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Amend XI to Environ Rept
	ML20039G438
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Site:	Clinch River
Issue date:	01/31/1982
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C0RRECTED C0PY o INSTRUCTIONS AMENDMENT XI The replacement pages in the enclosed packets are to be inserted in the CRBRP Environmental Report as follows:

VOLUME 1 Section Pages to be Replaced Table of Contents Replace pages 3 through 6 Add page 5a Replace pages 16, 16a, 17 and 18 List of Tables Replace pages 34, 35 Delete pages 35a, 36, 36a Add page 36 ,

Replace pages 58 and 59 List of Figures Replace pages 67, 68, 69 and 70

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2.6 Remove entire Section 2.6 Add pages 2.6-1 through 2.6-70 VOLUME 2 3.1 Replace pages 3.1-7 and -3.1-8

3.4 Replace pages 3.4-16 and 3.4-17 3.5 Replace pages 3.5-23 through 3.5-26 Replace pages 3.5-33 and 3.5-34 5.4 Replace pages 5.4-12a, 5.4-13 and 5.4-14 6.1 Replace pages 6.1-29a, 6.1-30, 6.1-31, 6.1-32, 6.1-32a, 6.1-32b Replace pages 6.1-38a, 6.1-38b, 6.1-38c LJ 8201180231 820108 A DR ADOCK 05000537 PDR

VOLUME 2 Pages to be Replaced

_ Section 9

7.1 Remove entire Section 7.1 Add pages 7.1-1 through 7.1-71 7.2 Remove entire Section~7.2

Add pages 7.2-1 through 7.2-8 VOLUME 3 13.0 Replace pages 13.0-12 and 13.0-12a Replace page 13.0-32a Replace page 13.0-35 through 13.0-38a VOLUME 5

Amendment XI Insert Amendment XI Tab and page AXI-1

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U Department of Energy Washington, D.C. 20545 Docket No. 50-537 JAN 0 81981 Mr. Paul S. Check, Director CRBR Program Office Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Check:

AMENDMENT ?!0. XI TO THE ENVIRON?1 ENTAL REPORT FOR THE CLINCH RIVER BREEDER REACTOR PLANT The application for a Construction Permit and Class 104(b) Operating License for the Clinch River Breeder Reactor Plant, docketed April 10,1975, in tRC p) q--

Docket No. 50-537, is hereby amended by the submission of Amendment No. XI to the Environmental Report, pursuant to 10 CFR Part 51. This amendment incorporates revisions to Section 2.6, " Meteorology" and Chapter 7 " Environ-mental Effects of Accidents."

A Certificate of Service, confinning service of Amendment No. XI to the Environmental Report upon the designated local public officials and representatives of Government agencies, will be filed with your office after service has been made. Three signed originals of this letter and 41 copies of this amendment, each with a copy of the submittal letter, are hereby submitted.

Sincerely,

., Ok (r W 1/-

Jo n R. Longene r, Manager

! Licensing 14 EnytS6nmental Coordination Office of Nuclear Energy

Enclosure:

'As Stated gg g g cc: Service List SUBSCR an SWORN to before me l Standard Distribution this u d day of January, 1982.

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Licensing Distribution Notary Public l

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SERVICE LIST

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Atomic Safety & Licensing Board Dr. Cadet H. Hand, Jr., Director U. S. Nuclear Regulatory Commission Bodega Marine Laboratory Washington, D. C. 20555 University of California P. O. Box 247 Atomic Safety & Licensing Board Panel Bodega Bay, CA U. S. Nuclear Regulatory Commission 94923 Washington, D. C. 20555 Lewis E. Wallace, Esq.

Mr. Gerald Largen Division of Law Office of the County Executive Tennessee Valley Authority Knoxville, TN 37902 Roane County Courthouse Kingston, TN 37763 Dr. Thomas Cochran Natural Resources Defense Council, Inc.

1725 I Street, NW Suite 600 Wash.ington, DC 20006

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Docketing & Service Station Office of the Secretary U. S. Nuclear Regulatory Comission Washington, DC 20555

/~m (j Counsel for NRC Staff U. S. Nuclear Regulatory Comission Washington, DC 20555 William B. Hubbard, Esq.

Assistant Attorney General State nf Tennessee .

Office of the Attorney General 422 Supreme Cour.t Bui-ldingr Nashville, TN 37219 Mr. Gustave A. Linenberger Atomic Safety & Licensing Board U. S. Nuclear Regulatory Commission Wash.ington, DC 20555 Marshall E. Miller, Esq.

Chaiman Atomic Safety & Licensing Board U. S. Nuclear Regulatory Commission Washington, DC 20555 Luther M. Reed, Esq.

