121.03-121.04-141.00-149.67-151.08-121.08-121.04-12 Pr-1432.68-151.94-151.55-152.39-151.75-151.40-154.01-153.69-152.94-15 Pr-144 8.65-144.45-161.70-187.81-164.17-181.60-204.29-144.49-161.72-18 Np-2393.17-141.23-145.23-154.39-151.76-157.48-162.09-141.41-145.98-15 Br-832.33-149.28-162.88-170.00.00.01.14-149.28-162.88-17 Br-841.68-151.56-171.09-190.00.00.08.23-161.56-171.09-19 Br-851.89-171.63-201.04-230.00.00.09.30-181.63-201.04-23The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-2 (continued)RADIOACTIVITY CONCENTRATIONS DUE TO LIQUID EFFLUENTS (µCi/cc)IsotopeUnits 1 and 2 CombinedUnits 3 and 4 CombinedUnits 1-4 CombinedDischargeWHTFLake AnnaDischargeWHTFLake AnnaDischargeWHTFLake Anna Revision 52-09/29/2016 NAPS UFSAR 11C-22I-1307.18-141.13-141.60-152.56-134.18-145.92-151.70-135.31-147.53-15I-1315.74-113.61-112.55-117.15-104.59-103.24-105.65-104.95-103.50-10 I-1324.54-121.73-135.12-152.50-119.89-132.92-141.50-111.16-123.44-14 I-1331.93-114.31-129.32-158.22-111.90-114.11-125.39-112.33-115.04-12 I-1345.94-149.11-161.05-170.00.00.02.92-149.11-161.05-17 I-1353.32-123.21-132.59-141.15-111.16-129.35-147.58-121.48-121.19-13 Rb-869.70-157.50-156.29-151.82-141.43-141.20-142.31-142.18-141.83-14 Rb-88 7.56-153.99-171.56-191.87-131.02-154.02-189.93-141.06-154.17-18 Cs-1341.95-111.89-111.84-114.25-114.12-114.00-116.03-116.01-115.84-11 Cs-1361.13-128.12-136.42-132.08-111.52-111.20-111.74-111.60-111.26-11 Cs-1372.32-112.26-112.21-113.58-113.49-113.41-115.76-115.76-115.61-11 H-34.52-064.34-064.21-067.77-067.49-067.25-061.19-051.18-051.15-05The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-2 (continued)RADIOACTIVITY CONCENTRATIONS DUE TO LIQUID EFFLUENTS (µCi/cc)IsotopeUnits 1 and 2 CombinedUnits 3 and 4 CombinedUnits 1-4 CombinedDischargeWHTFLake AnnaDischargeWHTFLake AnnaDischargeWHTFLake Anna Revision 52-09/29/2016 NAPS UFSAR 11C-23The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-3MAXIMUM INDIVIDUAL DOSES FROM LIQUID EFFLUENTSLADTP Dose Results (mrem/yr)AdultsChildrenInfantsTotal BodyLiverThyroidTotal BodyLiverThyroidTotal BodyLiverThyroidI.Units 1 and 2Fish ingestion1.81-12.40-14.52-24.21-22.04-13.70-2------Water ingestion4.15-14.16-14.47-14.37-14.43-15.04-16.61-16.76-18.24-1Shoreline use2.12-42.12-42.12-42.47-42.47-42.47-4------Swimming2.30-52.30-52.30-52.30-52.30-52.30-5------
Boating5.99-65.99-65.99-63.34-63.34-63.34-6------Totals5.96-16.56-14.92-14.79-16.47-15.41-16.61-16.76-18.24-1II.Units 3 and 4Fish ingestion3.59-14.70-14.28-18.50-23.88-13.85-1------
Water ingestion7.15-17.18-11.157.55-17.66-11.611.141.173.21Shoreline use3.14-43.14-43.14-43.66-43.66-43.66-4------
Swimming2.03-42.03-42.03-42.03-42.03-42.03-4------Boating5.27-55.27-55.27-52.94-52.94-52.94-5------Totals1.071.191.588.41-11.152.001.141.173.21III.Units 1-4Fish ingestion5.23-16.87-13.52-11.23-15.75-13.11-1------
Water ingestion1.131.141.601.201.212.121.811.854.05 Shoreline use5.10-45.10-45.10-45.95-45.95-45.95-4------Swimming9.32-59.32-59.32-59.32-59.32-59.32-5------Boating2.42-52.42-52.42-51.35-51.35-51.35-5------
Totals1.651.831.951.321.792.431.811.854.05 Revision 52-09/29/2016 NAPS UFSAR 11C-24 The following information is HI ST ORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-4 GASEOUS SOURCE TERMS BY ISOTOPE AND RELEASE MODE (Ci/yr released)
Isotope Units 1 and 2 Units 3 and 4 Ground Level Mixed-Mode Ground Level Mixed-ModeKr-83m 1.52 8.80-1 4.00 0.0Kr-85m 7.64 1.06+1 2.00+1 0.0Kr-85 2.33+1 4.00+2 8.00 1.47+3Kr-87 4.50 1.76 1.20+1 0.0Kr-88 1.46+1 1.28+1 3.20+1 0.0Kr-89 3.64-1 6.20-3 2.00 0.0 Xe-131m 1.26+1 2.40+2 1.00+1 8.00 Xe-133m 1.74+1 1.86+2 2.60+1 0.0 Xe-133 1.64+3 2.60+4 1.85+3 1.40+1 Xe-135m 9.80-1 7.80+2 2.00 0.0 Xe-135 2.49+1 7.00+1 5.40+1 0.0 Xe-137 6.80-1 1.34-2 0.0 0.0 Xe-138 3.28 2.40-1 8.00 0.0 I-131 1.95-1 0.0 3.60-2 0.0 I-133 2.50-1 0.0 3.80-2 0.0Co-58 1.22-1 0.0 0.0 0.0Co-60 5.48-2 0.0 0.0 0.0 Mn-54 3.65-2 0.0 0.0 0.0 Fe-59 1.22-2 0.0 0.0 0.0Sr-89 2.64-3 0.0 0.0 0.0Sr-90 4.07-4 0.0 0.0 0.0 Cs-134 3.65-2 0.0 0.0 0.0 Cs-137 6.09-2 0.0 0.0 0.0Ar-41 5.00+1 0.0 0.0 0.0C-14 0.0 1.60+1 0.0 0.0H-3 1.16+3 0.0 0.0 0.0a.Some small Units 1 and 2 mixed-mode particulate releases were conservatively assume d to be ground-level releases for simplicity.
Revision 52-09/29/2016 NAPS UFSAR 11C-25The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-5MAXIMUM DOSES FOR PATHWAYS OF EXPOSURE TO GASEOUS RELEASES Exposure Pathway Location ofMaximumMaximum Total-Body Dose (mrem/yr)Maximum Thyroid Dose (mrem/yr)
Age Group Units 1 and 2 Units 3 and 4 Units1-4Age GroupUnits 1 and 2Units 3 and 4Units 1-4Plume1750 m SAll4.47-19.16-25.39-1All a8.66-12.63-11.13Ground plane1750 m SAll1.372.26-41.37All a1.602.75-41.60Vegetation2000 m NEChild6.80-15.92-46.81-1Child1.892.57-12.14Meat2250 m NEAdult7.24-22.66-57.24-2Child1.34-11.58-21.50-1 Cow milk3250 m NInfant2.54-12.26-32.56-1Infant6.971.258.22 Goat milk4000 m ENEInfant1.77-18.58-41.78-1Infant2.714.74-13.18 Inhalation2000 m EAdult1.55-11.05-41.55-1Infant7.80-11.21-19.01-1a.For the plume and ground-plane exposure pathways, skin doses are shown instead of thyroid doses.
Revision 52-09/29/2016 NAPS UFSAR 11C-26 The following information is HI ST ORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-6MAXIMUM ORGAN DOSE FROM GASEOUS RELEASES a Annual Dose (mrem)
Exposure Pathway Units 1 and 2 Units 3 and 4 Units 1-4 Plume (noble gases) 1.78-1 3.25-22.11-1 Ground plane 2.81-1 4.63-5 2.81-1Vegetation 0.0 0.0 0.0 Meat 0.0 0.0 0.0 Cow milk 6.97 1.25 8.22 Inhalation 2.09-1 3.25-2 2.42-1Total non-noble gas 7.46 1.28 8.74 Overall total 7.64 1.31 8.95a.Receptor location: 3250 m N; receptor, organ: infant, thyroid.
The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-7MAXIMUM TOTAL BODY AND SKIN DOSES FROM GASEOUS RELEASES a Exposure Pathway Annual Dose (mrem)Units 1 and 2Units 3 and 4Units 1-4Total BodySkinTotal BodySkinTotal BodySkinPlume4.47-18.66-19.16-22.63-15.39-11.13 Ground plane1.37 1.60 2.26-42.75-41.371.60 Inhalation1.17-11.12-18.16-50.01.17-11.12-1 Totals1.93 2.589.19-22.63-12.032.84a.Receptor location: 1750 m S; receptor: adult.
Revision 52-09/29/2016 NAPS UFSAR 11C-27The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-8 LIQUID WASTE PROCESSING SYSTEMStreamNumberStream Feed, gpdCollectionTime, hr ProcessTime, hrDischargeTime, hrTotalTime, hrDensity, 6H/6ALType of ActivityFraction of Activity 1Steam generator blowdown7.20+030025.725.73745 Secondary liquid1.02Sampling sinks4.52+0162811.125.7664.83745P.C.1.03Primary coolant leakage1.78+01P.C.1.04Laboratory wastes5.52+01P.C.1.0 5Spent-resin flush3.47+01P.C1.06Laundry drains5.21+020025.725.73745 See Reg. Guide 1.BB, Table B-181.0 7 Boron recovery system (reactor coolant letdown)1.07+0420980.025.7314.73745P.C1.0-1.0 8 Boron recovery system (reactor coolant drains)3.00+02P.C.1.0 9 Condensate leakage to turbine building sumps1.95+0300003745 Secondary steam1.0 Revision 52-09/29/2016 NAPS UFSAR 11C-28The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11C-8 (continued)
LIQUID WASTE PROCESSING SYSTEMStreamNumberStream Flow Rateto Tank 1, gpd Capacity ofTank 1, gal Flow Rateto LastTank, gpd Capacity ofLast Tank, galFraction ExpectedTo BeDischarged Number of BatchesPer YearSystemDfs, Total 1Steam-generator blowdown7.20+0325,000NANA1.0340 10 I, MO, TE, 10 22Sampling sinks1.529+025000864025,0001.014 10 4 2 10 5 MO TE, 10 6 , Others3Primary coolant leakage4Laboratory wastes 5Spent-resin flush6Laundry drains blowdown5.21+02250,000NANA1.0340 10 I, MO, TE, 10 2 Others 7 Boron recovery system (reactor coolant letdown)1.10+04120,000230425,0001.041.8 10 5 I, 20 Cs, Rb 10 6 MO, TE, 10 Others 8 Boron recovery system (reactor coolant drains) 10 5 I, 10 6 MO, TE, 10 6 , Others 9 Condensate leakage to turbine building sumpsNANANANA1.01.01.0 All Revision 52-09/29/2016 NAPS UFSAR 11C-29 The following informat ion is HISTORICAL an d is not intended or expected to be updated for the life of the plant.Table 11.C-9 TOTAL LIQUID RELEASES Isotope Activity (µCi/g)Release (Ci)Cr-51 2.6E-14 9.4E-05Mn-54 1.4E-14 5.3E-05 Fe-55 2.4E-14 8.9E-05 Fe-59 1.7E-14 6.4E-05 Co-58 2.7E-13 9.7E-04 Co-60 1.0E-13 3.8E-04Sr-89 5.5E-15 2.0E-05Sr-90 1.2E-16 4.5E-07Sr-91 4.2E-16 1.5E-06Y-90 1.1E-16 3.9E-07Y-91m 2.5E-16 9.3E-07Y-91 2.7E-14 9.9E-05Y-93 1.8E-16 6.4E-07Zr-95 1.3E-14 4.8E-05 Nb-95 1.8E-14 6.7E-05Mo-991.5E-11 5.6E-02Tc-99m 9.7E-12 3.6E-02 Ru-103 1.8E-15 6.5E-06 Ru-106 2.1E-14 7.6E-05 Rh-103m 1.7E-15 6.1E-06 Rh-106 2.2E-14 8.2E-05Te-125m 1.8E-15 6.5E-06Te-127m 2.9E-14 1.1E-04Te-127 3.9E-14 1.4E-04Te-129m 1.7E-13 6.1E-04Te-129 1.0E-13 3.8E-04Te-131m 1.6E-13 5.9E-04Te-131 2.9E-14 1.1E-04Te-132 2.2E-12 8.2E-03 Ba-137m 5.5E-13 2.0E-03 Ba-140 2.8E-15 1.0E-05 Revision 52-09/29/2016 NAPS UFSAR 11C-30 La-140 2.0E-15 7.2E-06 Ce-141 1.2E-15 4.3E-06 Ce-143 1.8E-16 6.7E-07 Ce-144 4.3E-14 1.6E-04Pr-143 5.7E-16 2.1E-06Pr-144 4.2E-14 1.6E-04 Np-239 1.3E-14 4.9E-05Br-83 1.2E-14 4.3E-05Br-84 8.5E-16 3.1E-06Br-85 9.6E-18 3.5E-08 I-130 3.5E-14 1.3E-04 I-1311.6E-11 5.9E-02 I-132 2.3E-12 8.4E-03 I-133 9.2E-12 3.4E-02 I-134 3.1E-14 1.1E-04 I-135 1.7E-12 6.1E-03 Rb-86 1.7E-15 6.3E-06 Rb-88 3.8E-15 1.4E-05 Cs-134 6.0E-13 2.2E-03 Cs-136 2.5E-13 9.1E-04 Cs-137 6.0E-13 2.2E-03 H-3 3.5E-02 5.8E+02Grams released 3.7E+15Notes:Isotope releases of less than 1.E-10 Ci/yr are set to 0.0.
Anticipated operational occu rrences: 1.50E-01 Ci added to release.
Blowdown rate: 3.66+15 g/yr.
Total release (excluding tritium) is 2.2E-01 Ci.
Total release (excluding tritium) is 6.0E-11
µCi/g.The following informat ion is HISTORICAL an d is not intended or expected to be updated for the life of the plant.Table 11.C-9 (continued)TOTAL LIQUID RELEASESIsotopeActivity (µCi/g)Release (Ci)
Revision 52-09/29/2016 NAPS UFSAR 11C-31 The following information is HIST ORICAL and is not in tended or expected to be updated for the life of the plant.Table 11.C-10 GASEOUS RELEASES FOR NORTH ANNA UNITS 1 AND 2 Input ParametersValuePlant capacity factor 0.8 Containment buildingNoble gas release to containment bu ilding (fraction per day of primary coolant activity) 0.01 Iodine release to containment build ing (fraction per day of primary coolant activity) 0.00001Following recirc. program assumes instant cold purge Following recirc. exhaust ventil ation rate used for hot pur gePurge exhaust ventilation rate, cfm 2.20E+04Purge exhaust vent ilation time, hr 1.01E+03Iodine exhaust filter efficiency, %
9.00E+0lParticulate exhaust filter efficiency 9.90E+0l %Number of hot purges per year 0.0Number of cold purges per year 4.00E+00 Continuous ventilation exhaust rate, cfm 0.0 Continuous ventilation exhaust rate set to zero during pur ge Containment volume, ft 3 1.84E+06 Containment internal cleanup system Containment internal clean system operatesPrior to purging cold shutdown 1.60E+0lPrior to purging hot shutdown 1.60E+0lContainment internal cleanup system mixing ef ficiency 0.70 Recirculation rate, cfm 4.00E+3Iodine filter efficiency, %
9.00E+0lParticulate filter efficiency, %
9.90E+0l Auxiliary building Iodine exhaust filter efficiency 0.0%Particulate exhaust filter efficiency 0.0%Primary coolant leakage rate into building, lb/day 1.60E+02 Iodine partition factor 7.50E-03 Revision 52-09/29/2016 NAPS UFSAR 11C-32Turbine building No special design to collect valv e leakage (2.5 inches or lar ger)Iodine exhaust filter efficiency, %
0.0Particulate exhaust filter efficiency, %
0.0Steam leakage, lb/hr 1700 Main condenser air ejectorVolatile iodine/total iodine in primar y system (V olatile iodine is treated as noble gas in steam generator) 0.05 Primary to secondary leak rate, lb/day 100 MC/AE volatile iodine partition factor 0.15Iodine exhaust filter efficiency, %
0.0Particulate exhaust filter efficiency, %
0.0 Condenser bypass fraction 0.0Steam generator blowdown flash tank is vented through the main condenser Offgas system No process Holdup time prior to offgas process, min 8.64E+04Exhaust filter iodine efficiency, %
90.0Exhaust filter particulate efficiency, %
99.10 Decay schemesKr-85m to Kr-85 (branching fraction 0.218)
Xe-133m to Xe-133 (b ranching fraction 1.000)
The following information is HIST ORICAL and is not in tended or expected to be updated for the life of the plant.
Table 11.C-10 (continued)
GASEOUS RELEASES FOR NORTH ANNA UNITS 1 AND 2 Input ParametersValue Revision 52-09/29/2016 NAPS UFSAR 11C-33The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-11 GASEOUS RELEASES (Ci/yr/reactor)
Nuclide Containment BuildingAuxiliary BuildingTurbine BuildingMain Condenser/ Air Ejector Blowdown Flash TankOffgas SystemTotalKr-83m4.9E-054.7E-014.1E-05 2.9E-01 0.0 4.4E-01 1.2E+00Kr-85m2.0E-022.3E+002.1E-041.5E+000.05.3E+009.1E+00 Kr-851.1E+014.0E-01 3.5E-052.5E-010.02.0E+022.1E+02 Kr-876.2E-061.4E+001.1E-18.5E-010.08.8E-01 3.1E+00 Kr-885.4E-034.5E+003.8E-042.8E+000.06.4E+001.4E+01 Kr-890.0 1.1E-011.0E-057.2E-020.03.1E-031.9E-01 Xe-131m5.0E+008.1E-017.0E-055.0E-01 0.01.2E+021.3E+02 Xe-133m3.2E+00 3.4E+00 3.0E-042.1E+000.09.3E+011.0E+02 Xe-1335.0E+02 2.0E+021.7E-021.2E+020.01.3E+04 1.3E+04 Xe-135m 0.0 3.0E-012.6E-051.9E-010.03.9E+023.9E+02 Xe-135 4.5E-01 7.4E+006.5E-044.6E+000.03.5E+014.8E+01 Xe-1370.0 2.1E-011.8E-051.3E-010.06.7E-036.7E-03 Xe-1380.0 1.0E+008.7E-056.4E-010.01.2E-011.8E+00 I-1318.5E-045.9E-025.9E-043.7E-020.00.09.7E-02 I-1337.4E-057.6E-02 7.6E-044.8E-02 0.00.0 1.2E-01 Co-587.5E-046.0E-020.0 0.00.02.0E-046.1E-02 Co-603.4E-04 2.7E-020.0 0.0 0.0 7.1E-05 2.7E-02 Mn-542.2E-041.8E-020.0 0.0 0.0 4.8E-051.8E-02 Fe-59 7.5E-056.0E-03 0.00.00.02.5E-056.1E-03 Sr-891.7E-051.3E-030.0 0.0 0.0 5.1E-061.3E-03 Revision 52-09/29/2016 NAPS UFSAR 11C-34Sr-903.0E-062.0E-040.0 0.0 0.06.0E-072.0E-04Cs-134 2.2E-04 1.8E-020.0 0.0 0.0 4.6E-051.8E-02Cs-1373.8E-043.0E-020.0 0.0 0.0 7.5E-053.0E-02 C-14 0.0 0.0 0.0 0.0 0.08.0E+008.0E+00Ar-41 2.5E+010.0 0.0 0.0 0.0 0.0 2.5E+01H-3 0.0 0.0 0.0 0.0 0.0 0.0 5.8E+02Releases via Ventilation Vent aKr-83m4.9E-054.7E-010.0 2.9E-010.0 0.0 7.6E-01Kr-85m2.0E-022.3E+000.01.5E+000.0 0.0 3.8E+00Kr-85 1.1E+014.0E-010.02.5E-010.0 0.0 1.1E+01Kr-876.2E-061.4E+000.08.5E-010.0 0.0 2.2E+00Kr-885.4E-034.5E+000.02.8E+000.0 0.0 7.2E+00Kr-890.01.1E-010.07.2E-020.0 0.0 1.9E-01Xe-131m5.0E+008.1E-010.05.0E-010.0 0.0 6.3E+00Xe-133m3.2E+003.4E+000.02.1E+000.0 0.0 8.8E+00Xe-1335.0E+022.0E+020.01.2E+020.0 0.0 8.2E+02Xe-135m0.03.0E-010.01.9E-010.0 0.0 4.8E-01Xe-1354.5E-017.4E+000.04.6E+000.0 0.0 1.3E+01a.H-3 has been added to this release point.The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-11 (continued)GASEOUS RELEASES (Ci/yr/reactor)
Nuclide Containment BuildingAuxiliary BuildingTurbine BuildingMain Condenser/ Air Ejector Blowdown Flash TankOffgas SystemTotal Revision 52-09/29/2016 NAPS UFSAR 11C-35Releases via Ventilation Vent a (continued)Xe-1370.02.1E-010.01.3E-010.00.03.3E-01Xe-1380.01.0E+000.06.4E-010.00.01.7E+00 I-1318.5E-045.9E-020.03.7E-020.00.09.6E-02 I-1337.4E-057.6E-020.04.8E-020.00.01.2E-01 Co-587.5E-046.0E-020.00.00.00.06.1E-02 Co-603.4E-042.7E-020.00.00.00.02.7E-02 Mn-542.2E-041.8E-020.00.00.00.01.8E-02 Fe-597.5E-056.0E-030.00.00.00.06.1E-03 Sr-891.7E-051.3E-030.00.00.00.01.3E-03 Sr-90 3.0E-062.0E-040.00.00.00.02.0E-04 Cs-1342.2E-041.8E-020.00.00.00.01.8E-02 Cs-137 3.8E-043.0E-020.00.00.00.03.0E-02 C-140.00.00.00.00.00.00.0 Ar-412.5E+0l0.00.0 0.0 0.0 0.0 2.5E+0l H-30.00.00.00.00.00.05.8E+02a.H-3 has been added to this release point.The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-11 (continued)GASEOUS RELEASES (Ci/yr/reactor)
Nuclide Containment BuildingAuxiliary BuildingTurbine BuildingMain Condenser/ Air Ejector Blowdown Flash TankOffgas SystemTotal Revision 52-09/29/2016 NAPS UFSAR 11C-36Releases via Turbine BuildingKr-83m0.00.04.1E-050.00.00.04.1E-05Kr-85m0.00.02.1E-040.00.00.02.1E-04 Kr-850.00.03.5E-050.00.00.03.5E-05 Kr-870.00.01.1E-040.00.00.01.1E-04 Kr-880.00.03.8E-040.00.00.03.8E-04 Kr-89 0.00.01.0E-050.00.00.01.0E-05 Xe-131m0.00.07.0E-050.00.00.07.0E-05 Xe-133m0.00.03.0E-040.00.00.03.0E-04 Xe-1330.00.01.7E-020.00.00.01.7E-02 Xe-135m0.00.02.6E-050.00.00.02.6E-05 Xe-1350.00.06.5E-040.00.00.06.5E-04 Xe-1370.00.01.8E-050.00.00.01.8E-05 Xe-1380.00.08.7E-050.00.00.08.7E-05 I-1310.00.05.9E-040.00.00.05.9E-04 I-1330.00.07.6E-040.00.00.07.6E-04 Co-580.00.00.00.00.00.00.0 Co-600.00.00.00.00.00.00.0 Mn-540.00.00.00.00.00.00.0 Fe-590.00.00.00.00.00.00.0The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-11 (continued)GASEOUS RELEASES (Ci/yr/reactor)
Nuclide Containment BuildingAuxiliary BuildingTurbine BuildingMain Condenser/ Air Ejector Blowdown Flash TankOffgas SystemTotal Revision 52-09/29/2016 NAPS UFSAR 11C-37Releases via Turbine Building (continued)Sr-890.00.00.00.00.00.00.0Sr-900.00.00.00.00.00.00.0 Cs-1340.00.00.00.00.00.00.0 Cs-1370.00.00.00.00.00.00.0 C-140.00.00.00.00.00.00.0 Ar-410.00.00.00.00.00.00.0 H-30.00.00.00.00.00.00.0Releases via Blowdown Flash TankKr-83m0.00.00.00.00.00.00.0 Kr-85m0.00.00.00.00.00.00.0 Kr-850.00.00.00.00.00.00.0 Kr-870.00.00.00.00.00.00.0 Kr-880.00.00.00.00.00.00.0 Kr-890.00.00.00.00.00.00.0 Xe-131m0.00.00.00.00.00.00.0 Xe-133m0.00.00.00.00.00.00.0 Xe-1330.00.00.00.00.00.00.0 Xe-135m0.00.00.00.00.00.00.0The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-11 (continued)GASEOUS RELEASES (Ci/yr/reactor)
Nuclide Containment BuildingAuxiliary BuildingTurbine BuildingMain Condenser/ Air Ejector Blowdown Flash TankOffgas SystemTotal Revision 52-09/29/2016 NAPS UFSAR 11C-38Releases via Blowdown Flash Tank (continued)Xe-1350.00.00.00.00.00.00.0Xe-1370.00.00.00.00.00.00.0 Xe-1380.00.00.00.00.00.00.0 I-1310.00.00.00.00.00.00.0 I-1330.00.00.00.00.00.00.0 Co-580.00.00.00.00.00.00.0 Co-600.00.00.00.00.00.00.0 Mn-540.00.00.00.00.00.00.0 Fe-590.00.00.00.00.00.00.0 Sr-890.00.00.00.00.00.00.0 Sr-900.00.00.00.00.00.00.0 Cs-1340.00.00.00.00.00.00.0 Cs-1370.00.00.00.00.00.00.0 C-140.00.00.00.00.00.00.0 Ar-410.00.00.00.00.00.00.0 H-30.00.00.00.00.00.00.0The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-11 (continued)GASEOUS RELEASES (Ci/yr/reactor)
Nuclide Containment BuildingAuxiliary BuildingTurbine BuildingMain Condenser/ Air Ejector Blowdown Flash TankOffgas SystemTotal Revision 52-09/29/2016 NAPS UFSAR 11C-39Releases via Process VentKr-83m0.00.00.00.00.04.4E-014.4E-01Kr-85m0.00.00.00.00.05.3E+005.3E+00 Kr-850.00.00.00.00.02.0E+022.0E+02 Kr-870.00.00.00.00.08.8E-018.8E-01 Kr-880.00.00.00.00.06.4E+006.4E+00 Kr-890.00.00.00.00.03.1E-033.1E-03 Xe-131m0.00.00.00.00.01.2E+021.2E+02 Xe-133m0.00.00.00.00.09.3E+019.3E+01 Xe-1330.00.00.00.00.01.3E+041.3E+04 Xe-135m0.00.00.00.00.03.9E+023.9E+02 Xe-1350.00.00.00.00.03.5E+013.5E+01 Xe-1370.00.00.00.00.06.7E-036.7E-03 Xe-1380.00.00.00.00.01.2E-011.2E-01 I-1310.00.00.00.00.00.00.0 I-1330.00.00.00.00.00.00.0 Co-580.00.00.00.00.02.0E-042.0E-04 Co-600.00.00.00.00.07.1E-057.1E-05 Mn-540.00.00.00.00.04.8E-054.8E-05 Fe-590.00.00.00.00.02.5E-052.5E-05The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-11 (continued)GASEOUS RELEASES (Ci/yr/reactor)
Nuclide Containment BuildingAuxiliary BuildingTurbine BuildingMain Condenser/ Air Ejector Blowdown Flash TankOffgas SystemTotal Revision 52-09/29/2016 NAPS UFSAR 11C-40Releases via Process Vent (continued)Sr-890.00.00.00.00.05.1E-065.1E-06Sr-900.00.00.00.00.06.0E-076.0E-07 Cs-1340.00.00.00.00.04.6E-054.6E-05 Cs-1370.00.00.00.00.07.5E-057.5E-05 C-140.00.00.00.00.08.0E+008.0E+00 Ar-410.00.00.00.00.00.00.00.0 H-30.00.00.00.00.00.00.0The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-11 (continued)GASEOUS RELEASES (Ci/yr/reactor)
Nuclide Containment BuildingAuxiliary BuildingTurbine BuildingMain Condenser/ Air Ejector Blowdown Flash TankOffgas SystemTotal Revision 52-09/29/2016 NAPS UFSAR 11C-41 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-12 DISTANCES AND ELEVATIONS FOR SPECIAL LOCATIONS aSpecial Location Distance Elevation Maximum ElevationSector N Milk cow 3.25 290 300 Meat animal 3.00 300-Milk goat---Nearest residence 2.50 285-Vegetable garden 3.25 290 300 Nearest site boundary 1.417 250-Sector NNE Milk cow 6.75 325 355 Meat animal 5.25 345-Milk goat---Nearest residence 2.25 270 305Vegetable garden 4.25 285 340 Nearest site boundary 1.374 250-Sector NE Milk cow---Meat animal 2.25 305-Milk goat---Nearest residence 2.00 285-Vegetable garden 2.00 285-Nearest site boundary 1.351 250-Sector ENE Milk cow---Meat animal 4.00 330-Milk goat 4.00 330-Nearest residence 3.25 295-Vegetable garden 3.50 310-Nearest site boundary 1.351 250-a.See note at end of table.
Revision 52-09/29/2016 NAPS UFSAR 11C-42Sector E Milk cow 3.00 280-Meat animal 5.00 260 310 Milk goat---Nearest residence 2.00 250 275Vegetable garden 3.00 280-Nearest site boundary 1.352 250 275Sector ESE Milk cow---Meat animal 7.75 255 300 Milk goat-250-Nearest residence 2.75 255 285Vegetable garden 3.00 255 285 Nearest site boundary 1.377 250 285Sector SE Milk cow---Meat animal 2.25 255 295 Milk goat 7.00 250 295 Nearest residence 2.25 255 295Vegetable garden 2.25 255 295 Nearest site boundary 1.422 250 295 Sector SSE Milk cow---Meat animal 2.25 295 -Milk goat---Nearest residence 3.25 250 300Vegetable garden 3.25 250 300 Nearest site boundary 1.483 250 295a.See note at end of table.
The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-12 (continued)DISTANCES AND ELEVATIONS FOR SPECIAL LOCATIONS aSpecial LocationDistanceElevation Maximum Elevation Revision 52-09/29/2016 NAPS UFSAR 11C-43Sector S Milk cow---Meat animal 2.50 280 315 Milk goat---Nearest residence 1.75 265 310Vegetable garden 2.50 280 315 Nearest site boundary 1.554 250 310 Sector SSW Milk cow 4.80 250 320 Meat animal 3.25 250 320 Milk goat---Nearest residence 2.25 295 320Vegetable garden 2.25 295 320 Nearest site boundary 1.658 280 320Sector SW Milk cow---Meat animal 2.50 305 325 Milk goat---Nearest residence 2.25 315 325Vegetable garden 2.25 315 325 Nearest site boundary 1.730 305 325Sector WSW Milk cow 4.75 365 400 Meat animal 2.75 355-Milk goat---Nearest residence 2.75 345 350Vegetable garden 2.75 355-Nearest site boundary 1.781 330 350a.See note at end of table.
The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-12 (continued)DISTANCES AND ELEVATIONS FOR SPECIAL LOCATIONS aSpecial LocationDistanceElevation Maximum Elevation Revision 52-09/29/2016 NAPS UFSAR 11C-44Sector W Milk cow---Meat animal 6.75 300 370 Milk goat---Nearest residence 2.75 350 370Vegetable garden 4.25 250 370 Nearest site boundary 1.740 260 305Sector WNW Milk cow 5.00 345 365 Meat animal 6.25 375-Milk goat---Nearest residence 1.75 330-Vegetable garden 5.00 345 365 Nearest site boundary 1.656 310-Sector NW Milk cow---Meat animal 4.00 250 325 Milk goat---Nearest residence 1.75 285 295Vegetable garden 3.25 260 325 Nearest site boundary 1.552 265 295Sector NNW Milk cow 3.50 310 325 Meat animal 3.75 290 325 Milk goat---Nearest residence 3.50 310 325Vegetable garden 3.50 310 325 Nearest site boundary 1.477 250 260a.See note at end of table.
The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-12 (continued)DISTANCES AND ELEVATIONS FOR SPECIAL LOCATIONS aSpecial LocationDistanceElevation Maximum Elevation Revision 52-09/29/2016 NAPS UFSAR 11C-45 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.Table 11C-12 (continued)
DISTANCE AND ELEVATIONS FOR SPECIAL LOCATIONS aNotes:1.Distances are given in kilometers from the center point of containment 1 to the item indicated.2.The elevation of the point of intere st is given in feet, mean sea level.3.The elevation of the highest terrain along th e cardinal compass radi al between the plant and the point of interest is gi ven in feet, mean s ea level, if the high point has a greater elevation than the point of interest.
Revision 52-09/29/2016 NAPS UFSAR 11C-46The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-13 ANNUAL AVERAGE /Q (sec/m 3), D/Q (m-2), AND TERRAIN CORRECTION FACTOR (TCF) AT SITE BOUNDARIES AND OFFSITE EXPOSURE LOCATIONS FOR GROUND-LEVEL RELEASES AT NORTH ANNA (May 1, 1974 through April 30, 1975)
Exposure DirectionParameterSite Boundary Nearest ResidenceNearest GardenNearest Meat Animal Nearest Milk CowNearest Milk Goat N/Q6.8-061.9-061.1-061.3-061.1-06-D/Q3.3-088.0-094.1-095.0-094.1-09-TCF3.42.21.81.91.8-NNE/Q5.4-061.7-064.4-073.0-071.8-07-D/Q3.6-089.9-092.1-091.3-097.3 TCF3.52.31.51.41.2-NE/Q4.7-061.8-061.8-061.4-06--D/Q3.0-081.0-081.0-087.7-09--
TCF3.62.52.52.3--
ENE/Q4.8-066.6-075.6-074.4-07-4.4-07D/Q2.0-082.2-091.8-091.3-09-1.3-09 TCF 3.61.81.71.6-1.6 E/Q1.0-054.1-061.8-066.4-071.8-06-D/Q3.0-081.1-084.0-091.2-094.0 TCF3.62.51.91.41.9-ESE/Q1.2-052.7-062.3-064.1-07--D/Q3.1-085.3-094.3-095.0-10--
TCF3.52.01.91.2--
Revision 52-09/29/2016 NAPS UFSAR 11C-47 SE /Q 6.6-062.3-062.3-062.3 2.6-07 D/Q2.8-088.5-098.5-098.5 5.9-10 TCF 3.4 2.3 2.3 2.3-1.2 SSE/Q2.7-064.9-074.9-071.0 -D/Q2.0-082.7-092.7-096.6 -TCF 3.3 1.8 1.8 2.3--S/Q4.3-063.1-061.5-061.5 -D/Q2.9-082.0-088.5-098.5 -TCF 3.3 2.8 2.2 2.2--SSW/Q1.6-067.4-077.4-073.3-071.6 D/Q1.3-085.7-095.7-092.4-099.7 TCF 3.1 2.3 2.3 1.8 1.5-SW/Q1.1-066.1-076.1-075.0 -D/Q8.7-094.3-094.3-093.5 -TCF 2.9 2.3 2.3 2.2--WSW/Q9.2-075.5-073.6-073.6-071.2 D/Q6.0-093.4-092.1-092.1-095.9 TCF 2.7 2.3 2.0 2.0 1.5-The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-13 (continued)ANNUAL AVERAGE /Q (sec/m 3), D/Q (m-2), AND TERRAIN CORRECTION FACTOR (TCF) AT SITE BOUNDARIES AND OFFSITE EXPOSURE LOCATIONS FOR GROUND-LEVEL RELEASES AT NORTH ANNA (May 1, 1974 through April 30, 1975)
Exposure DirectionParameterSite Boundary Nearest ResidenceNearest GardenNearest Meat Animal Nearest Milk CowNearest Milk Goat Revision 52-09/29/2016 NAPS UFSAR 11C-48 W/Q1.7-066.2-072.5-071.0 -D/Q8.9-092.9-099.8-103.4 -TCF 2.8 2.0 1.5 1.2--WNW/Q2.0-061.7-061.9-071.3-071.9 D/Q9.8-098.0-096.3-103.9-106.3 TCF 3.1 2.8 1.4 1.3 1.4-NW/Q4.0-062.8-067.4-074.9 -D/Q1.7-081.1-082.5-091.5 -TCF 3.3 2.8 1.8 1.6--NNW/Q4.9-067.2-077.2-076.5-077.2 D/Q2.1-082.4-092.1-092.1-092.4 TCF 3.3 1.7 1.7 1.7 1.7-The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-13 (continued)ANNUAL AVERAGE /Q (sec/m 3), D/Q (m-2), AND TERRAIN CORRECTION FACTOR (TCF) AT SITE BOUNDARIES AND OFFSITE EXPOSURE LOCATIONS FOR GROUND-LEVEL RELEASES AT NORTH ANNA (May 1, 1974 through April 30, 1975)
Exposure DirectionParameterSite Boundary Nearest ResidenceNearest GardenNearest Meat Animal Nearest Milk CowNearest Milk Goat Revision 52-09/29/2016 NAPS UFSAR 11C-49The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-14 ANNUAL AVERAGE /Q (sec/m 3), D/Q (m-2), AND TERRAIN CORRECTION FACTOR (TCF) AT SITE BOUNDARIES AND OFFSITE EXPOSURE LOCATIONS FOR MIXED RELEASE MODES AT NORTH ANNA (May 1, 1974 through April 30, 1975)
Exposure DirectionParameterSite Boundary Nearest ResidenceNearest GardenNearest Meat Animal Nearest Milk CowNearest Milk Goat N/Q9.5-074.4-073.0-073.4-073.0-07-D/Q1.2-083.2-091.7-092.0-091.7-09-TCF3.42.21.81.91.8-NNE/Q1.1-065.7-072.1-071.6-079.9-08-D/Q1.8-085.2-091.1-097.4-104.3 TCF3.52.31.51.4 1.2-NE/Q1.1-066.4-076.4-075.6-07--D/Q1.5-085.6-095.6-094.3-09--
TCF3.62.52.52.3--
ENE/Q6.0-071.9-071.7-071.5-07 -1.5-07D/Q6.4-097.7-106.4-104.8-10-4.8-10 TCF3.61.81.71.6-1.6 E/Q6.2-073.7-072.1-071.0-072.1-07-D/Q7.4-092.8-091.1-093.2-101.1 TCF3.62.51.91.41.9-ESE/Q7.1-072.8-082.5-076.8-08--D/Q6.4-091.2-091.0-091.4-10--
TCF3.52.01.91.2--
Revision 52-09/29/2016 NAPS UFSAR 11C-50 SE/Q9.5-074.9-074.9-074.9 8.8-08 D/Q1.2-083.8-093.8-093.8 3.0-10 TCF 3.4 2.3 2.3 2.3-1.2 SSE/Q8.1-072.5-072.5-074.3 -D/Q1.0-081.5-091.5-093.7 -TCF 3.3 1.8 1.8 2.3--S/Q1.0-068.0-074.8-074.8 -D/Q1.7-081.2-085.0-095.0 -TCF 3.3 2.8 2.2 2.2--SSW/Q7.0-074.0-074.0-072.2-071.2 D/Q8.2-093.7-093.7-091.5-096.3 TCF 3.1 2.3 2.3 1.8 1.5-SW/Q5.7-073.7-073.7-073.2 -D/Q5.2-092.6-092.6-092.1 -TCF 2.9 2.3 2.3 2.2--WSW/Q4.0-072.7-072.0-072.0-079.3 D/Q3.8-092.1-091.3-091.3-093.7 TCF 2.7 2.3 2.0 2.0 1.5-The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-14 (continued)ANNUAL AVERAGE /Q (sec/m 3), D/Q (m-2), AND TERRAIN CORRECTION FACTOR (TCF) AT SITE BOUNDARIES AND OFFSITE EXPOSURE LOCATIONS FOR MIXED RELEASE MODES AT NORTH ANNA (May 1, 1974 through April 30, 1975)
Exposure DirectionParameterSite Boundary Nearest ResidenceNearest GardenNearest Meat Animal Nearest Milk CowNearest Milk Goat Revision 52-09/29/2016 NAPS UFSAR 11C-51 W/Q4.5-072.9-071.3-076.0 -D/Q3.5-091.2-094.1-101.5 -TCF 2.8 2.0 1.5 1.2--WNW/Q4.1-073.8-077.7-085.6-087.7 D/Q4.6-093.8-093.1-102.0-103.1 TCF 3.1 2.8 1.4 1.3 1.4-NW/Q6.7-075.3-072.3-071.7 -D/Q6.4-094.5-091.0-096.3 -TCF 3.3 2.8 1.8 1.6--NNW/Q5.9-071.9-071.9-071.8-071.9 D/Q5.8-097.1-107.1-106.3-107.1 TCF 3.3 1.7 1.7 1.7 1.7-The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-14 (continued)ANNUAL AVERAGE /Q (sec/m 3), D/Q (m-2), AND TERRAIN CORRECTION FACTOR (TCF) AT SITE BOUNDARIES AND OFFSITE EXPOSURE LOCATIONS FOR MIXED RELEASE MODES AT NORTH ANNA (May 1, 1974 through April 30, 1975)