Attorney for the City of Oak Ridge 253 Main Street, East O'

Oak Ridge, TN 37830 10/19f81

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STANDARD DISTRIBUTION Mr. Lochlir. W. Caffey, Director (2)

Clinch River Breeder Reactor Plant Project P. O. Box U Oak Ridge, TN 37830 Mr. George G. Glenn, Manager (2)

Clinch River Project General Electric Company Advanced Reactor Systems Department P. O. Box 508 Sunnyvale, CA 94086 Mr. William J. Purcell, Project (2)

Manager Clinch River Breeder Reactor Plant Project Westinghouse Electric Corporation

' Advanced Reactors Division .

Clinch River Site P. O. Box W Oak Ridge, _ TN 37830 p Mr. W. W. Dewald, Project Manager CRBRP Reactor Plant (2)

V Westinghouse Electric Corporation Advanced Reactors Division P. O. Box 158 Madison, PA 15663 lir. R. J. Beeley, Program Manager (2)

Clinch River Breeder Reactor Plant Atomics--International Division Rockwell International P. O. Box 309 Mr. M. C. Ascher, Project Manager (2)

CRBRP Project Burns and Roe, Inc, 700 Kinderkamack Road Oradell, NJ 07649 Mr. H. R. Lane, Resident Manager (1)

Burns & Roe, Inc.

P. O. Box T Oak Ridge, TN 37830 i

Mr. Dean Armstrong, Acting Project (2)

Manager i

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/ Stone & Webster Engineering Division l P. O. Box 811 Oak Ridge, TN 37830 l

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LICENSING DISTRIBUTION O

Mr. Hugh Pa'rris Manager of Power- .

Tennessee Valley Authori.ty 50.0A CST 2 Chattanooga, TN 37401 Mr John Taylor Electric Power Research Institute 3412 Hillview Avenue Palo Alto, CA 94303 Dr. Jeffrey H. Broido Man.ager Analysis and Safety Department Gas Cooled Fast Reactor Pr.ogram General Atomic Company P. O. Box 81608 San Diego, CA 92138 O ~

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10/19/81

INSTRUCTIONS AMENDMENT XI 1

The replacement pages in the enclosed packets are to be inserted in the CRBRP Environmental Report as follows:

VOLUME 1

-Section Pages to be Replaced Table of Contents Replace pages 3 through 6 Add page 5a Replace pages 16, 16a, 17 and 18 List of Tables Replace pages 34, 35 Delete pages 35a, 36, 36a Add page 36 Replace pages 58 and 59 .

List of Figures Replace pages 67, 68, 69 and 70 2.6 Remove entire Section 2.6 Add pages 2.6-1 through 2.6-70 VOLUME 2 3.1 Replace pages 3.1-17 and 3.1-18 l

l 3.4 Replace pages 3.4-16 and 3.4-17 3.5 Replace pages 3.5-23 through 3.5-26 f Replace pages 3.5-33 and 3.5-34 5.4 Replace pages 5.4-12a, 5.4-13 and 5.4-14 6.1 Replace pages 6.1-29a, 6.1-30, 6.1-31, 6.1-32, 6.1-32a, 6.1-32b l

Replace pages 6.1-38a, 6.1-38b, 6.1-38c A

I i VOLUME 2 Section Pages to be Replaced ;

I 7.1 Remove entire Section 7.1 Add pages 7.1-1 through 7.1-71

7.2 Replace pages 7.2-1 through 7.2-6 Add page 7.2-Sa Add page 7.2-8 f.

VOLUNE 3 13.0 Replace pages 13.0-12 and 13.0-12a Replace page 13.0-32a

Replace page 13.0-35 through 13.0-38a I

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1 TABLE OF CONTENTS Page 2.3.2 Historic Features 2.3-2 2.3.3 Archaeological Features 2.3-4 2.3.4 Effects of Plant Construction and Operation 2.3-10 2.4 Geology 2.4-1 2.4.1 General 2.4-1 2.4.2 Geologic History 2.4-2 i 2.4.2.1 Regional 2.4-2 2.4.2.2 Site Geology 2.4-3 2.4.2.3 Physiography 2.4-4 2.4.3 Stratigraphy and Lithology 2.4-6 2.4.3.1 Knox Group 2.4-6 i -

2.4.3.2 Chickamauga Group. 2.4-6 '

2.4.3.2.1 Unit A 2.4-7

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2.4.3.2.2 Unit B 2.4-8 2.4.3.2.3 Undifferentiated Chickamauga 2.4-8 2.4.3.3 Terrace and Alluvial Deposits 2.4-9 2.4.4 Structure 2.4-9 2.4.4.1 Site Structure 2.4-9 2.4.4.2 Nearby Tectonic Structures 2.4-10 2.4.4.2.1 Copper Creek Fault 2.4-11 2.4.4.2.2 Whiteoak Mountain Fault 2.4-12 I

2.4.5 Solution Activity 2.4-13 2.4.6 Physical Character of the Rocks 2.4-13 2.5 Hydrology 2.5-1 2.5.1 Surface Water 2.5-1

2. 5.1.1 Tributaries 2.5-2 2.5.1.2 Water Flow 2.5-3 2.5.1.3 Historical Low Flow 2.5-3 2.5.1.4 Reservoir Water Levels 2.5-4 2.5.1.5 Flood History 2.5-6 t,.