Exposure DirectionParameterSite Boundary Nearest ResidenceNearest GardenNearest Meat Animal Nearest Milk CowNearest Milk Goat Revision 52-09/29/2016 NAPS UFSAR 11C-52 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-15 MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OF WIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASSVEPCO North Anna JFD 35-Foot Level-Period of Record: 1/5/74 - 30/4/75Stability Class: A-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 26 66 120 64 6 0 282 NNE 23 60 50 9 0 0 142 NE 20 57 34 1 0 0112 ENE 25 40 22 4 0 0 91 E 38 71 8 2 1 0 120 ESE 12 45 29 0 0 0 86 SE 15 44 34 1 0 0 94 SSE 12 52 43 2 0 0 109 S 8 92 88 11 0 199 SSW 10 59114 20 0 0 203 SW 3 59 65 9 1 0 137 WSW 13 29 28 12 0 0 82 W 19 27 20 11 4 1 82 WNW 15 27 21 9 1 1 74 NW 20 62 39 10 1 3 135 NNW 24 42 54 38 1 0 159Variable 0 0 0 0 0 0 0Totals 283 832 769 203 15 5 2107 Periods of Calms 0 HoursStability Class: B-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 7 18 9 0 0 34 NNE 1 6 5 1 0 0 13 NE 0 5 7 0 0 0 12 ENE 1 3 3 0 0 0 7 E 2 3 2 0 0 0 7 ESE 2 2 3 0 0 0 7 SE 0 9 4 1 0 0 14 SSE 1 8 2 1 0 0 12 S 3 8 8 0 0 0 19 SSW 3 6 4 0 0 0 13 SW 5 4 5 2 0 0 16 WSW 2 3 1 3 1 0 10 W 2 2 4 2 0 3 13 WNW 2 3 1 2 0 0 8 NW 1 3 4 1 0 3 12 NNW 1 5 11 1 0 0 18Variable 0 0 0 0 0 0 0Totals 26 77 82 23 1 6 215 Revision 52-09/29/2016 NAPS UFSAR 11C-53 Periods of Calms 1 HoursVEPCO North Anna JFD 35-Foot Level-Period of Record: 1/ 5/74 - 30/ 4/75Stability Class: C-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 4 15 17 8 0 0 44 NNE 1 12 15 0 0 0 28 NE 3 5 4 1 0 0 13 ENE 0 6 6 3 0 0 15 E 0 11 1 0 0 0 12 ESE 2 9 4 0 0 0 15 SE 3 8 6 1 0 0 18 SSE 3 10 1 1 0 0 15 S 1 11 5 1 0 0 18 SSW 1 18 7 0 1 0 27 SW 3 8 9 0 0 0 20 WSW 1 4 2 2 4 0 13 W 2 4 6 2 2 1 17 WNW 2 4 3 6 2 6 23 NW 2 5 4 4 1 3 19 NNW 2 6 20 3 0 0 31Variable 0 0 0 0 0 0 0Totals 30 136110 32 10 10 328 Periods of Calms 0 HoursStability Class: D-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 23 77 104 30 5 0 239 NNE 20 60 48 11 0 0 139 NE 21 58 21 11 1 0112 ENE 22 28 11 1 0 1 63 E 24 53 13 0 1 3 94 ESE 10 45 17 1 0 0 73 SE 21 81 17 1 0 0 120 SSE 30 76 21 3 0 0 130 S 44 97 48 9 0 0 198 SSW 27 107 77 25 2 0 238 SW 35 64 46 11 7 0 163 WSW 32 30 32 8 5 0 107 W 27 34 19 14 7 13114 WNW 18 37 25 31 11 6 128 NW 21 78 52 42 15 6 214 NNW 11 53 68 23 3 2 160Variable 0 0 3 0 0 0 0Totals 386 978 619 221 57 31 2292 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-54 Periods of Calms 3 HoursVEPCO North Anna JFD 35-Foot-Level Period of Record: 1/ 5/74 - 30/ 4/75Stability Class: E-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 27 51 24 8 0 0110 NNE 13 39 22 3 0 0 77 NE 6 34 9 2 0 0 51 ENE 10 29 13 0 0 0 52 E 25 34 7 2 0 0 68 ESE 14 45 13 3 4 0 79 SE 50 67 15 1 1 0 154 SSE 64 75 11 5 0 0 155 S 57 81 40 6 0 0 184 SSW 44 84 39 16 3 0 186 SW 38 66 62 8 0 0 174 WSW 38 48 20 3 2 0 111 W 81 34 16 7 1 1 140 WNW 66 38 16 18 8 4 150 NW 35 42 19 11 3 2112 NNW 16 23 20 6 0 0 65Variable 0 0 0 0 0 0 0Totals 584 790 346 99 22 7 1848 Periods of Calms 15 HoursStability Class: F-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 12 1 3 1 0 0 17 NNE 4 1 0 0 0 0 5 NE 5 1 0 0 0 0 6 ENE 4 5 1 0 0 0 10 E 8 7 3 0 0 0 18 ESE 13 10 1 0 0 0 24 SE 21 10 1 0 0 0 32 SSE 30 29 1 0 0 0 60 S 38 26 3 0 0 0 67 SSW 16 12 2 0 0 0 30 SW 18 12 3 0 0 0 33 WSW 28 13 2 0 0 0 43 W 75 58 5 1 1 0 140 WNW 68 37 2 0 0 0 107 NW 28 24 3 0 0 0 55 NNW 11 6 2 0 0 0 19Variable 0 0 0 0 0 0 0Totals 379 252 32 2 1 0 666 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-55 Periods of Calms 15 HoursVEPCO North Anna JFD 35-Foot Level-Period of Record: 1/5/74 - 30/4/75Stability Class: G-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 36 1 0 0 0 0 37 NNE 5 2 0 0 0 0 7 NE 5 1 0 0 0 0 6 ENE 4 1 0 0 0 0 5 E 11 3 0 0 0 0 14 ESE 15 5 0 0 0 0 20 SE 16 5 0 0 0 0 21 SSE 9 5 1 0 0 0 15 S 20 10 1 0 0 0 31 SSW 13 2 0 0 0 0 15 SW 4 5 0 0 0 0 9 WSW 11 3 0 0 0 0 14 W 36 17 2 0 0 0 55 WNW 95 23 2 0 0 0 120 NW 47 11 0 1 0 0 59 NNW 17 1 1 0 0 0 19Variable 0 0 0 0 0 0 0Totals 344 95 7 1 0 0 447 Periods of Calms 25 Hours Hours of Missing Data: 798Total Observations for the Period are: 7962 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-56VEPCO North Anna JFD 35-Foot Level-Period of Record: JAN 1/5/74 - 30/4/75Stability Class: A-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 1 0 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E 0 2 0 0 0 0 2 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 1 0 0 0 0 1 W 0 0 0 0 0 0 0 WNW 0 1 0 0 0 0 1 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 1 4 0 0 0 0 5 Periods of Calms 0 HoursStability Class: B-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 1 0 0 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 1 0 0 0 1 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 1 0 1 0 0 0 2 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-57VEPCO North Anna JFD 35-Foot Level-Period of Record: JAN 1/5/74 - 30/4/75Stability Class: C-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 1 0 0 0 0 0 1 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 1 0 0 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 2 0 0 0 0 0 2 Periods of Calms 0 HoursStability Class: D-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 0 7 7 3 0 19 NNE 1 5 1 0 0 0 7 NE 0 4 5 1 0 0 10 ENE 4 1 1 0 0 0 6 E 2 1 0 0 0 0 3 ESE 0 5 0 0 0 0 5 SE 1 6 0 0 0 0 7 SSE 0 4 5 0 0 0 9 S 0 6 3 2 0 0 11 SSW 1 3 2 2 0 0 8 SW 0 4 1 1 0 0 6 WSW 2 2 1 0 0 0 5 W 0 2 1 0 0 0 3 WNW 0 4 1 0 0 0 5 NW 0 5 4 1 0 0 10 NNW 0 10 7 4 1 0 22Variable 0 0 0 0 0 0 0Totals 13 62 39 18 4 0 136 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-58VEPCO North Anna JFD 35-Foot Level-Period of Record: JAN 1/5/74 - 30/4/75Stability Class: E-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 6 7 5 0 0 19 NNE 0 3 3 0 0 0 6 NE 0 7 4 0 0 0 11 ENE 2 3 4 0 0 0 9 E 3 5 1 0 0 0 9 ESE 3 6 3 0 0 0 12 SE 2 19 4 1 0 0 26 SSE 1 13 4 0 0 0 18 S 2 16 14 1 0 0 33 SSW 0 9 7 0 0 0 16 SW 2 11 15 0 0 0 28 WSW 1 6 1 0 0 0 8 W 4 0 0 1 0 0 5 WNW 5 3 0 3 2 0 13 NW 3 4 1 1 3 0 12 NNW 1 3 5 3 0 0 12Variable 0 0 0 0 0 0 0Totals 30114 73 15 5 0 237 Periods of Calms 2 HoursStability Class: F-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 0 0 0 0 0 2 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 2 0 0 0 0 2 E 2 0 0 0 0 0 2 ESE 1 1 0 0 0 0 2 SE 4 2 0 0 0 0 6 SSE 1 5 0 0 0 0 6 S 3 8 1 0 0 0 12 SSW 2 0 2 0 0 0 4 SW 2 2 0 0 0 0 4 WSW 2 0 0 0 0 0 2 W 7 6 2 0 0 0 15 WNW 4 5 0 0 0 0 9 NW 2 1 0 0 0 0 3 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 32 32 5 0 0 0 69 Periods of Calms 2 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-59VEPCO North Anna JFD 35-Foot Level-Period of Record: JAN 1/5/74 - 30/4/75Stability Class: G-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 1 0 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 1 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E 1 1 0 0 0 0 2 ESE 2 2 0 0 0 0 4 SE 1 1 0 0 0 0 2 SSE 1 2 0 0 0 0 3 S 2 1 1 0 0 0 4 SSW 2 0 0 0 0 0 2 SW 0 1 0 0 0 0 1 WSW 0 0 0 0 0 0 0 W 2 0 0 0 0 0 2 WNW 8 4 0 0 0 0 12 NW 2 1 0 0 0 0 3 NNW 1 0 0 0 0 0 1Variable 0 0 0 0 0 0 0Totals 22 15 1 0 0 0 38 Periods of Calms 6 Hours Hours of Missing Data: 245Total Observations for Jan: 499 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-60VEPCO North Anna JFD 35-Foot Level-Period of Record: FEB 1/5/74 - 30/4/75Stability Class: A-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 0 0 0 0 0 1 NNE 0 1 0 0 0 0 1 NE 0 1 0 0 0 0 1 ENE 0 0 1 0 0 0 1 E 0 2 1 0 0 0 3 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 1 0 0 0 1 S 0 1 3 0 0 0 4 SSW 0 0 1 0 0 0 1 SW 0 0 0 0 0 0 0 WSW 0 1 0 0 0 0 1 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 1 6 7 0 0 0 14 Periods of Calms 0 HoursStability Class: B-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 1 0 0 0 1 NNE 1 0 0 0 0 0 1 NE 0 0 1 0 0 0 1 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 2 0 0 0 2 S 0 0 2 0 0 0 2 SSW 0 0 1 0 0 0 1 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 1 0 1 W 0 1 0 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 1 1 7 0 1 0 10 Periods of Calms 1 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-61VEPCO North Anna JFD 35-Foot Level-Period of Record: FEB 1/5/74 - 30/4/75Stability Class: C-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 1 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 1 0 0 0 0 1 SE 0 0 1 0 0 0 1 SSE 0 0 0 0 0 0 0 S 0 2 2 0 0 0 4 SSW 0 1 2 0 1 0 4 SW 0 0 1 0 0 0 1 WSW 0 0 1 0 3 0 4 W 0 0 0 0 0 0 0 WNW 0 1 1 0 0 0 2 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 0 5 9 0 4 0 18 Periods of Calms 0 HoursStability Class: D-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 4 13 5 1 0 24 NNE 5 11 11 2 0 0 29 NE 3 3 1 0 0 0 7 ENE 2 0 0 0 0 0 2 E 5 1 0 0 0 0 6 ESE 1 4 0 0 0 0 5 SE 1 0 1 0 0 0 2 SSE 0 1 0 0 0 0 1 S 0 4 4 0 0 0 8 SSW 1 9 4 6 1 0 21 SW 1 7 2 0 3 0 13 WSW 0 2 4 2 2 0 10 W 1 1 3 1 0 0 6 WNW 0 1 1 1 0 0 3 NW 1 3 4 1 0 0 9 NNW 0 1 2 3 0 0 6Variable 0 0 0 0 0 0 0Totals 22 52 50 21 7 0 152 Periods of Calms 1 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-62VEPCO North Anna JFD 35-Foot Level-Period of Record: FEB 1/5/74 - 30/4/75Stability Class: E-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 9 19 5 1 0 0 34 NNE 4 19 8 0 0 0 31 NE 2 10 0 0 0 0 12 ENE 1 6 1 0 0 0 8 E 4 7 0 0 0 0 11 ESE 1 1 0 0 0 0 2 SE 9 6 2 0 0 0 17 SSE 5 7 0 3 0 0 15 S 10 14 7 1 0 0 32 SSW 4 13 2 10 0 0 29 SW 2 19 14 1 0 0 39 WSW 2 4 3 2 1 0 12 W 9 2 4 0 1 0 15 WNW 8 12 0 0 0 0 20 NW 7 4 7 3 0 0 21 NNW 5 5 3 0 0 0 13Variable 0 0 0 0 0 0 0Totals 82 148 56 24 2 0 312 Periods of Calms 10 HoursStability Class: F-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 0 1 0 0 0 2 NNE 1 0 0 0 0 0 1 NE 1 0 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 1 0 0 0 0 0 1 SE 2 2 0 0 0 0 4 SSE 2 7 1 0 0 0 10 S 7 4 0 0 0 0 11 SSW 3 2 0 0 0 0 5 SW 1 1 1 0 0 0 3 WSW 3 2 1 0 0 0 6 W 5 4 1 0 0 0 10 WNW 6 2 0 0 0 0 8 NW 2 4 0 0 0 0 6 NNW 2 0 0 0 0 0 2Variable 0 0 0 0 0 0 0Totals 37 28 5 0 0 0 70 Periods of Calms 10 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-63VEPCO North Anna JFD 35-Foot Level-Period of Record: FEB 1/5/74 - 30/4/75Stability Class: G-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 3 0 0 0 0 0 3 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 4 0 0 0 0 0 4 ESE 3 0 0 0 0 0 3 SE 4 0 0 0 0 0 4 SSE 1 0 1 0 0 0 2 S 1 3 0 0 0 0 4 SSW 4 0 0 0 0 0 4 SW 1 1 0 0 0 0 2 WSW 1 0 0 0 0 0 1 W 4 0 0 0 0 0 4 WNW 12 1 0 0 0 0 13 NW 2 1 0 0 0 0 3 NNW 3 0 0 0 0 0 3Variable 0 0 0 0 0 0 0Totals 43 6 1 0 0 0 50 Periods of Calms 14 Hours Hours of Missing Data: 10Total Observations for FEB: 662 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-64VEPCO North Anna JFD 35-Foot Level-Period of Record: MAR 1/5/74 - 30/4/75Stability Class: A-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 2 0 0 0 0 3 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 2 0 0 0 0 2 E 0 1 1 0 0 0 2 ESE 0 0 0 0 0 0 0 SE 0 1 0 0 0 0 1 SSE 0 2 0 0 0 0 2 S 0 0 2 0 0 0 2 SSW 0 1 2 0 0 0 3 SW 0 0 0 5 1 0 6 WSW 0 0 1 1 0 0 2 W 2 0 0 2 0 0 4 WNW 0 1 0 0 0 0 1 NW 0 3 2 0 0 0 5 NNW 0 2 0 0 0 0 2Variable 0 0 0 0 0 0 0Totals 3 15 8 8 1 0 35 Periods of Calms 0 HoursStability Class: B-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 1 0 0 0 0 1 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 1 0 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 2 0 0 2 WSW 0 0 0 0 0 0 0 W 0 0 0 1 0 0 1 WNW 0 0 0 2 0 0 2 NW 0 0 0 0 0 0 0 NNW 0 1 1 1 0 0 3Variable 0 0 0 0 0 0 0Totals 0 3 1 6 0 0 10 Periods of Claims 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-65VEPCO North Anna JFD 35-Foot Level-Period of Record: MAR 1/5/74 - 30/4/75Stability Class: C-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 2 0 0 0 2 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 1 0 0 0 0 1 E 0 1 0 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 3 1 0 0 4 SSW 0 0 0 0 0 0 0 SW 0 0 2 0 0 0 2 WSW 0 0 1 0 1 0 2 W 0 0 0 1 0 0 1 WNW 0 0 1 5 0 0 6 NW 0 0 0 0 0 0 0 NNW 0 0 1 0 0 0 1Variable 0 0 0 0 0 0 0Totals 0 2 10 7 1 0 20 Periods of Calms 0 HoursStability Class: D-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 5 15 3 0 0 25 NNE 0 7 7 4 0 0 18 NE 1 10 3 3 0 0 17 ENE 1 7 0 0 0 0 8 E 2 10 0 0 0 0 12 ESE 1 1 1 0 0 0 3 SE 3 2 4 0 0 0 9 SSE 1 7 10 1 0 0 19 S 1 4 8 3 0 0 16 SSW 0 5 12 5 0 0 22 SW 0 5 10 3 0 0 18 WSW 1 1 1 0 1 0 4 W 1 3 4 4 1 1 14 WNW 3 0 6 13 6 1 29 NW 0 3 3 10 1 0 17 NNW 0 0 6 10 1 0 17Variable 0 0 0 0 0 0 0Totals 17 70 90 59 10 2 248 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-66VEPCO North Anna JFD 35-Foot Level-Period of Record: MAR 1/5/74 - 30/4/75Stability Class: E-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 5 6 1 0 0 14 NNE 1 7 3 2 0 0 13 NE 0 2 0 1 0 0 3 ENE 0 7 6 0 0 0 13 E 3 7 3 2 0 0 15 ESE 1 16 7 2 3 0 29 SE 2 10 5 0 0 0 17 SSE 5 6 1 0 0 0 12 S 3 11 7 0 0 0 21 SSW 2 3 7 0 0 0 12 SW 2 5 12 0 0 0 19 WSW 1 6 4 0 0 0 11 W 1 4 2 3 0 1 11 WNW 1 1 5 10 5 3 25 NW 1 3 1 1 0 2 8 NNW 1 1 2 1 0 0 5Variable 0 0 0 0 0 0 0Totals 26 94 71 23 8 6 228 Periods of Calms 0 HoursStability Class: F-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 1 0 0 1 NNE 1 0 0 0 0 0 1 NE 1 0 0 0 0 0 1 ENE 1 1 1 0 0 0 3 E 1 4 3 0 0 0 8 ESE 0 6 1 0 0 0 7 SE 0 2 1 0 0 0 3 SSE 2 4 0 0 0 0 6 S 1 1 0 0 0 0 2 SSW 0 0 0 0 0 0 0 SW 0 2 0 0 0 0 2 WSW 0 3 0 0 0 0 3 W 4 2 0 1 1 0 8 WNW 2 2 1 0 0 0 5 NW 5 0 0 0 0 0 5 NNW 1 1 0 0 0 0 2Variable 0 0 0 0 0 0 0Totals 19 28 7 2 1 0 57 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-67VEPCO North Anna JFD 35-Foot Level-Period of Record: MAR 1/5/74 - 30/4/75Stability Class: G-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 1 2 0 0 0 0 3 NE 0 0 0 0 0 0 0 ENE 1 0 0 0 0 0 1 E 3 0 0 0 0 0 3 ESE 2 1 0 0 0 0 3 SE 3 1 0 0 0 0 4 SSE 0 0 0 0 0 0 0 S 3 0 0 0 0 0 3 SSW 1 1 0 0 0 0 2 SW 0 0 0 0 0 0 0 WSW 2 1 0 0 0 0 3 W 2 4 0 0 0 0 6 WNW 9 1 0 0 0 0 10 NW 3 0 0 0 0 0 3 NNW 2 0 0 0 0 0 2Variable 0 0 0 0 0 0 0Totals 32 11 0 0 0 0 43 Periods of Calms 0 Hours Hours of Missing Data: 103Total Observations for Mar: 641 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-68VEPCO North Anna JFD 35-Foot Level-Period of Record: APR 1/5/74 - 30/4/75Stability Class: A-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 1 2 0 0 0 4 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 2 0 0 0 0 2 E 0 4 0 0 0 0 4 ESE 0 1 2 0 0 0 3 SE 1 2 3 0 0 0 6 SSE 0 0 1 0 0 0 1 S 0 0 2 0 0 0 2 SSW 0 0 3 4 0 0 7 SW 0 0 0 1 0 0 1 WSW 0 0 2 1 0 0 3 W 0 1 1 0 3 1 6 WNW 0 3 2 0 1 1 7 NW 0 1 8 2 0 3 14 NNW 1 2 2 1 0 0 6Variable 0 0 0 0 0 0 0Totals 3 17 28 9 4 5 66 Periods of Calms 0 HoursStability Class: B-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 1 1 0 0 0 0 2 ESE 0 0 0 0 0 0 0 SE 0 1 0 0 0 0 1 SSE 0 0 0 0 0 0 0 S 0 0 1 0 0 0 1 SSW 0 0 0 0 0 0 0 SW 0 0 1 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 0 1 0 0 3 4 WNW 0 0 0 0 0 0 0 NW 0 0 2 1 0 3 6 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 1 2 5 1 0 6 15 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-69VEPCO North Anna JFD 35-Foot Level-Period of Record: APR 1/5/74 - 30/4/75Stability Class: C-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 2 0 0 2 NNE 0 0 0 0 0 0 0 NE 0 1 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E 0 4 0 0 0 0 4 ESE 0 2 0 0 0 0 2 SE 0 1 0 0 0 0 1 SSE 0 1 0 1 0 0 2 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 1 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 0 3 0 2 1 6 WNW 0 1 1 1 2 6 11 NW 0 0 0 3 1 3 7 NNW 0 0 3 1 0 0 4Variable 0 0 0 0 0 0 0Totals 0 10 8 8 5 10 41 Periods of Calms 0 HoursStability Class: D-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 9 9 4 1 0 24 NNE 0 4 5 0 0 0 9 NE 0 14 3 0 0 0 17 ENE 2 5 6 0 0 0 13 E 0 11 5 0 0 0 16 ESE 1 9 2 0 0 0 12 SE 2 12 0 0 0 0 14 SSE 2 7 2 1 0 0 12 S 1 9 5 2 0 0 17 SSW 2 4 9 11 1 0 27 SW 0 2 7 7 4 0 20 WSW 1 0 1 1 1 0 4 W 1 1 0 1 4 12 19 WNW 1 4 2 9 5 5 26 NW 1 10 19 23 13 6 72 NNW 2 6 13 2 1 2 26Variable 0 0 0 0 0 0 0Totals 17 107 88 61 30 25 328 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-70VEPCO North Anna JFD 35-Foot Level-Period of Record: APR 1/5/74 - 30/4/75Stability Class: E-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 3 7 2 0 0 0 12 NNE 1 3 0 0 0 0 4 NE 1 6 0 0 0 0 7 ENE 0 3 2 0 0 0 5 E 3 8 3 0 0 0 14 ESE 1 12 2 0 0 0 15 SE 3 8 1 0 0 0 12 SSE 4 2 0 2 0 0 8 S 0 1 4 4 0 0 9 SSW 0 1 4 6 3 0 14 SW 1 1 3 1 0 0 6 WSW 2 0 2 0 1 0 5 W 2 1 1 0 0 0 4 WNW 2 1 2 2 1 1 9 NW 0 4 4 3 0 0 11 NNW 0 2 5 1 0 0 11Variable 0 0 0 0 0 0 0Totals 26 60 35 19 5 1 146 Periods of Calms 0 HoursStability Class: F-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 0 0 0 0 0 2 NNE 0 1 0 0 0 0 1 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 1 0 0 0 0 0 1 ESE 4 1 0 0 0 0 5 SE 1 1 0 0 0 0 2 SSE 0 0 0 0 0 0 0 S 1 0 0 0 0 0 1 SSW 0 1 0 0 0 0 1 SW 1 0 0 0 0 0 1 WSW 2 1 1 0 0 0 4 W 2 5 0 0 0 0 7 WNW 6 4 0 0 0 0 10 NW 4 4 2 0 0 0 10 NNW 4 2 0 0 0 0 6Variable 0 0 0 0 0 0 0Totals 28 20 3 0 0 0 51 Periods of Calms 1 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-71VEPCO North Anna JFD 35-Foot Level-Period of Record: APR 1/5/74 - 30/4/75Stability Class: G-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 0 0 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 2 0 0 0 0 0 2 ENE 0 0 0 0 0 0 0 E 1 0 0 0 0 0 1 ESE 1 1 0 0 0 0 2 SE 0 1 0 0 0 0 1 SSE 1 1 0 0 0 0 2 S 0 1 0 0 0 0 1 SSW 2 0 0 0 0 0 2 SW 0 0 0 0 0 0 0 WSW 2 0 0 0 0 0 2 W 3 3 1 0 0 0 7 WNW 10 6 0 0 0 0 16 NW 12 4 0 0 0 0 16 NNW 4 0 1 0 0 0 5Variable 0 0 0 0 0 0 0Totals 39 17 2 0 0 0 58 Periods of Calms 1 Hours Hours of Missing Data: 13Total Observations for APR: 707 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-72VEPCO North Anna JFD 35-Foot Level-Period of Record: MAY 1/5/74 - 30/4/75Stability Class: A-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 19 12 6 0 0 38 NNE 2 7 4 1 0 0 14 NE 1 9 6 0 0 0 16 ENE 5 5 7 2 0 0 19 E 7 12 3 0 0 0 22 ESE 2 8 11 0 0 0 21 SE 2 7 13 1 0 0 23 SSE 1 9 16 2 0 0 28 S 3 17 13 8 0 0 41 SSW 2 4 13 5 0 0 24 SW 0 18 13 0 0 0 31 WSW 2 3 4 1 0 0 10 W 1 4 5 2 1 0 13 WNW 1 3 7 2 0 0 13 NW 2 6 8 2 0 0 18 NNW 1 9 9 5 1 0 25Variable 0 0 0 0 0 0 0Totals 33 140 144 37 2 0 356 Periods of Calms 0 HoursStability Class: B-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 4 3 0 0 7 NNE 0 1 0 0 0 0 1 NE 0 2 3 0 0 0 5 ENE 0 1 1 0 0 0 2 E 0 0 1 0 0 0 1 ESE 0 0 2 0 0 0 2 SE 0 4 4 1 0 0 9 SSE 0 3 0 1 0 0 4 S 0 1 0 0 0 0 1 SSW 0 0 0 0 0 0 0 SW 1 1 1 0 0 0 3 WSW 1 0 0 0 0 0 1 W 1 0 0 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 0 1 1 0 0 0 2 NNW 0 0 2 0 0 0 2Variable 0 0 0 0 0 0 0Totals 3 14 19 5 0 0 41 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-73VEPCO North Anna JFD 35-Foot Level-Period of Record: MAY 1/5/74 - 30/4/75Stability Class: C-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 5 0 0 0 0 5 NNE 0 3 0 0 0 0 3 NE 2 0 0 0 0 0 2 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 2 4 0 0 0 6 SSE 1 3 0 0 0 0 4 S 0 0 0 0 0 0 0 SSW 1 0 2 0 0 0 3 SW 0 0 1 0 0 0 1 WSW 0 1 0 0 0 0 1 W 1 0 2 0 0 0 3 WNW 1 1 0 0 0 0 2 NW 0 1 1 0 0 0 2 NNW 0 1 0 0 0 0 1Variable 0 0 0 0 0 0 0Totals 6 17 10 0 0 0 33 Periods of Calms 0 HoursStability Class: D-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 5 8 3 0 0 0 16 NNE 6 6 5 0 0 0 17 NE 0 2 0 0 0 0 2 ENE 2 0 0 0 0 0 2 E 0 5 2 0 0 0 7 ESE 1 1 1 0 0 0 3 SE 0 11 3 0 0 0 14 SSE 5 5 0 0 0 0 10 S 5 7 7 1 0 0 20 SSW 3 7 15 0 0 0 25 SW 3 3 1 0 0 0 7 WSW 6 2 3 0 0 0 11 W 1 5 0 0 0 0 6 WNW 0 2 4 1 0 0 7 NW 6 8 1 1 0 0 16 NNW 2 6 1 0 0 0 9Variable 0 0 0 0 0 0 0Totals 45 78 46 3 0 0 172 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-74VEPCO North Anna JFD 35-Foot Level-Period of Record: MAY 1/5/74 - 30/4/75Stability Class: E-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 3 1 0 0 0 5 NNE 1 0 0 0 0 0 1 NE 0 0 1 0 0 0 1 ENE 1 0 0 0 0 0 1 E 2 0 0 0 0 0 2 ESE 0 2 0 0 0 0 2 SE 4 0 0 0 0 0 4 SSE 3 8 0 0 0 0 11 S 3 6 1 0 0 0 10 SSW 0 3 1 0 0 0 4 SW 2 3 0 0 0 0 5 WSW 3 2 0 0 0 0 5 W 6 2 0 0 0 0 8 WNW 5 4 3 0 0 0 12 NW 3 2 1 1 0 0 7 NNW 2 2 1 0 0 0 5Variable 0 0 0 0 0 0 0Totals 36 37 9 1 0 0 83 Periods of Calms 0 HoursStability Class: F-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 1 0 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E 1 1 0 0 0 0 2 ESE 0 0 0 0 0 0 0 SE 2 0 0 0 0 0 2 SSE 2 0 0 0 0 0 2 S 1 2 1 0 0 0 4 SSW 2 1 0 0 0 0 3 SW 1 1 0 0 0 0 2 WSW 2 2 0 0 0 0 4 W 2 2 1 0 0 0 5 WNW 3 3 1 0 0 0 7 NW 1 3 1 0 0 0 5 NNW 2 1 0 0 0 0 3Variable 0 0 0 0 0 0 0Totals 20 16 4 0 0 0 40 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-75VEPCO North Anna JFD 35-Foot Level-Period of Record: MAY 1/5/74 - 30/4/75Stability Class: G-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 0 0 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 1 0 0 0 0 0 1 SSE 0 0 0 0 0 0 0 S 0 1 0 0 0 0 1 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 1 0 0 0 0 0 1 W 0 1 1 0 0 0 2 WNW 3 1 2 0 0 0 6 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 6 3 3 0 0 0 12 Periods of Calms 0 Hours Hours of Missing Data: 7Total Observations for MAY: 737 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-76VEPCO North Anna JFD 35-Foot Level-Period of Record: JUN 1/5/74 - 30/4/75Stability Class: A-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 6 17 37 8 1 0 69 NNE 2 16 10 0 0 0 28 NE 4 8 7 0 0 0 19 ENE 4 2 5 1 0 0 12 E 3 14 1 1 1 0 20 ESE 1 10 5 0 0 0 16 SE 5 11 11 0 0 0 27 SSE 1 12 6 0 0 0 19 S 4 9 17 0 0 0 30 SSW 3 6 20 0 0 0 29 SW 0 9 14 1 0 0 24 WSW 1 5 2 2 0 0 10 W 1 6 1 1 0 0 9 WNW 1 5 3 1 0 0 10 NW 0 13 0 0 0 0 13 NNW 1 5 9 1 0 0 16Variable 0 0 0 0 0 0 0Totals 37 148 148 16 2 0 351 Periods of Calms 0 HoursStability Class: B-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 4 2 3 0 0 9 NNE 0 1 1 0 0 0 2 NE 0 1 0 0 0 0 1 ENE 0 0 1 0 0 0 1 E 1 0 0 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 0 2 0 0 0 0 2 SSE 0 0 0 0 0 0 0 S 1 0 0 0 0 0 1 SSW 0 1 0 0 0 0 1 SW 0 0 0 0 0 0 0 WSW 0 3 1 0 0 0 4 W 0 0 0 0 0 0 0 WNW 0 1 0 0 0 0 1 NW 0 0 0 0 0 0 0 NNW 0 2 1 0 0 0 3Variable 0 0 0 0 0 0 0Totals 2 15 6 3 0 0 26 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-77VEPCO North Anna JFD 35-Foot Level-Period of Record: JUN 1/5/74 - 30/4/75Stability Class: C-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 4 3 1 0 0 8 NNE 0 1 3 0 0 0 4 NE 0 0 1 0 0 0 1 ENE 0 3 0 0 0 0 3 E 0 3 0 0 0 0 3 ESE 0 2 0 0 0 0 2 SE 1 1 0 0 0 0 2 SSE 0 1 0 0 0 0 1 S 0 3 0 0 0 0 3 SSW 0 2 0 0 0 0 2 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 1 0 1 0 0 2 WNW 0 0 0 0 0 0 0 NW 0 1 2 0 0 0 3 NNW 1 1 9 0 0 0 11Variable 0 0 0 0 0 0 0Totals 2 23 18 2 0 0 45 Periods of Calms 0 HoursStability Class: D-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 3 5 11 1 0 0 20 NNE 1 0 1 1 0 0 3 NE 4 3 0 0 0 0 7 ENE 2 3 1 0 0 0 7 E 2 4 3 0 0 0 10 ESE 0 5 1 0 0 0 6 SE 1 24 0 0 0 0 25 SSE 3 13 1 0 0 0 17 S 5 8 6 0 0 0 19 SSW 3 12 4 0 0 0 19 SW 5 4 0 0 0 0 9 WSW 4 1 0 0 0 0 5 W 7 4 1 0 0 0 12 WNW 3 2 0 1 0 0 6 NW 2 4 1 0 0 0 7 NNW 1 2 6 1 0 0 10Variable 0 0 0 0 0 0 0Totals 48 94 36 4 0 0 182 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-78VEPCO North Anna JFD 35-Foot Level-Period of Record: JUN 1/5/74 - 30/4/75Stability Class: E-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 0 0 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 1 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E 1 0 0 0 0 0 1 ESE 0 2 1 0 0 0 3 SE 3 3 0 0 0 0 6 SSE 3 9 0 0 0 0 12 S 6 3 0 0 0 0 9 SSW 5 4 0 0 0 0 9 SW 4 3 0 0 0 0 7 WSW 6 4 1 0 0 0 11 W 5 3 0 0 0 0 8 WNW 6 0 0 0 0 0 6 NW 1 0 0 0 0 0 1 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 41 32 2 0 0 0 75 Periods of Calms 0 HoursStability Class: F-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 2 0 0 0 2 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 1 0 0 0 0 1 SE 0 0 0 0 0 0 0 SSE 1 1 0 0 0 0 2 S 2 1 0 0 0 0 3 SSW 0 0 0 0 0 0 0 SW 3 1 0 0 0 0 4 WSW 2 2 0 0 0 0 4 W 6 2 0 0 0 0 8 WNW 4 0 0 0 0 0 4 NW 2 0 0 0 0 0 2 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 20 8 2 0 0 0 30 Periods of Calms 1 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-79VEPCO North Anna JFD 35-Foot Level-Period of Record: JUN 1/5/74 - 30/4/75Stability Class: G-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 1 0 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 1 0 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 0 2 0 0 0 0 2 Periods of Calms 0 Hours Hours of Missing Data: 8Total Observations for JUN: 712 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-80VEPCO North Anna JFD 35-Foot Level-Period of Record: JUL 1/5/74 - 30/4/75Stability Class: A-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 7 5 27 2 0 0 41 NNE 5 6 7 1 0 0 19 NE 6 13 2 0 0 0 21 ENE 5 10 0 0 0 0 15 E 10 12 0 0 0 0 22 ESE 4 4 2 0 0 0 10 SE 3 4 1 0 0 0 8 SSE 5 8 3 0 0 0 16 S 0 16 10 0 0 0 26 SSW 3 17 23 1 0 0 44 SW 1 15 9 0 0 0 25 WSW 7 11 3 0 0 0 21 W 7 5 4 0 0 0 16 WNW 7 5 3 2 0 0 17 NW 10 19 2 0 0 0 31 NNW 7 10 8 1 0 0 26Variable 0 0 0 0 0 0 0Totals 87 160 104 7 0 0 358 Periods of Calms 0 HoursStability Class: B-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 1 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 1 1 0 0 0 0 2 SE 0 1 0 0 0 0 1 SSE 0 1 0 0 0 0 1 S 0 1 0 0 0 0 1 SSW 0 1 1 0 0 0 2 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 1 1 0 0 0 0 2 WNW 1 0 0 0 0 0 1 NW 0 0 0 0 0 0 0 NNW 0 0 3 0 0 0 3Variable 0 0 0 0 0 0 0Totals 3 7 4 0 0 0 14 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-81VEPCO North Anna JFD 35-Foot Level-Period of Record: JUL 1/5/74 - 30/4/75Stability Class: C-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 1 0 0 0 1 ENE 0 1 0 0 0 0 1 E 0 2 0 0 0 0 2 ESE 0 2 1 0 0 0 3 SE 0 1 1 1 0 0 3 SSE 1 0 1 0 0 0 2 S 0 0 0 0 0 0 0 SSW 0 3 0 0 0 0 3 SW 1 4 1 0 0 0 6 WSW 1 1 0 0 0 0 2 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 2 1 0 0 0 0 3 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 5 15 5 1 0 0 26 Periods of Calms 0 HoursStability Class: D-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 3 4 0 0 0 0 7 NNE 2 0 0 0 0 0 2 NE 3 4 1 0 0 0 8 ENE 1 3 0 0 0 0 4 E 2 3 0 0 0 0 5 ESE 0 1 1 0 0 0 3 SE 1 6 6 0 0 0 13 SSE 3 12 0 0 0 0 15 S 5 8 0 0 0 0 13 SSW 3 10 0 0 0 0 13 SW 5 14 2 0 0 0 21 WSW 5 5 0 0 0 0 10 W 8 6 0 0 0 0 14 WNW 4 2 2 0 0 0 8 NW 3 14 9 0 0 0 26 NNW 2 6 4 0 0 0 12Variable 0 0 0 0 0 0 0Totals 51 98 25 0 0 0 173 Periods of Calms 2 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-82VEPCO North Anna JFD 35-Foot Level-Period of Record: JUL 1/5/74 - 30/4/75Stability Class: E-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 4 1 0 0 0 7 NNE 1 0 0 0 0 0 1 NE 0 1 0 0 0 0 1 ENE 2 2 0 0 0 0 4 E 4 0 0 0 0 0 4 ESE 1 0 0 0 0 0 1 SE 5 2 0 0 0 0 7 SSE 2 1 0 0 0 0 3 S 2 1 0 0 0 0 3 SSW 3 2 4 0 0 0 9 SW 3 1 3 0 0 0 7 WSW 3 3 0 0 0 0 6 W 15 3 0 0 0 0 18 WNW 15 3 0 0 0 0 18 NW 7 5 1 0 0 0 13 NNW 2 1 1 0 0 0 4Variable 0 0 0 0 0 0 0Totals 67 29 10 0 0 0 106 Periods of Calms 3 HoursStability Class: F-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 1 0 0 0 0 0 1 NE 1 0 0 0 0 0 1 ENE 1 0 0 0 0 0 1 E 0 1 0 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 1 1 0 0 0 0 2 SSE 1 1 0 0 0 0 2 S 1 0 1 0 0 0 2 SSW 1 0 0 0 0 0 1 SW 2 0 0 0 0 0 2 WSW 2 0 0 0 0 0 2 W 3 5 0 0 0 0 8 WNW 9 2 0 0 0 0 11 NW 5 1 0 0 0 0 6 NNW 0 0 0 0 0 0 2Variable 0 0 0 0 0 0 2Totals 28 11 1 0 0 0 40 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-83VEPCO North Anna JFD 35-Foot Level-Period of Record: JUL 1/5/74 - 30/4/75Stability Class: G-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 1 0 0 0 0 0 1 E 0 0 0 0 0 0 0 ESE 1 0 0 0 0 0 1 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 2 1 0 0 0 0 3 WNW 4 0 0 0 0 0 4 NW 3 0 0 0 0 0 3 NNW 2 0 0 0 0 0 2Variable 0 0 0 0 0 0 0Totals 13 1 0 0 0 0 14 Periods of Calms 0 Hours Hours if Missing Data: 7Total Observations for JUL: 737 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-84VEPCO North Anna JFD 35-Foot Level- Period of Record: AUG 1/5/74 - 30/4/75Stability Class: A-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 12 10 0 0 0 24 NNE 3 8 10 2 0 0 23 NE 4 17 15 1 0 0 37 ENE 3 10 5 1 0 0 19 E 6 6 2 1 0 0 15 ESE 2 2 1 0 0 0 5 SE 0 7 3 0 0 0 10 SSE 1 4 7 0 0 0 12 S 0 13 15 0 0 0 28 SSW 1 11 15 1 0 0 28 SW 2 8 13 1 0 0 24 WSW 0 1 9 0 0 0 10 W 4 2 1 1 0 0 8 WNW 2 3 0 0 0 0 5 NW 4 7 7 0 0 0 18 NNW 4 10 5 0 0 0 19Variable 0 0 0 0 0 0 2Totals 38 121118 8 0 0 285 Periods of Calms 0 HoursStability Class: B-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 1 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 0 1 0 0 0 1 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 1 0 0 0 0 1 SSE 1 2 0 0 0 0 3 S 1 3 5 0 0 0 9 SSW 1 1 0 0 0 0 2 SW 3 3 1 0 0 0 7 WSW 1 0 0 0 0 0 1 W 0 0 0 0 0 0 0 WNW 0 1 0 0 0 0 1 NW 1 2 1 0 0 0 4 NNW 0 1 0 0 0 0 1Variable 0 0 0 0 0 0 0Totals 8 14 9 0 0 0 31 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-85VEPCO North Anna JFD 35-Foot Level- Period of Record: AUG 1/5/74 - 30/4/75Stability Class: C-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 3 1 0 0 0 4 NNE 0 2 1 0 0 0 3 NE 0 1 1 0 0 0 2 ENE 0 0 0 0 0 0 0 E 0 1 1 0 0 0 2 ESE 1 0 0 0 0 0 1 SE 0 0 0 0 0 0 0 SSE 0 2 0 0 0 0 2 S 0 1 0 0 0 0 1 SSW 0 5 0 0 0 0 5 SW 0 3 0 0 0 0 3 WSW 0 0 0 0 0 0 0 W 0 1 0 0 0 0 1 WNW 0 1 0 0 0 0 1 NW 0 1 0 0 0 0 1 NNW 1 2 0 0 0 0 3Variable 0 0 0 0 0 0 0Totals 2 23 4 0 0 0 29 Periods of Calms 0 HoursStability Class: D-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 8 2 0 0 0 10 NNE 1 5 4 0 0 0 10 NE 4 3 2 0 0 0 9 ENE 1 3 0 0 0 0 4 E 3 6 0 0 0 0 9 ESE 0 7 1 1 0 0 9 SE 1 7 0 0 0 0 8 SSE 4 10 0 0 0 0 14 S 9 23 4 0 0 0 36 SSW 6 9 2 0 0 0 17 SW 7 6 2 0 0 0 15 WSW 5 5 0 0 0 0 10 W 2 2 0 0 0 0 4 WNW 2 4 0 0 0 0 6 NW 0 5 0 0 0 0 5 NNW 2 5 1 0 0 0 8Variable 0 0 0 0 0 0 0Totals 47 108 18 1 0 0 174 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-86VEPCO North Anna JFD 35-Foot Level- Period of Record: AUG 1/5/74 - 30/4/75Stability Class: E-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 0 0 0 0 0 1 NNE 0 3 1 0 0 0 4 NE 0 1 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 4 0 0 0 0 0 4 SSE 4 6 0 0 0 0 10 S 5 3 0 0 0 0 8 SSW 5 3 0 0 0 0 8 SW 0 0 0 0 0 0 0 WSW 3 0 0 0 0 0 3 W 8 2 0 0 0 0 10 WNW 1 2 0 0 0 0 3 NW 2 2 0 0 0 0 4 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 33 22 1 0 0 0 56 Periods of Calms 0 HoursStability Class: F-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 1 0 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 1 0 0 0 0 0 1 WSW 4 0 0 0 0 0 4 W 3 5 0 0 0 0 8 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 1 0 0 0 1Variable 0 0 0 0 0 0 0Totals 8 6 1 0 0 0 15 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-87VEPCO North Anna JFD 35-Foot Level- Period of Record: AUG 1/5/74 - 30/4/75Stability Class: G-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 1 0 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 1 0 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 1 1 0 0 0 0 2 NNW 1 0 0 0 0 0 1Variable 0 0 0 0 0 0 0Totals 2 3 0 0 0 0 5 Periods of Calms 0 Hours Hours of Missing Data: 149 Total Observations for Aug: 595 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-88VEPCO North Anna JFD 35-Foot Level- Period of Record: SEP 1/5/74 - 30/4/75Stability Class: A-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 2 7 24 4 0 39 NNE 5 5 11 2 0 0 23 NE 3 6 2 0 0 0 11 ENE 2 2 1 0 0 0 5 E 5 10 0 0 0 0 15 ESE 2 11 2 0 0 0 15 SE 1 10 3 0 0 0 14 SSE 2 13 9 0 0 0 24 S 0 22 12 3 0 0 37 SSW 1 12 17 7 0 0 37 SW 0 3 2 1 0 0 6 WSW 2 5 1 3 0 0 11 W 1 6 1 2 0 0 10 WNW 2 1 0 0 0 0 3 NW 1 0 3 0 1 0 5 NNW 3 1 3 10 0 0 17Variable 0 0 0 0 0 0 0Totals 32 109 74 52 5 0 272 Periods of Calms 0 HoursStability Class: B-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 1 4 1 0 0 6 NNE 0 3 1 1 0 0 5 NE 0 1 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 1 0 0 0 0 1 S 0 1 0 0 0 0 1 SSW 1 1 0 0 0 0 2 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 1 0 0 0 1 WNW 1 1 0 0 0 0 2 NW 0 0 0 0 0 0 0 NNW 0 1 1 0 0 0 2Variable 0 0 0 0 0 0 0Totals 2 10 7 2 0 0 21 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-89VEPCO North Anna JFD 35-Foot Level- Period of Record: SEP 1/5/74 - 30/4/75Stability Class: C-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 1 6 5 0 0 14 NNE 1 5 5 0 0 0 11 NE 0 0 0 0 0 0 0 ENE 0 0 1 0 0 0 1 E 0 0 0 0 0 0 0 ESE 0 1 1 0 0 0 2 SE 0 3 0 0 0 0 3 SSE 0 2 0 0 0 0 2 S 0 0 0 0 0 0 0 SSW 0 3 0 0 0 0 3 SW 1 0 0 0 0 0 1 WSW 0 0 0 0 0 0 0 W 1 0 1 0 0 0 2 WNW 0 0 0 0 0 0 0 NW 0 0 0 1 0 0 1 NNW 0 1 3 2 0 0 6Variable 0 0 0 0 0 0 0Totals 5 16 17 8 0 0 46 Periods of Calms 0 HoursStability Class: D-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 7 18 8 0 0 34 NNE 2 2 4 4 0 0 12 NE 2 0 2 2 0 0 6 ENE 4 2 2 1 0 0 9 E 3 3 0 0 0 0 6 ESE 3 4 3 0 0 0 10 SE 3 7 0 0 0 0 10 SSE 4 4 0 1 0 0 9 S 11 8 3 0 0 0 22 SSW 5 14 1 0 0 0 20 SW 9 5 0 0 0 0 14 WSW 5 3 0 0 0 0 8 W 5 1 0 0 0 0 6 WNW 2 5 1 2 0 0 10 NW 2 8 1 0 0 0 11 NNW 0 2 4 1 0 0 7Variable 0 0 0 0 0 0 0Totals 61 75 39 19 0 0 194 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-90VEPCO North Anna JFD 35-Foot Level- Period of Record: SEP 1/5/74 - 30/4/75Stability Class: E-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 0 2 0 0 0 3 NNE 3 1 4 0 0 0 8 NE 1 1 0 0 0 0 2 ENE 0 1 0 0 0 0 1 E 2 0 0 0 0 0 2 ESE 5 2 0 0 0 0 7 SE 6 4 0 0 0 0 10 SSE 19 9 0 0 0 0 28 S 12 4 2 0 0 0 18 SSW 11 5 0 0 0 0 16 SW 8 1 0 0 0 0 9 WSW 7 1 0 0 0 0 8 W 9 1 0 1 0 0 11 WNW 5 1 0 1 0 0 7 NW 2 2 1 0 0 0 5 NNW 0 1 0 0 0 0 1Variable 0 0 0 0 0 0 0Totals 91 34 9 2 0 0 136 Periods of Calms 0 HoursStability Class: F-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 1 1 0 0 0 0 2 E 1 0 0 0 0 0 1 ESE 1 0 0 0 0 0 1 SE 2 0 0 0 0 0 2 SSE 6 1 0 0 0 0 7 S 6 1 0 0 0 0 7 SSW 1 1 0 0 0 0 2 SW 0 1 0 0 0 0 1 WSW 2 1 0 0 0 0 3 W 11 3 0 0 0 0 14 WNW 2 0 0 0 0 0 2 NW 1 0 0 0 0 0 1 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 34 9 0 0 0 0 43 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-91VEPCO North Anna JFD 35-Foot Level- Period of Record: SEP 1/5/74 - 30/4/75Stability Class: G-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 1 0 0 0 0 1 E 0 1 0 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 1 0 0 0 0 0 1 SSE 0 0 0 0 0 0 0 S 0 1 0 0 0 0 1 SSW 0 0 0 0 0 0 0 SW 0 1 0 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 2 0 0 0 0 0 2 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 3 4 0 0 0 0 7 Periods of Calms 0 Hours Hours of Missing Data: 1 Total Observations for SEP: 719 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-92VEPCO North Anna JFD 35-Foot Level- Period of Record: OCT 1/5/74 - 30/4/75Stability Class: A-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 4 2 21 14 1 0 42 NNE 4 9 6 3 0 0 22 NE 1 1 1 0 0 0 3 ENE 4 3 0 0 0 0 7 E 4 5 0 0 0 0 9 ESE 1 5 1 0 0 0 7 SE 3 0 0 0 0 0 3 SSE 2 2 0 0 0 0 4 S 1 8 8 0 0 0 17 SSW 0 4 11 0 0 0 15 SW 0 1 7 0 0 0 8 WSW 0 1 0 0 0 0 1 W 2 1 0 0 0 0 3 WNW 1 3 3 3 0 0 10 NW 3 11 4 3 0 0 21 NNW 6 2 18 15 0 0 41Variable 0 0 0 0 0 0 0Totals 36 58 80 38 1 0 213 Periods of Calms 0 HoursStability Class: B-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 1 5 0 0 0 6 NNE 0 0 3 0 0 0 3 NE 0 0 2 0 0 0 2 ENE 0 2 1 0 0 0 3 E 0 0 0 0 0 0 0 ESE 1 0 0 0 0 0 1 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 1 0 0 0 0 0 1 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 1 0 0 0 1Variable 0 0 0 0 0 0 0Totals 2 3 12 0 0 0 17 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-93VEPCO North Anna JFD 35-Foot Level-Period of Record: OCT 1/5/74 - 30/4/75Stability Class: C-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 2 1 0 0 0 5 NNE 0 1 3 0 0 0 4 NE 1 3 0 0 0 0 4 ENE 0 1 0 0 0 0 1 E 0 0 0 0 0 0 0 ESE 1 0 1 0 0 0 2 SE 2 0 0 0 0 0 2 SSE 0 0 0 0 0 0 0 S 0 2 0 0 0 0 2 SSW 0 1 0 0 0 0 1 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 2 0 0 0 2Variable 0 0 0 0 0 0 0Totals 6 10 7 0 0 0 23 Periods of Calms 0 HoursStability Class: D-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 14 15 1 0 0 31 NNE 0 8 4 0 0 0 12 NE 2 3 3 0 0 0 8 ENE 1 2 1 0 0 0 4 E 2 2 1 0 0 0 5 ESE 1 3 3 0 0 0 7 SE 1 1 1 0 0 0 3 SSE 0 0 0 0 0 0 0 S 1 3 0 0 0 0 4 SSW 1 7 3 0 0 0 11 SW 0 0 0 0 0 0 0 WSW 1 3 0 0 0 0 4 W 1 0 0 0 0 0 1 WNW 2 3 1 0 0 0 6 NW 1 5 2 0 0 0 8 NNW 2 10 13 0 0 0 25Variable 0 0 0 0 0 0 0Totals 17 64 47 1 0 0 129 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-94VEPCO North Anna JFD 35-Foot Level-Period of Record: OCT 1/5/74 - 30/4/75Stability Class: E-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 3 1 0 1 0 0 5 NNE 1 1 0 0 0 0 2 NE 0 0 0 0 0 0 0 ENE 3 2 0 0 0 0 5 E 2 5 0 0 0 0 7 ESE 1 1 0 0 0 0 2 SE 9 7 0 0 0 0 16 SSE 9 1 0 0 0 0 10 S 9 6 1 0 0 0 16 SSW 3 3 1 0 0 0 7 SW 4 1 0 0 0 0 5 WSW 1 1 0 0 0 0 2 W 10 4 0 0 0 0 14 WNW 9 5 0 0 0 0 14 NW 2 1 0 0 0 0 3 NNW 0 3 1 0 0 0 4Variable 0 0 0 0 0 0 0Totals 66 42 3 1 0 0112 Periods of Calms 0 HoursStability Class: F-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 4 1 0 0 0 0 5 NNE 0 0 0 0 0 0 0 NE 1 0 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E 1 0 0 0 0 0 1 ESE 4 0 0 0 0 0 4 SE 3 1 0 0 0 0 4 SSE 5 2 0 0 0 0 7 S 9 4 0 0 0 0 13 SSW 5 2 0 0 0 0 7 SW 2 0 0 0 0 0 2 WSW 2 0 0 0 0 0 2 W 11 13 1 0 0 0 25 WNW 13 7 0 0 0 0 20 NW 3 4 0 0 0 0 7 NNW 1 1 0 0 0 0 2Variable 0 0 0 0 0 0 0Totals 64 35 1 0 0 0 100 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-95VEPCO North Anna JFD 35-Foot Level-Period of Record: OCT 1/5/74 - 30/4/75Stability Class: G-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 12 0 0 0 0 0 12 NNE 2 0 0 0 0 0 2 NE 1 0 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E 1 0 0 0 0 0 1 ESE 2 1 0 0 0 0 3 SE 1 0 0 0 0 0 1 SSE 3 0 0 0 0 0 3 S 5 1 0 0 0 0 6 SSW 2 0 0 0 0 0 2 SW 2 0 0 0 0 0 2 WSW 2 0 0 0 0 0 2 W 9 2 0 0 0 0 11 WNW 25 3 0 0 0 0 28 NW 14 0 0 0 0 0 14 NNW 2 0 0 0 0 0 2Variable 0 0 0 0 0 0 0Totals 83 7 0 0 0 0 90 Periods of Calms 4 Hours Hours of Missing Data: 56 Total Observations for OCT: 688 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-96VEPCO North Anna JFD 35-Foot Level-Period of Record: NOV 1/5/74 - 30/4/75Stability Class: A-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 5 4 10 0 0 20 NNE 1 7 2 0 0 0 10 NE 0 2 1 0 0 0 3 ENE 2 4 3 0 0 0 9 E 1 2 0 0 0 0 3 ESE 0 3 5 0 0 0 8 SE 0 2 0 0 0 0 2 SSE 0 1 0 0 0 0 1 S 0 6 6 0 0 0 12 SSW 0 1 9 2 0 0 12 SW 0 5 7 0 0 0 12 WSW 1 0 6 4 0 0 11 W 0 1 6 3 0 0 10 WNW 0 2 3 1 0 0 6 NW 0 2 5 3 0 0 10 NNW 1 1 0 5 0 0 7Variable 0 0 0 0 0 0 0Totals 7 44 57 28 0 0 136 Periods of Calms 0 HoursStability Class: B-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 1 1 2 0 0 4 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 1 0 0 0 0 0 1 E 0 0 1 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 1 0 0 0 0 1 SSW 1 1 1 0 0 0 3 SW 0 0 0 0 0 0 0 WSW 0 0 0 3 0 0 3 W 0 0 1 1 0 0 2 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 1 0 2 0 0 0 3Variable 0 0 0 0 0 0 0Totals 3 3 6 6 0 0 18 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-97VEPCO North Anna JFD 35-Foot Level- Period of Record: NOV 1/5/74 - 30/4/75Stability Class: C-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 3 0 0 0 3 NNE 0 0 3 0 0 0 3 NE 0 0 1 1 0 0 2 ENE 0 0 5 2 0 0 7 E 0 0 0 0 0 0 0 ESE 0 0 1 0 0 0 1 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 2 0 0 0 0 2 SSW 0 2 2 0 0 0 4 SW 0 1 2 0 0 0 3 WSW 0 2 0 2 0 0 4 W 0 2 0 0 0 0 2 WNW 0 0 0 0 0 0 0 NW 0 0 1 0 0 0 1 NNW 0 1 2 0 0 0 3Variable 0 0 0 0 0 0 0Totals 0 10 20 5 0 0 35 Periods of Calms 0 HoursStability Class: D-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 3 4 8 0 0 0 15 NNE 1 7 5 0 0 0 13 NE 1 8 1 0 0 0 10 ENE 1 1 0 0 0 0 2 E 0 0 0 0 0 0 0 ESE 0 1 3 0 0 0 4 SE 0 2 2 0 0 0 4 SSE 2 5 3 0 0 0 10 S 3 13 5 1 0 0 22 SSW 1 22 17 0 0 0 40 SW 4 7 11 0 0 0 22 WSW 1 3 6 3 0 0 13 W 0 3 4 4 2 0 13 WNW 0 7 4 2 0 0 13 NW 2 9 6 3 0 0 20 NNW 0 4 9 1 0 0 14Variable 0 0 0 0 0 0 0Totals 19 96 84 14 2 0 215 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-98VEPCO North Anna JFD 35-Foot Level- Period of Record: NOV 1/5/74 - 30/4/75Stability Class: E-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 2 0 0 0 0 4 NNE 0 2 0 0 0 0 2 NE 2 2 0 0 0 0 4 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 1 1 0 0 0 0 2 SE 0 2 0 0 0 0 2 SSE 6 7 3 0 0 0 16 S 3 9 1 0 0 0 13 SSW 6 7 5 0 0 0 18 SW 1 5 2 0 0 0 8 WSW 6 13 5 0 0 0 24 W 10 4 7 1 0 0 22 WNW 4 2 2 0 0 0 8 NW 4 9 3 0 0 0 16 NNW 2 3 1 0 0 0 6Variable 0 0 0 0 0 0 0Totals 47 68 29 1 0 0 145 Periods of Calms 0 HoursStability Class: F-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 0 0 0 0 0 2 NNE 1 0 0 0 0 0 1 NE 0 0 0 0 0 0 0 ENE 1 0 0 0 0 0 1 E 0 0 0 0 0 0 0 ESE 2 0 0 0 0 0 2 SE 3 0 0 0 0 0 3 SSE 4 5 0 0 0 0 9 S 6 1 0 0 0 0 7 SSW 2 2 0 0 0 0 4 SW 3 2 0 0 0 0 5 WSW 5 1 0 0 0 0 6 W 12 1 0 0 0 0 13 WNW 8 6 0 0 0 0 14 NW 0 7 0 0 0 0 7 NNW 1 1 1 0 0 0 3Variable 0 0 0 0 0 0 0Totals 50 26 1 0 0 0 77 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-99VEPCO North Anna JFD 35-Foot Level-Period of Record: NOV 1/5/74 - 30/4/75Stability Class: G-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 18 0 0 0 0 0 18 NNE 1 0 0 0 0 0 1 NE 1 0 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 3 0 0 0 0 0 3 SE 4 2 0 0 0 0 6 SSE 3 2 0 0 0 0 5 S 6 2 0 0 0 0 8 SSW 1 1 0 0 0 0 2 SW 1 0 0 0 0 0 1 WSW 3 0 0 0 0 0 3 W 8 2 0 0 0 0 10 WNW 11 6 0 0 0 0 17 NW 8 4 0 0 0 0 12 NNW 2 1 0 0 0 0 3Variable 0 0 0 0 0 0 0Totals 70 20 0 0 0 0 90 Periods of Calms 0 Hours Hours of Missing Data: 4 Total Observations for NOV: 716 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-100VEPCO North Anna JFD 35-Foot Level-Period of Record: DEC 1/5/74 - 30/4/75Stability Class: A-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 1 0 0 0 0 1 NNE 1 1 0 0 0 0 2 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 2 1 0 0 0 0 3 ESE 0 1 0 0 0 0 1 SE 0 0 0 0 0 0 0 SSE 0 1 0 0 0 0 1 S 0 0 0 0 0 0 0 SSW 0 3 0 0 0 0 3 SW 0 0 0 0 0 0 0 WSW 0 1 0 0 0 0 1 W 1 1 1 0 0 0 3 WNW 1 0 0 0 0 0 1 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 5 10 1 0 0 0 16 Periods of Calms 0 HoursStability Class: B-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 1 0 0 0 0 1 ESE 0 1 1 0 0 0 2 SE 0 0 0 0 0 0 0 SSE 0 1 0 0 0 0 1 S 0 1 0 0 0 0 1 SSW 0 1 1 0 0 0 2 SW 0 0 2 0 0 0 2 WSW 0 0 0 0 0 0 0 W 0 0 1 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 0 5 5 0 0 0 10 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-101VEPCO North Anna JFD 35-Foot Level-Period of Record: DEC 1/5/74 - 30/4/75Stability Class: C-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 1 0 0 1 E 0 0 0 0 0 0 0 ESE 0 1 0 0 0 0 1 SE 0 0 0 0 0 0 0 SSE 0 1 0 0 0 0 1 S 1 1 0 0 0 0 2 SSW 0 1 1 0 0 0 2 SW 0 0 1 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 1 0 0 0 0 0 1 NW 0 1 0 0 0 0 1 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 2 5 2 1 0 0 10 Periods of Calms 0 HoursStability Class: D-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 9 3 1 0 0 14 NNE 1 5 1 0 0 0 7 NE 1 4 0 5 1 0 11 ENE 0 1 0 0 0 1 2 E 2 7 2 0 1 3 15 ESE 1 4 1 0 0 0 6 SE 7 3 0 1 0 0 11 SSE 6 8 0 0 0 0 14 S 3 4 3 0 0 0 10 SSW 1 5 8 1 0 0 15 SW 1 7 10 0 0 0 18 WSW 1 3 16 2 1 0 23 W 0 6 6 4 0 0 16 WNW 1 3 3 2 0 0 9 NW 3 4 2 3 1 0 13 NNW 0 1 2 1 0 0 4Variable 0 0 0 0 0 0 0Totals 29 74 57 20 4 4 188 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-102VEPCO North Anna JFD 35-Foot Level-Period of Record: DEC 1/5/74 - 30/4/75Stability Class: E-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 4 0 0 0 0 5 NNE 1 0 3 1 0 0 5 NE 0 3 4 1 0 0 8 ENE 1 5 0 0 0 0 6 E 1 2 0 0 0 0 3 ESE 0 2 0 1 1 0 4 SE 3 6 3 0 1 0 13 SSE 3 6 3 0 0 0 12 S 2 7 3 0 0 0 12 SSW 5 31 8 0 0 0 44 SW 9 16 13 3 0 0 41 WSW 3 8 4 1 0 0 16 W 2 8 2 1 0 0 13 WNW 5 4 4 2 0 0 15 NW 3 6 0 2 0 0 11 NNW 0 2 1 1 0 0 4Variable 0 0 0 0 0 0 0Totals 39110 48 13 2 0 212 Periods of Calms 0 HoursStability Class: F-Elevation: 35 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 0 0 2 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 1 0 0 0 0 1 ENE 0 1 0 0 0 0 1 E 1 0 0 0 0 0 1 ESE 0 1 0 0 0 0 1 SE 3 1 0 0 0 0 4 SSE 6 3 0 0 0 0 9 S 1 4 0 0 0 0 5 SSW 0 3 0 0 0 0 3 SW 2 2 2 0 0 0 6 WSW 2 1 0 0 0 0 3 W 9 10 0 0 0 0 19 WNW 11 6 0 0 0 0 17 NW 3 0 0 0 0 0 3 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 39 33 2 0 0 0 74 Periods of Calms 1 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-103VEPCO North Anna JFD 35-Foot Level-Period of Record: DEC 1/5/74 - 30/4/75Stability Class: G-Elevation: 35 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 0 0 0 0 0 1 NNE 1 0 0 0 0 0 1 NE 1 0 0 0 0 0 1 ENE 2 0 0 0 0 0 2 E 1 0 0 0 0 0 1 ESE 1 0 0 0 0 0 1 SE 1 0 0 0 0 0 1 SSE 0 0 0 0 0 0 0 S 3 0 0 0 0 0 3 SSW 1 0 0 0 0 0 1 SW 0 1 0 0 0 0 1 WSW 0 2 0 0 0 0 2 W 6 2 0 0 0 0 8 WNW 11 1 0 0 0 0 12 NW 2 0 0 1 0 0 3 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 31 6 0 1 0 0 38 Periods of Calms 0 Hours Hours of Missing Data: 195 Total Observations for DEC: 549 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-104VEPCO North Anna JFD 150-Foot Level-Peri od of Record: 1/5/74 - 30/4/75Stability Class: A-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 31 77112 56 3 0 279 NNE 26 75 52 9 0 0 162 NE 25 66 31 0 0 0 122 ENE 34 43 31 2 0 0110 E 36 36 7 4 0 0 83 ESE 40 53 11 0 0 0 104 SE 21 58 18 0 0 0 97 SSE 19 50 26 0 0 0 95 S 20 92 54 6 0 0 172 SSW 8 75 130 31 0 0 244 SW 12 51 78 29 0 0 170 WSW 6 31 30 7 1 0 75 W 14 28 26 12 3 0 83 WNW 15 26 12 3 1 2 59 NW 24 53 39 9 1 0 126 NNW 28 45 44 27 1 2 147Variable 0 0 0 0 0 0 0Totals 359 859 701 195 10 4 2128 Periods of Calms 0 HoursStability Class: B-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 3 4 14 5 0 0 25 NNE 0 11 9 2 0 0 21 NE 0 6 5 0 0 0 11 ENE 1 2 6 0 0 0 9 E 1 3 2 0 0 0 6 ESE 1 4 2 0 0 0 7 SE 2 9 4 0 0 0 15 SSE 2 4 1 0 0 0 7 S 4 9 9 0 0 0 22 SSW 1 7 7 0 0 0 15 SW 3 5 4 1 0 0 13 WSW 1 5 3 2 0 0 11 W 2 5 2 2 0 1 12 WNW 1 1 1 2 0 2 7 NW 3 2 3 3 1 0 12 NNW 1 8 6 2 1 1 19Variable 0 0 0 0 0 0 0Totals 26 84 78 19 2 4 213 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-105VEPCO North Anna JFD 150-Foot Level- Pe riod of Record: 1/5/74 - 30/4/75Stability Class: C-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 3 14 32 3 0 0 52 NNE 1 12 12 2 0 0 27 NE 1 8 6 1 0 0 16 ENE 2 8 6 3 0 0 19 E 5 7 0 0 0 0 12 ESE 3 7 3 0 0 0 13 SE 4 8 5 0 0 0 17 SSE 3 10 2 0 0 0 15 S 0 9 3 0 0 0 12 SSW 0 10 12 2 0 0 24 SW 6 12 9 1 0 0 28 WSW 1 4 0 0 1 0 6 W 4 6 4 6 0 0 20 WNW 3 4 2 2 0 3 14 NW 4 4 11 4 4 4 31 NNW 6 8 8 1 1 2 26Variable 0 0 0 0 0 0 0Totals 46 131115 25 6 9 332 Periods of Calms 0 HoursStability Class: D-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 26 79 123 18 1 0 247 NNE 21 70 53 8 0 0 152 NE 24 55 33 11 1 0 124 ENE 21 35 16 1 2 0 75 E 22 50 11 0 0 3 86 ESE 16 43 11 1 0 0 71 SE 17 62 31 1 0 0 111 SSE 18 61 11 0 0 0 90 S 23 105 60 8 0 0 196 SSW 24 65 109 39 4 0 241 SW 25 70 94 33 7 0 229 WSW 30 31 24 7 1 0 93 W 19 28 22 14 5 5 93 WNW 15 29 30 16 11 9110 NW 23 62 63 52 12 3 215 NNW 20 56 62 24 5 0 167Variable 0 0 0 0 0 0 0Totals 344 901 753 233 49 20 2300 Periods of Calms 3 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-106VEPCO North Anna JFD 150-Foot Level-Peri od of Record: 1/5/74 - 30/4/75Stability Class: E-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 30 41 34 4 0 0 109 NNE 21 57 24 1 0 0 103 NE 21 46 19 2 0 0 88 ENE 13 26 9 0 0 0 48 E 19 44 14 2 1 0 80 ESE 12 32 9 2 1 0 56 SE 29 54 22 4 1 0110 SSE 17 72 27 2 0 0118 S 20 86 57 10 0 0 173 SSW 18 96 111 24 4 0 253 SW 27 84 69 20 2 0 202 WSW 22 30 38 3 1 0 94 W 23 29 45 12 5 1115 WNW 27 34 23 12 6 2 104 NW 24 55 39 23 7 3 151 NNW 31 50 15 5 2 0 103Variable 0 0 0 0 0 0 0Totals 354 836 555 126 30 6 1907 Periods of Calms 1 HoursStability Class: F-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 22 28 2 0 0 0 52 NNE 7 12 2 0 0 0 21 NE 12 7 1 0 0 0 20 ENE 7 4 0 0 0 0 11 E 9 10 3 0 0 0 22 ESE 10 8 1 0 0 0 19 SE 14 14 7 0 0 0 35 SSE 12 21 3 0 0 0 36 S 12 36 29 0 0 0 77 SSW 5 25 36 0 0 0 66 SW 20 26 7 1 0 0 54 WSW 15 14 10 0 0 0 39 W 19 18 8 0 1 0 46 WNW 24 31 16 2 0 0 73 NW 17 45 7 0 0 0 69 NNW 9 41 9 1 0 0 60Variable 0 0 0 0 0 0 0Totals 214 340 141 4 1 0 700 Periods of Calms 6 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-107VEPCO North Anna JFD 150-Foot Level-Peri od of Record: 1/5/74 - 30/4/75Stability Class: G-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 8 17 5 0 0 0 30 NNE 6 10 2 0 0 0 18 NE 5 7 0 0 0 0 12 ENE 9 5 0 0 0 0 14 E 10 12 0 0 0 0 22 ESE 7 9 0 0 0 0 16 SE 14 10 3 0 0 0 27 SSE 17 14 0 0 0 0 31 S 10 22 17 0 0 0 49 SSW 10 8 13 1 0 0 32 SW 19 16 2 0 0 0 37 WSW 15 17 0 1 0 0 33 W 10 21 2 1 1 0 35 WNW 13 31 1 0 0 0 45 NW 19 19 3 0 0 0 41 NNW 11 18 3 0 0 0 32Variable 0 0 0 0 0 0 0Totals 183 236 51 3 1 0 474 Periods of Calms 6 Hours Hours of Missing Data: 690Total Observations for the Period are: 8070 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-108VEPCO North Anna JFD 150-Foot Level-Period of Record: JAN 1/5/74 - 30/4/75Stability Class: A-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 1 0 0 0 0 0 1 NE 1 0 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E 1 1 0 0 0 0 2 ESE 0 1 0 0 0 0 1 SE 0 0 0 0 0 0 0 SSE 1 0 0 0 0 0 1 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 1 0 0 1 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 2 0 0 0 0 0 2 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 6 2 0 1 0 0 9 Periods of Calms 0 HoursStability Class: B-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 1 0 0 0 0 0 0 WNW 0 0 0 1 0 0 1 NW 0 0 0 0 0 0 1 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 1 0 0 1 0 0 2 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-109VEPCO North Anna JFD 150-Foot Level-Period of Record: JAN 1/5/74 - 30/4/75Stability Class: C-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 1 0 0 0 0 1 ESE 1 0 0 0 0 0 1 SE 1 0 0 0 0 0 1 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 1 0 0 0 0 0 1 WNW 1 0 0 0 0 0 1 NW 2 0 0 0 0 0 2 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 6 1 0 0 0 0 7 Periods of Calms 0 HoursStability Class: D-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 7 11 7 0 0 27 NNE 0 3 2 0 0 0 5 NE 0 2 5 0 0 0 7 ENE 1 5 0 0 0 0 6 E 3 1 2 0 0 0 6 ESE 1 0 0 0 0 0 1 SE 2 2 1 0 0 0 5 SSE 0 8 0 0 0 0 8 S 0 6 8 0 0 0 14 SSW 1 4 5 4 2 0 16 SW 1 1 2 3 2 0 9 WSW 1 3 0 1 0 0 5 W 1 0 3 0 3 3 10 WNW 1 1 1 1 0 0 4 NW 4 5 1 2 0 0 12 NNW 1 3 6 1 0 0 11Variable 0 0 0 0 0 0 0Totals 19 51 47 19 7 3 146 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-110VEPCO North Anna JFD 150-Foot Level-Period of Record: JAN 1/5/74 - 30/4/75Stability Class: E-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 5 4 12 3 0 0 24 NNE 3 8 3 0 0 0 14 NE 3 10 4 0 0 0 17 ENE 4 6 1 0 0 0 11 E 2 8 3 0 0 0 13 ESE 1 3 1 0 0 0 5 SE 4 7 4 1 0 0 16 SSE 0 10 8 2 0 0 20 S 4 16 8 1 0 0 29 SSW 1 11 26 6 0 0 44 SW 6 14 16 11 1 0 48 WSW 1 5 3 1 1 0 11 W 1 5 1 5 4 1 17 WNW 0 0 0 0 5 2 7 NW 1 3 0 0 1 0 5 NNW 4 3 3 0 0 0 10Variable 0 0 0 0 0 0 0Totals 40113 93 30 12 3 291 Periods of Calms 0 HoursStability Class: F-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 1 0 0 0 0 3 NNE 1 0 0 0 0 0 1 NE 0 2 0 0 0 0 2 ENE 1 2 0 0 0 0 3 E 1 1 0 0 0 0 2 ESE 1 1 0 0 0 0 2 SE 0 1 1 0 0 0 2 SSE 0 3 0 0 0 0 3 S 2 6 1 0 0 0 9 SSW 3 5 4 0 0 0 12 SW 3 5 1 0 0 0 9 WSW 2 0 1 0 0 0 3 W 1 1 0 0 0 0 2 WNW 5 4 3 1 0 0 13 NW 3 3 0 0 0 0 6 NNW 1 1 0 0 0 0 2Variable 0 0 0 0 0 0 0Totals 26 36 11 1 0 0 74 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-111VEPCO North Anna JFD 150-Foot Level-Period of Record: JAN 1/5/74 - 30/4/75Stability Class: G-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 4 0 0 0 0 4 NNE 0 2 1 0 0 0 3 NE 1 3 0 0 0 0 4 ENE 1 1 0 0 0 0 2 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 2 1 2 0 0 0 5 SSE 0 0 0 0 0 0 0 S 0 2 2 0 0 0 4 SSW 1 1 0 0 0 0 2 SW 2 0 1 0 0 0 3 WSW 1 3 0 0 0 0 4 W 3 0 0 0 0 0 3 WNW 5 0 0 0 0 0 5 NW 1 1 0 0 0 0 2 NNW 1 2 1 0 0 0 4Variable 0 0 0 0 0 0 0Totals 18 20 7 0 0 0 45 Periods of Calms 1 Hours Hours of Missing Data: 169 Total Observations for JAN: 575 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-112VEPCO North Anna JFD 150-Foot Level-Period of Record: FEB 1/5/74 - 30/4/75Stability Class: A-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 2 0 0 0 0 2 NNE 0 0 0 0 0 0 0 NE 0 1 1 0 0 0 2 ENE 0 1 2 0 0 0 3 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 1 0 0 0 1 SSW 0 2 2 0 0 0 4 SW 0 0 0 0 0 0 0 WSW 0 1 0 0 0 0 1 W 1 0 0 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 1 7 6 0 0 0 14 Periods of Calms 0 HoursStability Class: B-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 0 1 0 0 0 3 NNE 0 0 1 0 0 0 1 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 1 0 0 0 0 1 S 0 0 2 0 0 0 2 SSW 0 0 2 0 0 0 2 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 1 0 0 0 0 0 1 NW 0 0 0 1 0 0 1 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 3 1 6 1 0 0 11 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-113VEPCO North Anna JFD 150-Foot Level-Period of Record: FEB 1/5/74 - 30/4/75Stability Class: C-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 1 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 1 0 0 0 0 0 1 SE 0 0 0 0 0 0 0 SSE 0 2 0 0 0 0 2 S 0 0 1 0 0 0 1 SSW 0 2 3 0 0 0 5 SW 0 0 0 0 0 0 0 WSW 1 0 0 0 0 0 1 W 0 1 1 1 0 0 3 WNW 0 0 0 0 0 0 0 NW 0 1 0 0 3 0 4 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 2 6 6 1 3 0 18 Periods of Calms 0 HoursStability Class: D-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 4 3 9 3 0 0 19 NNE 0 7 4 1 0 0 12 NE 6 10 0 0 0 0 16 ENE 1 0 0 0 0 0 1 E 4 0 0 0 0 0 4 ESE 3 3 0 0 0 0 6 SE 1 2 0 0 0 0 3 SSE 0 0 0 0 0 0 0 S 0 3 5 0 0 0 8 SSW 0 7 10 0 0 0 17 SW 1 3 8 3 3 0 18 WSW 0 1 0 1 0 0 2 W 1 2 3 3 0 0 9 WNW 0 2 4 1 0 0 7 NW 1 3 2 7 0 0 13 NNW 0 3 5 2 1 0 11Variable 0 0 0 0 0 0 0Totals 22 49 50 21 4 0 146 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-114VEPCO North Anna JFD 150-Foot Level-Period of Record: FEB 1/5/74 - 30/4/75Stability Class: E-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 7 10 3 0 0 0 20 NNE 4 23 6 1 0 0 34 NE 6 20 3 0 0 0 29 ENE 2 8 2 0 0 0 12 E 3 5 0 0 0 0 8 ESE 1 3 2 0 0 0 6 SE 3 7 2 0 0 0 12 SSE 1 13 3 0 0 0 17 S 1 9 5 3 0 0 18 SSW 2 13 19 9 0 0 43 SW 1 6 20 4 1 0 32 WSW 3 0 4 2 0 0 9 W 1 1 2 1 0 0 5 WNW 2 2 11 0 0 0 15 NW 2 10 6 7 2 0 27 NNW 5 18 2 1 0 0 26Variable 0 0 0 0 0 0 0Totals 44 148 90 28 3 0 313 Periods of Calms 0 HoursStability Class: F-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 3 3 0 0 0 0 6 NNE 1 0 0 0 0 0 1 NE 2 0 0 0 0 0 2 ENE 1 0 0 0 0 0 1 E 2 0 0 0 0 0 2 ESE 1 0 0 0 0 0 1 SE 3 0 0 0 0 0 3 SSE 5 3 1 0 0 0 9 S 0 3 9 0 0 0 12 SSW 1 6 7 0 0 0 14 SW 2 2 0 0 0 0 4 WSW 0 0 1 0 0 0 1 W 0 2 0 0 0 0 2 WNW 3 4 1 0 0 0 8 NW 1 5 2 0 0 0 8 NNW 0 3 2 1 0 0 6Variable 0 0 0 0 0 0 0Totals 25 31 23 1 0 0 80 Periods of Calms 1 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-115VEPCO North Anna JFD 150-Foot Level-Period of Record: FEB 1/5/74 - 30/4/75Stability Class: G-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 0 0 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 1 0 0 0 0 0 1 E 2 2 0 0 0 0 4 ESE 2 2 0 0 0 0 4 SE 5 2 0 0 0 0 7 SSE 8 2 0 0 0 0 10 S 2 10 3 0 0 0 15 SSW 0 1 1 0 0 0 2 SW 1 1 0 0 0 0 2 WSW 1 0 0 0 0 0 1 W 0 3 0 0 0 0 3 WNW 1 2 0 0 0 0 3 NW 3 2 0 0 0 0 5 NNW 0 3 1 0 0 0 4Variable 0 0 0 0 0 0 0Totals 27 30 5 0 0 0 62 Periods of Calms 2 Hours Hours of Missing Data: 25 Total Observations for FEB: 647 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-116VEPCO North Anna JFD 150-Foot Level-Period of Record: MAR 1/5/74 - 30/4/75Stability Class: A-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 2 0 0 0 0 2 NNE 1 1 0 0 0 0 2 NE 0 0 0 0 0 0 0 ENE 2 0 0 0 0 0 2 E 0 0 1 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 0 1 0 0 0 0 1 SSE 0 1 0 0 0 0 1 S 0 2 0 0 0 0 2 SSW 0 3 1 0 0 0 4 SW 0 1 0 1 0 0 2 WSW 0 0 5 1 1 0 7 W 0 0 1 0 0 0 1 WNW 0 0 1 1 0 0 2 NW 2 3 0 0 0 0 5 NNW 1 2 0 0 0 0 3Variable 0 0 0 0 0 0 0Totals 6 16 9 3 1 0 35 Periods of Calms 0 HoursStability Class: B-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 1 0 0 1 NNE 0 1 0 0 0 0 1 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 1 0 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 2 0 0 0 2 W 0 0 0 0 0 0 0 WNW 0 0 0 1 0 0 1 NW 0 0 1 1 0 0 2 NNW 0 2 0 0 0 0 2Variable 0 0 0 0 0 0 0Totals 0 4 3 3 0 0 10 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-117VEPCO North Anna JFD 150-Foot Level-Period of Record: MAR 1/5/74 - 30/4/75Stability Class: C-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 1 2 0 0 0 3 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 1 1 0 0 0 0 2 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 3 1 0 0 4 SW 0 1 1 0 0 0 2 WSW 0 0 0 0 1 0 1 W 0 0 1 0 0 0 1 WNW 0 0 1 1 0 0 2 NW 0 0 3 1 1 0 5 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 1 3 11 3 2 0 20 Periods of Calms 0 HoursStability Class: D-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 7 9 7 0 0 24 NNE 0 8 6 4 0 0 18 NE 2 12 8 4 0 0 26 ENE 3 3 3 1 0 0 10 E 1 10 0 0 0 0 11 ESE 4 3 0 0 0 0 7 SE 1 2 0 0 0 0 3 SSE 2 3 3 0 0 0 8 S 4 10 11 1 0 0 26 SSW 0 4 6 7 0 0 17 SW 0 5 17 8 0 0 30 WSW 0 3 2 0 0 0 5 W 1 4 0 1 1 0 7 WNW 1 2 5 4 2 0 14 NW 1 2 9 12 6 0 30 NNW 0 3 6 4 0 0 13Variable 0 0 0 0 0 0 0Totals 21 81 85 53 9 0 249 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-118VEPCO North Anna JFD 150-Foot Level-Period of Record: MAR 1/5/74 - 30/4/75Stability Class: E-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 2 3 0 0 0 6 NNE 0 9 6 0 0 0 15 NE 1 3 4 1 0 0 9 ENE 0 4 0 0 0 0 4 E 4 10 6 2 0 0 22 ESE 1 9 2 1 0 0 13 SE 2 12 7 3 1 0 25 SSE 0 8 5 0 0 0 13 S 1 8 11 0 0 0 20 SSW 0 6 8 0 0 0 14 SW 0 9 12 1 0 0 22 WSW 1 0 5 0 0 0 6 W 2 6 11 0 1 0 20 WNW 1 1 0 3 0 0 5 NW 1 3 6 12 3 3 28 NNW 1 4 0 1 2 0 8Variable 0 0 0 0 0 0 0Totals 16 94 86 24 7 3 230 Periods of Calms 0 HoursStability Class: F-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 3 0 0 0 0 0 3 NNE 1 0 1 0 0 0 2 NE 0 2 0 0 0 0 2 ENE 2 0 0 0 0 0 2 E 1 3 2 0 0 0 6 ESE 2 2 1 0 0 0 5 SE 1 6 3 0 0 0 10 SSE 1 0 1 0 0 0 2 S 1 1 5 0 0 0 7 SSW 0 2 2 0 0 0 4 SW 1 0 0 0 0 0 1 WSW 0 2 0 0 0 0 2 W 0 2 2 0 1 0 5 WNW 0 2 1 1 0 0 4 NW 0 0 1 0 0 0 1 NNW 0 1 0 0 0 0 1Variable 0 0 0 0 0 0 0Totals 13 23 19 1 1 0 57 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-119VEPCO North Anna JFD 150-Foot Level-Period of Record: MAR 1/5/74 - 30/4/75Stability Class: G-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 2 0 0 0 0 2 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 2 0 0 0 0 0 2 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 1 1 0 0 0 0 2 SSE 0 3 0 0 0 0 3 S 2 2 0 0 0 0 4 SSW 1 4 1 0 0 0 6 SW 1 3 0 0 0 0 4 WSW 3 2 0 0 0 0 5 W 0 1 1 0 0 0 2 WNW 0 5 0 0 0 0 5 NW 3 2 0 0 0 0 5 NNW 1 2 0 0 0 0 3Variable 0 0 0 0 0 0 0Totals 14 27 2 0 0 0 43 Periods of Calms 0 Hours Hours of Missing Data: 100 Total Observations for MAR: 644 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-120VEPCO North Anna JFD 150-Foot Level-Period of Record: APR 1/5/74 - 30/4/75Stability Class: A-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 4 3 0 0 0 8 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 1 0 0 0 1 E 0 0 0 0 0 0 0 ESE 0 6 0 0 0 0 6 SE 1 4 1 0 0 0 6 SSE 0 2 0 0 0 0 2 S 0 0 1 0 0 0 1 SSW 0 0 5 4 0 0 9 SW 0 0 0 1 0 0 1 WSW 0 0 1 1 0 0 2 W 0 1 1 4 0 0 6 WNW 0 1 0 0 0 2 3 NW 0 6 6 0 0 0 12 NNW 0 3 3 0 1 2 9Variable 0 0 0 0 0 0 0Totals 2 27 22 10 1 4 66 Periods of Calms 0 HoursStability Class: B-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 1 0 0 0 0 0 1 E 0 0 0 0 0 0 0 ESE 1 1 0 0 0 0 2 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 1 0 0 0 1 SSW 0 0 0 0 0 0 0 SW 0 1 0 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 0 1 0 0 1 2 WNW 0 0 0 0 0 2 2 NW 0 0 1 1 1 0 3 NNW 0 0 1 0 1 1 3Variable 0 0 0 0 0 0 0Totals 2 2 4 1 2 4 15 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-121VEPCO North Anna JFD 150-Foot Level-Period of Record: APR 1/5/74 - 30/4/75Stability Class: C-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 1 1 2 0 0 4 NNE 0 1 0 0 0 0 1 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 2 2 0 0 0 0 4 ESE 0 2 0 0 0 0 2 SE 0 0 0 0 0 0 0 SSE 0 2 0 0 0 0 2 S 0 0 1 0 0 0 1 SSW 0 0 0 0 0 0 0 SW 0 0 1 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 1 0 2 0 0 3 WNW 0 1 1 1 0 3 6 NW 0 0 3 3 0 4 10 NNW 0 1 2 1 1 2 7Variable 0 0 0 0 0 0 0Totals 2 11 9 9 1 9 41 Periods of Calms 0 HoursStability Class: D-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 10 17 1 1 0 31 NNE 0 11 7 0 0 0 18 NE 1 9 1 0 0 0 11 ENE 1 13 3 0 0 0 17 E 0 11 4 0 0 0 15 ESE 1 9 3 0 0 0 13 SE 4 8 1 0 0 0 13 SSE 1 6 1 0 0 0 8 S 1 13 4 3 0 0 21 SSW 1 3 9 15 2 0 30 SW 0 1 7 6 2 0 16 WSW 2 0 3 2 1 0 8 W 0 1 1 1 0 2 5 WNW 0 3 0 3 8 9 23 NW 0 11 22 23 6 3 65 NNW 2 10 14 5 4 0 35Variable 0 0 0 0 0 0 0Totals 16119 97 59 24 14 329 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-122VEPCO North Anna JFD 150-Foot Level-Period of Record: APR 1/5/74 - 30/4/75Stability Class: E-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 4 6 2 0 0 0 12 NNE 0 6 2 0 0 0 8 NE 2 7 0 0 0 0 9 ENE 1 3 2 0 0 0 6 E 3 13 3 0 0 0 19 ESE 1 5 2 0 0 0 8 SE 3 8 1 0 0 0 12 SSE 4 2 2 0 0 0 8 S 0 0 6 6 0 0 12 SSW 0 0 3 7 4 0 14 SW 0 1 1 0 0 0 2 WSW 0 1 4 0 0 0 5 W 2 1 1 0 0 0 4 WNW 2 1 0 1 1 0 5 NW 1 4 9 3 0 0 17 NNW 1 2 3 1 0 0 7Variable 0 0 0 0 0 0 0Totals 24 60 41 18 5 0 148 Periods of Calms 0 HoursStability Class: F-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 4 8 0 0 0 0 12 NNE 0 4 0 0 0 0 4 NE 3 0 0 0 0 0 3 ENE 0 0 0 0 0 0 0 E 1 5 0 0 0 0 6 ESE 0 0 0 0 0 0 0 SE 1 2 0 0 0 0 3 SSE 1 1 0 0 0 0 2 S 0 0 0 0 0 0 0 SSW 0 0 1 0 0 0 1 SW 3 0 0 0 0 0 3 WSW 1 0 1 0 0 0 2 W 2 1 0 0 0 0 3 WNW 1 4 3 0 0 0 8 NW 0 4 1 0 0 0 5 NNW 0 3 0 0 0 0 3Variable 0 0 0 0 0 0 0Totals 17 32 6 0 0 0 55 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-123VEPCO North Anna JFD 150-Foot Level-Period of Record: APR 1/5/74 - 30/4/75Stability Class: G-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 1 1 0 0 0 3 NNE 2 2 0 0 0 0 4 NE 1 3 0 0 0 0 4 ENE 0 1 0 0 0 0 1 E 3 1 0 0 0 0 4 ESE 1 0 0 0 0 0 1 SE 2 0 0 0 0 0 2 SSE 1 1 0 0 0 0 2 S 1 1 0 0 0 0 2 SSW 2 0 0 0 0 0 2 SW 3 0 0 0 0 0 3 WSW 2 2 0 0 0 0 4 W 3 2 0 0 1 0 6 WNW 1 8 1 0 0 0 10 NW 4 3 1 0 0 0 8 NNW 3 4 0 0 0 0 7Variable 0 0 0 0 0 0 0Totals 30 29 3 0 1 0 63 Periods of Calms 1 Hours Hours of Missing Data: 2 Total Observations for APR: 718 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-124VEPCO North Anna JFD 150-Foot Level-Period of Record: MA Y 1/5/74 - 30/4/75Stability Class: A-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 9 13 5 0 0 27 NNE 3 20 8 0 0 0 31 NE 1 14 1 0 0 0 16 ENE 5 9 10 0 0 0 24 E 3 10 3 1 0 0 17 ESE 3 10 5 0 0 0 18 SE 4 18 5 0 0 0 27 SSE 3 13 16 0 0 0 32 S 2 14 8 5 0 0 29 SSW 1 7 18 6 0 0 32 SW 1 9 15 4 0 0 29 WSW 0 8 1 1 0 0 10 W 2 2 9 0 1 0 14 WNW 0 7 5 1 0 0 13 NW 0 2 13 1 0 0 16 NNW 2 10 5 2 0 0 19Variable 0 0 0 0 0 0 0Totals 30 162 135 26 1 0 354 Periods of Calms 0 HoursStability Class: B-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 1 3 0 0 0 4 NNE 0 2 4 0 0 0 6 NE 0 2 1 0 0 0 3 ENE 0 0 3 0 0 0 3 E 0 1 1 0 0 0 2 ESE 0 0 2 0 0 0 2 SE 0 5 4 0 0 0 9 SSE 0 1 1 0 0 0 2 S 0 1 1 0 0 0 2 SSW 0 0 0 0 0 0 0 SW 0 1 1 0 0 0 2 WSW 1 1 0 0 0 0 2 W 0 1 0 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 1 1 0 0 0 2Variable 0 0 0 0 0 0 0Totals 1 17 22 0 0 0 40 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-125VEPCO North Anna JFD 150-Foot Level-Period of Record: MA Y 1/5/74 - 30/4/75Stability Class: C-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 4 0 0 0 0 5 NNE 0 1 1 0 0 0 2 NE 1 2 0 0 0 0 3 ENE 1 0 0 0 0 0 1 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 3 0 0 0 0 3 SSE 1 5 1 0 0 0 7 S 0 0 0 0 0 0 0 SSW 0 0 1 0 0 0 1 SW 2 0 2 0 0 0 4 WSW 0 1 0 0 0 0 1 W 0 0 1 0 0 0 1 WNW 0 1 0 0 0 0 1 NW 1 0 0 0 0 0 1 NNW 0 2 1 0 0 0 3Variable 0 0 0 0 0 0 0Totals 7 19 7 0 0 0 33 Periods of Calms 0 HoursStability Class: D-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 14 1 0 0 0 16 NNE 3 9 5 0 0 0 17 NE 2 3 3 0 0 0 8 ENE 2 0 0 0 0 0 2 E 1 4 1 0 0 0 6 ESE 1 2 0 0 0 0 3 SE 4 7 1 0 0 0 12 SSE 4 3 2 0 0 0 9 S 2 2 6 0 0 0 10 SSW 1 9 12 3 0 0 25 SW 2 5 6 0 0 0 13 WSW 5 4 1 1 0 0 11 W 4 4 0 0 0 0 8 WNW 2 4 1 0 0 0 7 NW 2 4 5 0 0 0 11 NNW 1 5 1 0 0 0 7Variable 0 0 0 0 0 0 0Totals 37 79 45 4 0 0 165 Periods of Calms 2 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-126VEPCO North Anna JFD 150-Foot Level-Period of Record: MA Y 1/5/74 - 30/4/75Stability Class: E-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 0 3 0 0 0 4 NNE 1 1 2 0 0 0 4 NE 2 0 1 0 0 0 3 ENE 0 0 0 0 0 0 0 E 2 1 0 0 0 0 3 ESE 2 0 0 0 0 0 2 SE 1 0 0 0 0 0 1 SSE 2 0 0 0 0 0 2 S 3 7 5 0 0 0 15 SSW 0 5 0 0 0 0 5 SW 2 3 0 0 0 0 5 WSW 1 2 0 0 0 0 3 W 5 1 1 0 0 0 7 WNW 4 4 2 0 0 0 10 NW 3 1 1 0 0 0 5 NNW 0 3 1 1 0 0 5Variable 0 0 0 0 0 0 0Totals 29 28 16 1 0 0 74 Periods of Calms 0 HoursStability Class: F-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 1 0 0 0 0 2 NNE 0 2 0 0 0 0 2 NE 0 0 0 0 0 0 0 ENE 0 1 0 0 0 0 1 E 1 0 0 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 2 0 0 0 0 0 2 S 2 2 0 0 0 0 4 SSW 0 1 0 0 0 0 1 SW 1 1 0 0 0 0 2 WSW 2 0 0 0 0 0 2 W 5 6 2 0 0 0 13 WNW 0 2 0 0 0 0 2 NW 2 0 0 0 0 0 2 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 16 16 2 0 0 0 34 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-127VEPCO North Anna JFD 150-Foot Level-Period of Record: MA Y 1/5/74 - 30/4/75Stability Class: G-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 0 0 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 1 0 0 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 1 0 0 0 0 0 1 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 4 0 0 0 0 4 WNW 3 1 0 0 0 0 4 NW 1 0 0 0 0 0 1 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 7 5 0 0 0 0 12 Periods of Calms 0 Hours Hours of Missing Data: 30 Total Observations for MAY: 714 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-128VEPCO North Anna JFD 150-Foot Level-Period of Record: JUN 1/5/74 - 30/4/75Stability Class: A-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 5 21 30 4 0 0 60 NNE 4 24 7 0 0 0 35 NE 2 14 4 0 0 0 20 ENE 7 2 7 1 0 0 17 E 4 3 0 2 0 0 9 ESE 13 13 0 0 0 0 26 SE 6 15 5 0 0 0 26 SSE 3 8 6 0 0 0 17 S 4 7 12 0 0 0 23 SSW 3 11 20 0 0 0 34 SW 6 12 14 1 0 0 33 WSW 2 1 3 0 0 0 6 W 1 7 1 2 0 0 11 WNW 2 5 1 1 0 0 9 NW 2 12 1 0 0 0 15 NNW 0 4 6 0 0 0 10Variable 0 0 0 0 0 0 0Totals 64 159117 11 0 0 351 Periods of Calms 0 HoursStability Class: B-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 2 5 0 0 0 8 NNE 0 3 0 0 0 0 3 NE 0 0 0 0 0 0 0 ENE 0 1 1 0 0 0 2 E 1 0 0 0 0 0 1 ESE 0 1 0 0 0 0 1 SE 0 1 0 0 0 0 1 SSE 0 1 0 0 0 0 1 S 1 0 0 0 0 0 1 SSW 0 0 0 0 0 0 0 SW 1 0 0 0 0 0 1 WSW 0 2 1 0 0 0 3 W 0 1 0 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 2 1 0 0 0 3Variable 0 0 0 0 0 0 0Totals 4 14 8 0 0 0 26 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-129VEPCO North Anna JFD 150-Foot Level-Period of Record: JUN 1/5/74 - 30/4/75Stability Class: C-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 3 8 0 0 0 12 NNE 0 2 2 0 0 0 4 NE 0 1 1 0 0 0 2 ENE 1 4 0 0 0 0 5 E 0 0 0 0 0 0 0 ESE 1 1 0 0 0 0 2 SE 2 1 0 0 0 0 3 SSE 0 1 0 0 0 0 1 S 0 2 0 0 0 0 2 SSW 0 2 0 0 0 0 2 SW 1 0 0 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 1 0 1 0 0 2 WNW 0 0 0 0 0 0 0 NW 0 2 1 0 0 0 3 NNW 2 1 3 0 0 0 6Variable 0 0 0 0 0 0 0Totals 8 21 15 1 0 0 45 Periods of Calms 0 HoursStability Class: D-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 3 7 16 0 0 0 26 NNE 2 0 3 0 0 0 5 NE 2 2 0 0 0 0 4 ENE 4 4 2 0 0 0 10 E 3 3 2 0 0 0 8 ESE 0 6 0 0 0 0 6 SE 1 15 11 0 0 0 27 SSE 2 10 3 0 0 0 15 S 0 10 6 0 0 0 16 SSW 7 3 12 0 0 0 22 SW 5 5 2 0 0 0 12 WSW 5 3 0 0 0 0 8 W 2 3 2 0 0 0 7 WNW 3 1 2 0 0 0 6 NW 4 4 0 0 0 0 8 NNW 1 1 0 0 0 0 2Variable 0 0 0 0 0 0 0Totals 44 77 61 0 0 0 182 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-130VEPCO North Anna JFD 150-Foot Level-Period of Record: JUN 1/5/74 - 30/4/75Stability Class: E-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 1 0 0 0 0 1 NE 1 1 0 0 0 0 2 ENE 0 0 0 0 0 0 0 E 1 1 0 0 0 0 2 ESE 0 2 1 0 0 0 3 SE 4 3 0 0 0 0 7 SSE 0 5 2 0 0 0 7 S 4 5 3 0 0 0 12 SSW 3 1 1 0 0 0 5 SW 5 8 0 0 0 0 13 WSW 2 3 1 0 0 0 6 W 2 1 0 0 0 0 3 WNW 5 5 0 0 0 0 10 NW 1 1 0 0 0 0 2 NNW 2 0 0 0 0 0 2Variable 0 0 0 0 0 0 0Totals 30 37 8 0 0 0 75 Periods of Calms 0 HoursStability Class: F-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 2 0 0 0 0 3 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 1 0 0 0 0 1 SE 0 0 0 0 0 0 0 SSE 0 2 0 0 0 0 2 S 0 1 0 0 0 0 1 SSW 0 1 0 0 0 0 1 SW 3 1 0 0 0 0 4 WSW 3 2 2 0 0 0 7 W 3 0 0 0 0 0 3 WNW 2 1 0 0 0 0 3 NW 3 0 0 0 0 0 3 NNW 0 2 0 0 0 0 2Variable 0 0 0 0 0 0 0Totals 15 13 2 0 0 0 30 Periods of Calms 1 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-131VEPCO North Anna JFD 150-Foot Level-Period of Record: JUN 1/5/74 - 30/4/75Stability Class: G-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 1 0 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 1 0 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 0 2 0 0 0 0 2 Periods of Calms 0 Hours Hours of Missing Data: 8 Total Observations for JUN: 712 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-132VEPCO North Anna JFD 150-Foot Level-Period of Record: JUL 1/5/74 - 30/4/75Stability Class: A-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 6 10 19 1 0 0 36 NNE 4 8 9 0 0 0 21 NE 10 10 1 0 0 0 21 ENE 9 8 0 0 0 0 17 E 13 6 1 0 0 0 20 ESE 7 5 1 0 0 0 13 SE 4 3 0 0 0 0 7 SSE 5 11 0 0 0 0 16 S 3 21 6 0 0 0 30 SSW 1 18 22 3 0 0 44 SW 0 11 10 1 0 0 22 WSW 0 14 5 0 0 0 19 W 3 13 5 0 0 0 21 WNW 6 3 0 0 0 0 9 NW 9 15 6 1 0 0 31 NNW 13 8 8 2 0 0 31Variable 0 0 0 0 0 0 0Totals 93 164 93 8 0 0 358 Periods of Calms 0 HoursStability Class: B-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 1 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 1 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 1 0 0 0 0 1 SE 1 1 0 0 0 0 2 SSE 0 1 0 0 0 0 1 S 0 0 0 0 0 0 0 SSW 0 3 0 0 0 0 3 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 1 0 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 1 1 0 0 0 0 2 NNW 0 0 1 0 0 0 1Variable 0 0 0 0 0 0 0Totals 2 9 1 1 0 0 13 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-133VEPCO North Anna JFD 150-Foot Level-Period of Record: JUL 1/5/74 - 30/4/75Stability Class: C-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 1 0 0 0 0 1 NE 0 0 0 0 0 0 0 ENE 0 1 0 0 0 0 1 E 1 1 0 0 0 0 2 ESE 0 3 1 0 0 0 4 SE 0 1 2 0 0 0 3 SSE 0 0 0 0 0 0 0 S 0 0 1 0 0 0 1 SSW 0 0 3 0 0 0 3 SW 2 5 0 0 0 0 7 WSW 0 1 0 0 0 0 1 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 8 NW 0 0 0 0 0 0 0 NNW 2 1 0 0 0 0 3Variable 0 0 0 0 0 0 0Totals 5 14 7 0 0 0 26 Periods of Calms 0 HoursStability Class: D-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 3 2 0 0 0 0 5 NNE 3 3 1 0 0 0 7 NE 4 1 0 0 0 0 5 ENE 1 2 1 0 0 0 4 E 2 3 1 0 0 0 6 ESE 1 4 0 0 0 0 5 SE 1 4 5 0 0 0 10 SSE 3 11 1 0 0 0 15 S 3 11 4 0 0 0 18 SSW 4 7 0 0 0 0 11 SW 4 12 6 0 0 0 22 WSW 5 5 0 0 0 0 10 W 4 1 0 0 0 0 5 WNW 4 4 1 0 0 0 9 NW 2 8 8 1 0 0 19 NNW 6 11 4 0 0 0 21Variable 0 0 0 0 0 0 0Totals 50 89 32 1 0 0 172 Periods of Calms 1 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-134VEPCO North Anna JFD 150-Foot Level-Period of Record: JUL 1/5/74 - 30/4/75Stability Class: E-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 3 1 2 0 0 0 6 NNE 5 0 2 0 0 0 7 NE 0 0 0 0 0 0 0 ENE 1 2 0 0 0 0 3 E 2 2 0 0 0 0 4 ESE 2 2 0 0 0 0 4 SE 2 3 0 0 0 0 5 SSE 3 3 0 0 0 0 6 S 1 3 0 0 0 0 4 SSW 5 7 0 0 0 0 12 SW 0 6 0 0 0 0 6 WSW 2 2 0 0 0 0 4 W 3 5 1 0 0 0 9 WNW 5 5 1 0 0 0 11 NW 9 11 1 0 0 0 21 NNW 5 1 0 0 0 0 6Variable 0 0 0 0 0 0 0Totals 48 53 7 0 0 0 108 Periods of Calms 0 HoursStability Class: F-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 1 0 0 0 0 0 1 NE 2 0 0 0 0 0 2 ENE 3 0 0 0 0 0 3 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 2 0 0 0 0 0 2 SSE 2 0 0 0 0 0 2 S 0 2 0 0 0 0 2 SSW 1 0 0 0 0 0 1 SW 2 2 0 0 0 0 4 WSW 1 2 0 0 0 0 3 W 4 1 0 0 0 0 5 WNW 2 0 2 0 0 0 4 NW 2 5 0 0 0 0 7 NNW 1 0 0 0 0 0 1Variable 0 0 0 0 0 0 0Totals 23 12 2 0 0 0 37 Periods of Calms 3 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-135VEPCO North Anna JFD 150-Foot Level-Period of Record: JUL 1/5/74 - 30/4/75Stability Class: G-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 1 0 0 0 0 0 1 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 1 0 0 0 0 0 1 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 1 0 0 0 0 0 1 SSW 0 0 0 0 0 0 0 SW 2 1 0 0 0 0 3 WSW 0 1 0 0 0 0 1 W 1 0 0 0 0 0 1 WNW 1 1 0 0 0 0 2 NW 1 0 0 0 0 0 1 NNW 2 0 0 0 0 0 2Variable 0 0 0 0 0 0 0Totals 10 3 0 0 0 0 13 Periods of Calms 1 Hours Hours of Missing Data: 12 Total Observations for JUL: 732 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-136VEPCO North Anna JFD 150-Foot Level-Period of Record: AUG 1/5/74 - 30/4/75Stability Class: A-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 8 17 6 0 0 0 31 NNE 6 9 9 0 0 0 24 NE 5 16 13 0 0 0 34 ENE 7 10 7 1 0 0 25 E 9 5 2 0 0 0 17 ESE 5 4 1 0 0 0 10 SE 3 3 1 0 0 0 7 SSE 3 8 2 0 0 0 13 S 4 21 8 0 0 0 33 SSW 2 7 14 3 0 0 26 SW 3 13 16 1 0 0 33 WSW 2 2 8 0 0 0 12 W 4 1 2 1 0 0 8 WNW 2 1 0 0 0 0 3 NW 6 6 1 0 0 0 13 NNW 5 11 7 0 0 0 23Variable 0 0 0 0 0 0 0Totals 74 134 97 7 0 0 312 Periods of Calms 0 HoursStability Class: B-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 1 0 0 0 0 1 NE 0 1 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 1 0 0 0 0 1 SE 0 0 0 0 0 0 0 SSE 1 0 0 0 0 0 1 S 1 5 5 0 0 0 11 SSW 0 3 0 0 0 0 3 SW 1 3 2 0 0 0 6 WSW 0 1 0 0 0 0 1 W 1 0 0 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 1 1 1 0 0 0 3 NNW 1 2 0 0 0 0 3Variable 0 0 0 0 0 0 0Totals 6 18 8 0 0 0 32 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-137VEPCO North Anna JFD 150-Foot Level-Period of Record: AUG 1/5/74 - 30/4/75Stability Class: C-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 2 0 0 0 0 2 NNE 0 4 0 0 0 0 4 NE 0 1 1 0 0 0 2 ENE 0 1 0 0 0 0 1 E 1 1 0 0 0 0 2 ESE 0 1 1 0 0 0 2 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 3 0 0 0 0 3 SSW 0 2 0 0 0 0 2 SW 1 3 1 0 0 0 5 WSW 0 1 0 0 0 0 1 W 0 1 0 0 0 0 2 WNW 0 1 0 0 0 0 1 NW 1 0 0 0 0 0 1 NNW 1 2 0 0 0 0 3Variable 0 0 0 0 0 0 0Totals 5 23 3 0 0 0 31 Periods of Calms 0 HoursStability Class: D-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 3 1 0 0 0 0 7 NNE 7 7 5 0 0 0 19 NE 4 3 1 0 0 0 8 ENE 4 5 0 0 0 0 9 E 3 4 0 0 0 0 7 ESE 2 5 2 0 0 0 9 SE 1 8 0 0 0 0 9 SSE 1 7 0 0 0 0 8 S 7 28 3 0 0 0 38 SSW 8 6 9 0 0 0 23 SW 8 9 7 1 0 0 25 WSW 6 3 0 0 0 0 9 W 2 3 2 0 0 0 7 WNW 2 3 0 0 0 0 5 NW 3 5 0 0 0 0 8 NNW 3 3 1 0 0 0 7Variable 0 0 0 0 0 0 0Totals 64 103 30 1 0 0 198 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-138VEPCO North Anna JFD 150-Foot Level-Period of Record: AUG 1/5/74 - 30/4/75Stability Class: E-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 0 0 0 0 0 2 NNE 3 0 1 0 0 0 4 NE 0 2 0 0 0 0 2 ENE 0 1 0 0 0 0 1 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 3 0 0 0 0 0 3 SSE 3 8 0 0 0 0 11 S 4 6 0 0 0 0 10 SSW 1 5 4 0 0 0 10 SW 2 1 1 0 0 0 4 WSW 1 1 0 0 0 0 2 W 5 1 0 0 0 0 6 WNW 2 1 0 0 0 0 3 NW 3 2 0 0 0 0 5 NNW 3 0 0 0 0 0 3Variable 0 0 0 0 0 0 0Totals 32 28 6 0 0 0 66 Periods of Calms 1 HoursStability Class: F-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 1 0 0 0 0 1 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 1 0 0 0 0 0 1 SSW 0 1 0 0 0 0 1 SW 1 1 0 0 0 0 2 WSW 0 0 0 0 0 0 0 W 1 0 0 0 0 0 1 WNW 1 2 0 0 0 0 3 NW 3 2 0 0 0 0 5 NNW 1 2 0 0 0 0 3Variable 0 0 0 0 0 0 0Totals 8 9 0 0 0 0 17 Periods of Calms 1 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-139VEPCO North Anna JFD 150-Foot Level-Period of Record: AUG 1/5/74 - 30/4/75Stability Class: G-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 0 0 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 1 0 0 0 0 0 1 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 1 NW 0 1 0 0 0 0 1 NNW 1 1 0 0 0 0 1Variable 0 0 0 0 0 0 0Totals 3 2 0 0 0 0 5 Periods of Calms 0 Hours Hours of Missing Data: 81 Total Observations for AUG: 663 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-140VEPCO North Anna JFD 150-Foot Level-Period of Record: SEP 1/5/74 - 30/4/75Stability Class: A-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 7 2 17 28 0 0 54 NNE 0 8 8 1 0 0 17 NE 3 5 4 0 0 0 12 ENE 1 4 2 0 0 0 7 E 4 4 0 0 0 0 8 ESE 7 9 3 0 0 0 19 SE 0 9 1 0 0 0 10 SSE 3 4 0 0 0 0 7 S 6 16 12 1 0 0 35 SSW 1 20 23 8 0 0 52 SW 2 3 8 7 0 0 20 WSW 0 3 1 2 0 0 6 W 1 0 2 0 1 0 4 WNW 2 1 0 0 0 0 3 NW 1 1 0 0 0 0 2 NNW 2 1 0 2 0 0 5Variable 0 0 0 0 0 0 0Totals 40 90 81 49 1 0 261 Periods of Calms 0 HoursStability Class: B-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 3 0 0 0 3 NNE 0 3 4 0 0 0 7 NE 0 2 0 0 0 0 2 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 1 0 0 0 0 1 SSW 1 0 1 0 0 0 2 SW 1 0 0 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 1 0 0 0 0 1 WNW 0 1 1 0 0 0 2 NW 0 0 0 0 0 0 0 NNW 0 1 1 0 0 0 2Variable 0 0 0 0 0 0 0Totals 2 9 10 0 0 0 21 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-141VEPCO North Anna JFD 150-Foot Level-Period of Record: SEP 1/5/74 - 30/4/75Stability Class: C-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 3 14 0 0 0 18 NNE 0 3 5 0 0 0 8 NE 0 3 2 0 0 0 5 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 1 0 0 0 1 SE 0 2 1 0 0 0 3 SSE 0 0 1 0 0 0 1 S 0 2 0 0 0 0 2 SSW 0 0 1 0 0 0 1 SW 0 2 0 0 0 0 2 WSW 0 0 0 0 0 0 0 W 2 0 1 0 0 0 3 WNW 0 0 0 0 0 0 0 NW 0 0 1 0 0 0 1 NNW 0 0 1 0 0 0 1Variable 0 0 0 0 0 0 0Totals 3 15 28 0 0 0 46 Periods of Calms 0 HoursStability Class: D-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 8 27 0 0 0 37 NNE 1 3 6 1 0 0 11 NE 1 2 2 3 0 0 8 ENE 1 1 5 0 0 0 7 E 4 6 1 0 0 0 11 ESE 0 3 2 0 0 0 5 SE 1 7 1 1 0 0 10 SSE 1 3 1 0 0 0 5 S 2 6 2 0 0 0 10 SSW 2 11 16 0 0 0 29 SW 3 11 8 0 0 0 22 WSW 4 1 2 0 0 0 7 W 3 4 2 0 0 0 9 WNW 0 2 0 2 0 0 4 NW 3 6 1 0 0 0 10 NNW 2 4 1 1 0 0 8Variable 0 0 0 0 0 0 0Totals 30 78 77 8 0 0 193 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-142VEPCO North Anna JFD 150-Foot Level-Period of Record: SEP 1/5/74 - 30/4/75Stability Class: E-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 3 1 2 0 0 0 6 NNE 1 1 0 0 0 0 2 NE 2 0 4 1 0 0 7 ENE 0 0 1 0 0 0 1 E 1 0 0 0 0 0 1 ESE 3 2 0 0 0 0 5 SE 5 6 2 0 0 0 13 SSE 4 11 0 0 0 0 15 S 1 13 4 0 0 0 18 SSW 4 8 8 0 0 0 20 SW 1 13 4 0 0 0 18 WSW 4 1 0 0 0 0 5 W 1 2 0 0 0 0 3 WNW 4 3 0 2 0 0 9 NW 2 4 1 0 0 0 7 NNW 1 0 1 0 0 0 2Variable 0 0 0 0 0 0 0Totals 37 65 27 3 0 0 132 Periods of Calms 0 HoursStability Class: F-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 0 0 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 1 0 0 0 0 1 ESE 1 0 0 0 0 0 1 SE 2 2 0 0 0 0 4 SSE 1 6 0 0 0 0 7 S 2 4 1 0 0 0 7 SSW 0 3 4 0 0 0 7 SW 1 1 0 0 0 0 2 WSW 0 1 0 0 0 0 1 W 0 0 0 0 0 0 0 WNW 0 0 2 0 0 0 2 NW 2 5 0 0 0 0 7 NNW 1 0 0 0 0 0 1Variable 0 0 0 0 0 0 0Totals 11 23 7 0 0 0 41 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-143VEPCO North Anna JFD 150-Foot Level-Period of Record: SEP 1/5/74 - 30/4/75Stability Class: G-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 1 0 0 0 0 1 ESE 0 1 0 0 0 0 1 SE 0 0 0 0 0 0 0 SSE 1 0 0 0 0 0 1 S 0 1 0 0 0 0 1 SSW 0 0 1 0 0 0 1 SW 0 1 0 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 1 4 1 0 0 0 6 Periods of Calms 0 Hours Hours of Missing Data: 20 Total Observations for SEP: 700 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-144VEPCO North Anna JFD 150-Foot Level-Period of Record: OCT 1/5/74 - 30/4/75Stability Class: A-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 3 4 18 10 0 0 35 NNE 5 2 10 8 0 0 25 NE 2 4 6 0 0 0 12 ENE 3 4 0 0 0 0 7 E 1 4 0 0 0 0 5 ESE 2 3 0 0 0 0 5 SE 2 2 1 0 0 0 5 SSE 1 3 1 0 0 0 5 S 0 8 3 0 0 0 11 SSW 0 3 17 0 0 0 20 SW 0 0 12 3 0 0 15 WSW 2 2 1 0 0 0 5 W 2 1 0 0 0 0 3 WNW 2 4 3 0 0 0 9 NW 1 7 5 5 1 0 19 NNW 2 6 13 15 0 0 36Variable 0 0 0 0 0 0 0Totals 28 57 90 41 1 0 217 Periods of Calms 0 HoursStability Class: B-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 2 0 0 0 2 NNE 0 0 0 2 0 0 2 NE 0 0 4 0 0 0 4 ENE 0 1 2 0 0 0 3 E 0 1 0 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 2 0 0 0 0 0 2 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 1 0 0 1Variable 0 0 0 0 0 0 0Totals 2 2 8 3 0 0 15 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-145VEPCO North Anna JFD 150-Foot Level-Period of Record: OCT 1/5/74 - 30/4/75Stability Class: C-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 3 0 0 0 3 NNE 0 0 4 0 0 0 4 NE 0 1 1 0 0 0 2 ENE 0 2 1 0 0 0 3 E 0 1 0 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 1 0 1 0 0 0 2 SSE 2 0 0 0 0 0 2 S 0 0 0 0 0 0 0 SSW 0 2 0 0 0 0 2 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 2 0 0 0 0 0 2 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 5 6 10 0 0 0 21 Periods of Calms 0 HoursStability Class: D-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 8 20 0 0 0 30 NNE 1 7 11 0 0 0 19 NE 0 3 6 0 0 0 9 ENE 0 0 2 0 0 0 2 E 0 3 0 0 0 0 3 ESE 1 2 1 0 0 0 4 SE 0 1 5 0 0 0 6 SSE 1 1 0 0 0 0 2 S 1 0 1 0 0 0 2 SSW 0 2 1 1 0 0 4 SW 0 4 4 1 0 0 9 WSW 0 0 1 0 0 0 1 W 0 1 1 0 0 0 2 WNW 1 1 0 0 0 0 2 NW 3 5 1 0 0 0 9 NNW 1 5 6 3 0 0 15Variable 0 0 0 0 0 0 0Totals 11 43 60 5 0 0119 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-146VEPCO North Anna JFD 150-Foot Level-Period of Record: OCT 1/5/74 - 30/4/75Stability Class: E-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 3 1 1 0 0 6 NNE 2 0 1 0 0 0 3 NE 1 1 0 0 0 0 2 ENE 1 0 0 0 0 0 1 E 0 1 2 0 0 0 3 ESE 1 5 0 0 0 0 6 SE 2 5 4 0 0 0 11 SSE 0 4 1 0 0 0 5 S 0 5 0 0 0 0 5 SSW 1 9 8 0 0 0 18 SW 3 12 4 1 0 0 20 WSW 2 3 1 0 0 0 6 W 0 1 0 0 0 0 1 WNW 1 4 0 0 0 0 5 NW 0 5 1 0 0 0 6 NNW 0 12 1 0 0 0 13Variable 0 0 0 0 0 0 0Totals 15 70 24 2 0 0 111 Periods of Calms 0 HoursStability Class: F-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 6 1 0 0 0 9 NNE 1 5 1 0 0 0 7 NE 0 1 1 0 0 0 2 ENE 0 1 0 0 0 0 1 E 2 0 0 0 0 0 2 ESE 1 1 0 0 0 0 2 SE 1 1 0 0 0 0 2 SSE 0 3 1 0 0 0 4 S 0 5 6 0 0 0 11 SSW 0 4 10 0 0 0 14 SW 3 10 2 0 0 0 15 WSW 2 3 0 0 0 0 5 W 1 2 1 0 0 0 4 WNW 4 6 1 0 0 0 11 NW 0 9 1 0 0 0 10 NNW 1 16 1 0 0 0 18Variable 0 0 0 0 0 0 0Totals 18 73 26 0 0 0117 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-147VEPCO North Anna JFD 150-Foot Level-Period of Record: OCT 1/5/74 - 30/4/75Stability Class: G-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 2 0 0 0 0 2 NNE 1 1 0 0 0 0 2 NE 0 1 0 0 0 0 1 ENE 2 3 0 0 0 0 5 E 1 6 0 0 0 0 7 ESE 2 5 0 0 0 0 7 SE 0 3 0 0 0 0 3 SSE 4 2 0 0 0 0 6 S 2 2 2 0 0 0 6 SSW 2 1 7 0 0 0 10 SW 8 4 1 0 0 0 13 WSW 5 3 0 0 0 0 8 W 2 1 0 0 0 0 3 WNW 1 7 0 0 0 0 8 NW 1 3 0 0 0 0 4 NNW 0 3 1 0 0 0 4Variable 0 0 0 0 0 0 0Totals 31 47 11 0 0 0 89 Periods of Calms 0 Hours Hours of Missing Data: 55 Total Observations for OCT: 689 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-148VEPCO North Anna JFD 150-Foot Level-Period of Record: NOV 1/5/74 - 30/4/75Stability Class: A-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 6 6 8 3 0 24 NNE 10 3 1 0 0 0 5 NE 0 2 1 0 0 0 3 ENE 0 5 2 0 0 0 7 E 0 3 0 0 0 0 3 ESE 0 2 1 0 0 0 3 SE 0 3 4 0 0 0 7 SSE 0 0 1 0 0 0 1 S 1 2 3 0 0 0 6 SSW 0 3 7 7 0 0 17 SW 0 2 3 10 0 0 15 WSW 0 0 5 1 0 0 6 W 0 1 5 5 1 0 12 WNW 0 3 2 0 1 0 6 NW 1 1 7 2 0 0 11 NNW 1 0 2 6 0 0 9Variable 0 0 0 0 0 0 0Totals 5 36 50 39 5 0 135 Periods of Calms 0 HoursStability Class: B-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 1 0 3 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 1 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 1 0 0 0 0 0 1 S 0 0 0 0 0 0 0 SSW 0 1 1 0 0 0 2 SW 0 0 0 1 0 0 1 WSW 0 1 0 2 0 0 3 W 0 0 1 2 0 0 3 WNW 0 0 0 0 0 0 0 NW 1 0 0 0 0 0 1 NNW 0 0 1 1 0 0 2Variable 0 0 0 0 0 0 0Totals 2 3 4 9 0 0 18 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-149VEPCO North Anna JFD 150-Foot Level-Period of Record: NOV 1/5/74 - 30/4/75Stability Class: C-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 3 1 0 0 4 NNE 0 0 0 2 0 0 2 NE 0 0 1 1 0 0 2 ENE 0 0 5 2 0 0 7 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 1 0 0 0 1 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 1 1 1 0 0 3 SW 0 1 3 1 0 0 5 WSW 0 1 0 0 0 0 1 W 0 2 0 2 0 0 4 WNW 0 1 0 0 0 0 1 NW 0 0 3 0 0 0 3 NNW 0 1 1 0 0 0 2Variable 0 0 0 0 0 0 0Totals 0 7 18 10 0 0 35 Periods of Calms 0 HoursStability Class: D-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 5 11 0 0 0 17 NNE 0 7 3 1 0 0 11 NE 0 5 7 0 0 0 12 ENE 0 1 0 0 0 0 1 E 0 0 0 0 0 0 0 ESE 0 0 1 0 0 0 1 SE 1 1 6 0 0 0 8 SSE 0 1 0 0 0 0 1 S 0 7 9 3 0 0 19 SSW 0 6 21 9 0 0 36 SW 1 8 15 11 0 0 35 WSW 1 4 4 1 0 0 10 W 0 2 3 7 1 0 13 WNW 1 2 6 3 1 0 13 NW 0 7 9 3 0 0 19 NNW 1 5 13 2 0 0 21Variable 0 0 0 0 0 0 0Totals 6 61 108 40 2 0 217 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-150VEPCO North Anna JFD 150-Foot Level- Peri od of Record: NOV 1/5/74 - 30/4/75Stability Class: E-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 1 8 2 0 0 0 11 NNE 1 3 0 0 0 0 4 NE 0 2 2 0 0 0 4 ENE 2 0 0 0 0 0 2 E 0 1 0 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 0 2 0 0 0 0 2 SSE 0 2 1 0 0 0 3 S 0 4 9 0 0 0 13 SSW 1 5 13 2 0 0 21 SW 4 6 4 2 0 0 16 WSW 2 7 6 0 0 0 15 W 1 2 17 4 0 0 24 WNW 0 2 2 1 0 0 5 NW 0 4 8 0 0 0 12 NNW 4 2 4 1 0 0 11Variable 0 0 0 0 0 0 0Totals 16 50 68 10 0 0 144 Periods of Calms 0 HoursStability Class: F-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 3 1 0 0 0 4 NNE 0 0 0 0 0 0 0 NE 2 1 0 0 0 0 3 ENE 0 0 0 0 0 0 0 E 1 0 0 0 0 0 1 ESE 2 1 0 0 0 0 3 SE 2 2 0 0 0 0 4 SSE 0 1 0 0 0 0 1 S 2 5 4 0 0 0 11 SSW 0 1 6 0 0 0 7 SW 0 2 3 1 0 0 6 WSW 4 4 1 0 0 0 9 W 1 2 1 0 0 0 4 WNW 3 2 1 0 0 0 6 NW 0 6 2 0 0 0 8 NNW 1 3 6 0 0 0 10Variable 0 0 0 0 0 0 0Totals 18 33 25 1 0 0 77 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-151VEPCO North Anna JFD 150-Foot Level-Period of Record: NOV 1/5/74 - 30/4/75Stability Class: G-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 3 4 0 0 0 9 NNE 1 3 1 0 0 0 5 NE 0 0 0 0 0 0 0 ENE 2 0 0 0 0 0 2 E 1 0 0 0 0 0 1 ESE 0 1 0 0 0 0 1 SE 1 1 1 0 0 0 3 SSE 2 4 0 0 0 0 6 S 0 3 10 0 0 0 13 SSW 2 1 3 1 0 0 7 SW 2 3 0 0 0 0 5 WSW 3 4 0 0 0 0 7 W 1 7 0 0 0 0 8 WNW 1 5 0 0 0 0 6 NW 4 7 1 0 0 0 12 NNW 1 3 0 0 0 0 4Variable 0 0 0 0 0 0 0Totals 23 45 20 1 0 0 89 Periods of Calms 1 Hours Hours of Missing Data: 4 Total Observations for NOV: 716 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-152VEPCO North Anna JFD 150-Foot Level-Period of Record: DEC 1/5/74 - 30/4/75Stability Class: A-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 1 0 0 0 0 0 1 NE 1 0 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E 1 0 0 0 0 0 1 ESE 3 0 0 0 0 0 3 SE 1 0 0 0 0 0 1 SSE 0 0 0 0 0 0 0 S 0 1 0 0 0 0 1 SSW 0 1 1 0 0 0 2 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 2 0 0 0 0 2 WNW 1 1 0 0 0 0 2 NW 0 0 0 0 0 0 0 NNW 2 0 0 0 0 0 2Variable 0 0 0 0 0 0 0Totals 10 5 1 0 0 0 16 Periods of Calms 0 HoursStability Class: B-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 1 2 0 0 0 0 3 SSE 0 0 0 0 0 0 0 S 0 2 0 0 0 0 2 SSW 0 0 3 0 0 0 3 SW 0 0 1 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 1 0 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0Variable 0 0 0 0 0 0 0Totals 1 5 4 0 0 0 10 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-153VEPCO North Anna JFD 150-Foot Level-Period of Record: DEC 1/5/74 - 30/4/75Stability Class: C-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 0 0 0 0 0 0 0 NNE 1 0 0 0 0 0 1 NE 0 0 0 0 0 0 0 ENE 0 0 0 1 0 0 1 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 1 0 0 0 0 1 SSE 0 0 0 0 0 0 0 S 0 2 0 0 0 0 2 SSW 0 1 0 0 0 0 1 SW 0 0 1 0 0 0 1 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 1 0 0 0 0 1 NNW 1 0 0 0 0 0 1Variable 0 0 0 0 0 0 0Totals 2 5 1 1 0 0 9 Periods of Calms 0 HoursStability Class: D-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 4 2 0 0 0 8 NNE 4 5 0 1 0 0 10 NE 2 3 0 4 1 0 10 ENE 3 1 0 0 2 0 6 E 1 5 0 0 0 3 9 ESE 2 6 2 1 0 0 11 SE 0 5 0 0 0 0 5 SSE 3 8 0 0 0 0 11 S 3 9 1 1 0 0 14 SSW 0 3 8 0 0 0 11 SW 0 6 12 0 0 0 18 WSW 1 4 11 1 0 0 17 W 1 3 5 2 0 0 11 WNW 0 4 10 2 0 0 16 NW 0 2 5 4 0 0 11 NNW 2 3 5 6 0 0 16Variable 0 0 0 0 0 0 0Totals 24 71 61 22 3 3 184 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-154VEPCO North Anna JFD 150-Foot Level-Period of Record: DEC 1/5/74 - 30/4/75Stability Class: E-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 6 4 0 0 0 12 NNE 1 5 1 0 0 0 7 NE 3 0 1 0 0 0 4 ENE 2 2 3 0 0 0 7 E 1 2 0 0 1 0 4 ESE 0 1 1 1 1 0 4 SE 0 1 2 0 0 0 3 SSE 0 6 5 0 0 0 11 S 1 10 6 0 0 0 17 SSW 0 26 21 0 0 0 47 SW 3 5 7 1 0 0 16 WSW 3 5 14 0 0 0 22 W 0 3 11 2 0 0 16 WNW 1 6 7 5 0 0 19 NW 1 7 6 1 1 0 16 NNW 5 5 0 0 0 0 10Variable 0 0 0 0 0 0 0Totals 23 90 89 10 3 0 215 Periods of Calms 0 HoursStability Class: F-Elevation: 150 Feet
Direction 1-3 4-7 8-12 13-18 19-24>24Total N 5 4 0 0 0 0 9 NNE 2 1 0 0 0 0 3 NE 3 1 0 0 0 0 4 ENE 0 0 0 0 0 0 0 E 0 0 1 0 0 0 1 ESE 2 1 0 0 0 0 3 SE 2 0 3 0 0 0 5 SSE 0 2 0 0 0 0 2 S 2 7 3 0 0 0 12 SSW 0 1 2 0 0 0 3 SW 0 1 1 0 0 0 2 WSW 0 0 4 0 0 0 4 W 1 1 2 0 0 0 4 WNW 3 4 2 0 0 0 9 NW 1 6 0 0 0 0 7 NNW 3 10 0 0 0 0 13Variable 0 0 0 0 0 0 0Totals 24 39 18 0 0 0 81 Periods of Calms 0 Hours The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-155VEPCO North Anna JFD 150-Foot Level-Period of Record: DEC 1/5/74 - 30/4/75Stability Class: G-Elevation: 150 Feet Direction 1-3 4-7 8-12 13-18 19-24>24Total N 2 5 0 0 0 0 7 NNE 1 2 0 0 0 0 3 NE 3 0 0 0 0 0 3 ENE 1 0 0 0 0 0 1 E 2 2 0 0 0 0 4 ESE 0 0 0 0 0 0 0 SE 3 2 0 0 0 0 5 SSE 1 2 0 0 0 0 3 S 1 1 0 0 0 0 2 SSW 2 0 0 0 0 0 2 SW 0 2 0 0 0 0 2 WSW 0 2 0 1 0 0 3 W 0 2 1 1 0 0 4 WNW 0 1 0 0 0 0 1 NW 1 0 1 0 0 0 2 NNW 2 1 0 0 0 0 3Variable 0 0 0 0 0 0 0Totals 19 22 2 2 0 0 45 Periods of Calms 0 Hours Hours of Missing Data: 184 Total Observations for DEC: 560 The following information is HIST ORICAL and is not intended or expected to be updated for the life of the plant.
Table 11.C-15 (continued)MONTHLY AND ANNUAL JOINT FREQUENCY DISTRIBUTIONS OFWIND SPEED AND DIRECTION BY ATMOSPHERIC STABILITY CLASS Revision 52-09/29/2016 NAPS UFSAR 11C-156The following information is HISTORICAL and is not intended or ex pected to be updated for the life of the plant.Table 11.C-16MAXIMUM ELEVATIONS WITH IN A 10-MILE RADIUS OF THE NORTH ANNA UNIT 1 CONTAINMENT (1-MILE INCREMENTS)
Sector High Points, ft 0-1 1-2 2-3 3-4 4-5 5-6 6-7 7-8 8-9 9-10 N 260 346 370 380 380 410 420 450 450 460 NNE 300 351 360 390 390 370 400 405 390 412 NE 300 330 360 350 350 380 390 400 384 360 ENE 270 320 340 310 360 370 350 330 330 320 E 290 310 320 320 310 330 350 380 384 370 ESE 290 290 300 310 310 300 310 360 370 370 SE 290 290 290 270 290 330 330 320 340 340 SSE 300 300 290 330 330 320 360 360 350 330 S 310 320 330 330 340 360 360 350 340 340 SSW 320 330 320 350 380 400 390 420 390 400 SW 351 370 380411 440 460 480 490 470 450 WSW 350 390 403 410 420 450 470 500 500 480 W 320 370 360 390 420 436 470 480 450 440 WNW 330 360 330 380 420 430 360 380 370 380 NW 310 350 320 360 330 370 370 370 380 380 NNW 270 330 350 350 380 400 430 440 420 484 Revision 52-09/29/2016 NAPS UFSAR 11C-157 The following information is HI ST ORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-17 PARAMETERS USED TO DESCRIBE TH E PRESSURIZED WATER REACTOR WITHU-TUBE STEAM GENERATORS (VOLATILE CHEMISTRY)ParametersValue Thermal power (MWt) 2.90E+03Steam flow rate, lb/hr 1.22E+07Weight of water in reactor coolant system, lb 4.34E+05Weight of water in reactor coolant system, lb 4.34E+05Weight of water in all steam generators, lb 5.02E+05 Reactor coolant letdown fl ow (purification), lb/hr 2.23E+04 Reactor coolant letdown flow (yearl y average for boron control), lb/hr 3.40E+03Steam generator blowdown flow (total), lb/hr 3.25E+04 Fraction of radioactivity in blowdown stream which is not returned to the secondary coolant system Halogens 9.01E-01 Cs, Rb 5.36E-01 Others 9.04E-01Flow through the purification system cation demineralizer , lb/hr 2.23E+03 Ratio of condensate demineralizer flow rate to the total steam flow rate 6.59E-01 Ratio of the total amount of noble gases routed to gaseous radwaste from the purification system to the total amount of noble gases routed from the primary coolant system to the purification system (not including the boron recovery system)0.0 Notes:1.The reactor coolant concentrat ions given are for reactor cool ant entering the letdown line.2.The secondary coolant concentrations are based on a primary-to-secondary leakage of 100 lb/day.3.The steam-generator steam con centrations given are for steam leaving the steam generator.4.Values used in determining coolant activities are given on pp.
B-59 to B-65 of draft Regulatory Guide 1.BB.5.These coolant activities are calculate d according to draft Regulatory Guide 1.BB (September 9, 1975) methods.
Revision 52-09/29/2016 NAPS UFSAR11C-158The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-18 SOURCE TERMS FOR PWR WITH U-TUBE STEAM GENERATORS IsotopeReactor CoolantSteam Generator LiquidsSteam-GeneratorSteamDecay Constant
(µCi/g)(Ci)(µCi/g)(Ci)(µCi/g)(sec-1)Noble GasesKr-83m2.2E-024.4E+000.00.07.6E-091.04E-04Kr-85m1.1E-012.2E+010.00.03.9E-084.30E-05 Kr-851.9E-023.7E+000.00.06.5E-092.05E-09 Kr-876.4E-021.3E+010.00.02.1E-081.52E-04 Kr-882.1E-014.2E+010.00.07.1E-086.88E-05 Kr-895.4E-031.1E+000.00.01.9E-093.66E-03 Xe-131m3.8E-027.6E+000.00.01.3E-086.69E-07 Xe-133m1.6E-013.1E+010.00.05.5E-083.60E-06 Xe-1339.3E+001.8E+030.00.03.2E-061.52E-06 Xe-135m1.4E-022.8E+000.00.04.8E-097.55E-04 Xe-1353.5E-016.8E+010.00.01.2E-072.10E-05 Xe-1379.7E-031.9E+000.00.03.3E-093.01E-03 Xe-1384.8E-029.4E+000.00.01.6E-088.14E-04 HalogensBr-835.4E-031.1E+007.3E-081.7E-057.3E-108.02E-05 Br-842.8E-035.6E-011.2E-082.7E-061.2E-103.66E-04 Br-853.3E-046.4E-022.0E-104.5E-082.0E-124.03E-03 I-1302.6E-035.0E-016.7E-081.5E-056.7E-101.55E-05 Revision 52-09/29/2016 NAPS UFSAR11C-159 Halogens (continued)I-1313.7E-017.2E+011.1E-052.5E-031.1E-079.98E-07I-1321.1E-012.2E+012.0E-064.5E-042.0E-088.43E-05 I-1334.8E-019.4E+011.4E-053.2E-031.4E-079.26E-06 I-1345.2E-021.0E+013.5E-078.1E-053.5E-092.20E-04 I-1352.2E-014.4E+014.8E-061.1E-034.8E-082.92E-05 Cs, RbRb-861.1E-042.1E-021.9E-084.4E-061.9E-114.30E-07 Rb-882.2E-014.3E+016.4E-071.5E-046.4E-106.53E-04 Cs-1343.1E-026.2E+005.2E-061.2E-035.2E-091.07E-08 Cs-1361.6E-023.2E+002.8E-066.4E-042.8E-096.17E-07 Cs-1372.3E-024.5E+004.3E-069.8E-044.3E-097.30E-10Water Activation ProductsN-164.0E+017.9E+039.0E-072.0E-049.0E-079.75E-02TritiumH-31.0E+002.0E+021.0E-032.3E-011.0E-031.79E-09 Other NuclidesCr-512.6E-035.1E-012.8E-076.5E-052.8E-102.88E-07 Mn-544.2E-048.4E-026.4E-081.5E-056.4E-112.56E-08The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-18 (continued)SOURCE TERMS FOR PWR WITH U-TUBE STEAM GENERATORS Isotope Reactor CoolantSteam Generator LiquidsSteam-GeneratorSteamDecay Constant
(µCi/g)(Ci)(µC i/g)(C i)(µCi/g)(sec-1)
Revision 52-09/29/2016 NAPS UFSAR11C-160 Other Nuclides (continued)Fe-552.2E-034.3E-012.6E-075.8E-052.6E-108.14E-09Fe-591.4E-032.7E-011.9E-074.3E-051.9E-101.78E-07 Co-582.2E-024.3E+002.5E-065.8E-042.5E-091.12E-07 Co-602.7E-035.4E-012.9E-076.5E-052.9E-104.18E-09 Sr-894.8E-049.4E-026.3E-081.4E-056.3E-121.59E-07 Sr-901.4E-052.7E-031.3E-092.9E-071.3E-127.58E-10 Sr-917.8E-041.5E-019.6E-092.2E-069.6E-122.03E-05 Y-902.2E-054.4E-031.1E-092.6E-071.1E-123.01E-06 Y-91m4.2E-048.2E-023.3E-097.6E-073.3E-122.32E-04 Y-912.7E-035.4E-012.9E-076.5E-052.9E-101.37E-07 Y-931.6E-043.1E-023.9E-099.0E-073.9E-121.89E-05 Zr-958.2E-051.6E-021.3E-082.9E-061.3E-111.23E-07 Nb-956.8E-051.3E-021.3E-082.9E-061.3E-112.29E-07 Mo-995.9E-011.2E+022.0E-054.5E-032.0E-082.92E-06 Tc-99m4.4E-018.7E+011.0E-052.3E-031.0E-083.20E-05 Ru-1036.1E-051.2E-026.3E-091.4E-066.3E-122.03E-07 Ru-1061.4E-052.7E-031.3E-092.9E-071.3E-122.17E-08 Rh-103m4.9E-059.8E-032.3E-095.1E-072.3E-122.06E-04 Rh-1061.1E-052.1E-033.9E-108.9E-083.9E-102.32E-02The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-18 (continued)SOURCE TERMS FOR PWR WITH U-TUBE STEAM GENERATORS Isotope Reactor CoolantSteam Generator LiquidsSteam-GeneratorSteamDecay Constant
(µCi/g)(Ci)(µC i/g)(C i)(µCi/g)(sec-1)
Revision 52-09/29/2016 NAPS UFSAR11C-161 Other Nuclides (continued)Te-125m4.0E-057.8E-031.9E-094.3E-071.9E-121.38E-07Te-127m3.8E-047.5E-023.2E-087.3E-063.2E-117.36E-08 Te-1271.0E-032.0E-015.8E-081.3E-055.8E-112.05E-05 Te-129m1.9E-033.8E-011.9E-104.3E-051.9E-102.40E-07 Te-1291.8E-033.5E-017.0E-081.6E-057.0E-111.65E-04 Te-131m3.2E-036.3E-012.5E-075.8E-052.5E-106.42E-06 Te-1311.2E-032.4E-012.1E-084.8E-062.1E-114.62E-04 Te-1323.6E-027.0E+002.9E-066.6E-042.9E-092.47E-06 Ba-1371.7E-023.4E+008.8E-072.0E-048.8E-104.53E-03 Ba-1403.0E-045.9E-023.1E-087.1E-063.1E-116.27E-07 La-1401.9E-043.8E-021.9E-084.2E-061.9E-114.79E-06 Ce-1419.5E-051.9E-021.3E-082.9E-061.3E-112.47E-07 Ce-1435.1E-051.0E-022.6E-095.9E-072.6E-125.83E-06 Ce-1444.5E-058.9E-036.4E-091.5E-066.4E-122.82E-08 Pr-1436.8E-051.3E-026.2-091.4E-066.2E-125.91E-07 Pr-1443.6E-057.1E-032.0E-094.7E-072.0E-126.69E-04 Np-2391.6E-033.1E-011.7E-073.8E-051.7E-103.41E-06The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Table 11.C-18 (continued)SOURCE TERMS FOR PWR WITH U-TUBE STEAM GENERATORS Isotope Reactor CoolantSteam Generator LiquidsSteam-GeneratorSteamDecay Constant
(µCi/g)(Ci)(µC i/g)(C i)(µCi/g)(sec-1)
Revision 52-09/29/2016 NAPS UFSAR11C-162The following information is HISTORICAL and is not intended or expected to be updated for the life of the plant.Figure 11C-1FLOW CHART FOR LIQUID WASTE SYSTEM