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Amendment XI January, 1982 TABLE OF CONTENTS Page 2.5.1.6 Water Temperatures 2.5-7 2 . 5 .1.7 River Velocity 2.5-8 2.5.1.8 Surface Water Quality 2.5-9 2.5.1.9 Plant Requirements 2.5-9 2.5.2 Groundwater 2.5-10 (

2.5.2.1 Regional Groundwater Hydrology 2.5-10 2.5.2.2 Site Groundwater Hydrology 2.5-12 2.5.2.3 Regional Groundwater Use 2.5-15 2.5.2." Local Water Levels 2.5-16 2.5.2.5 Movement of Goundwater 2.5-18 2.5.2.6 Effects of Plant Construction and Operation 2.5-19 on Groundwater System h 2.5.2.7 Groundwater Quality 2.5-19 2.5.2.8 Conclusions 2.5-20 2.6 Meteorology 2.6-1 2,6.1 Regional Climatology 2.6-1 2 . 6 .1.1 Maximum Rainfall 2.6-3 2.6.1.2 Severe Snow and Glaze Storms 2.6-3 2.6.1.3 Thunderstorms and hail 2.6-4 2.6.1.4 Tornadoes 2.6-4 2.6.1.5 Strong Winds and Hurricanes 2.6-5 2.6.1.6 Inversions and High Air Pollution Potential 2.6-6 Statistics y 2.6.2 Local Meteorology 2.6-7 2.6.2.1 Temperature 2.6-8 2.6.2.2 Winds 2.6-8 4

Amendment XI-January, 1982 TABLE OF CONTENTS Page 2.6.2.3 Humidity 2.6-9 11 2.6.2.4 Precipitation 2.6-10 2.6.2.5 Fog 2.6-10 l9 2.6.2.6 Wind and Stability Data 2.6-11 2.6.3 Potential Influence of the Plant and Its 2.6-13

Facilities on Local Meterology 2.6.4 Topographical Description 2.6-14 0

2.6.5 On-Site Meterological Monitoring Program 2.6-15 2.6.6 Short-Term (Accident) Diffusion Estimates 2.6-15 2.6.6.1 Calculations 2.6-16 7 g 2.6.6.1.1 Time Interval: 0 - 8 Hours 2.6-17

() 2.6.6.1.2 Time Interval: 16 Hours to 26 Days 2.6-18 2.6.7 Long-Term Average Diffusion Estimates 2.6-19 9 2.7 Ecology 2.7-1 2.7.1 Terrestrial Ecology 2.7-1 2.7.1.1 Land Use History 2.7-1 2.7.1.2 Soils 2.7-2 2.7.1.2.1 Clarksville Series 2.7-3 2.7.1.2.2. Talbott Series 2.7-3 2.7.1.2.3 Fullerton Series 2.7-3 2.7.1.2.4 Minor Soils 2.7-4 2 . 7 .1. 3 Vegetation 2.7-7 2.7.1.3.1 Plant Communities 2.7-8 2.7.1.3.2 Successional Trends 2.7-389

) 2.7.1.3.3 Unusual or Rare Community Types 2.7-38k 2.7.1.3.4 Plant Species of Special Importance 2.7-381 5

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Amendment XI January, 1982 TABLE OF CONTENTS Page 2 . 7 .1. 4 Wildlife 2.7-38n 2.7.1.4.1 Mammals 2.7-38o 2.7.1.4.2 Avifauna 2.7-3 8t 2.7.1.4.3 Herpetofauna 2.7-38dd 2.7.1.4.4 Invertebrates 2.7-38ee 2.7.1.4.5 Threatened or Endangered Fauna 2.7-38ff 9 2 .7 .1. 5 Important Domestic Animals 2.7-38hh 9 1

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J NIE!!D. IX OCT. 1981 b)

\.J TABLE OF CONTENTS Page 2.7.1.6 Food Webs- 2.7-38ii 2.7.1.6.1 Important Plant Species 2.7-38jj 2.7.1.6.2 Important Animal Species 2.7-38nn g 2.7.1.6.3 Food Web Relationships and Critical Species 2.7-38uu

2. 7.1. 7 Reconnaissance Survey, August 1980 2. 7-38w 2.7.2 Aquatic Ecology 2.7-39 2.7.2.1 Introduction 2.7-39 2.7.2.2 Previous Environmental Studies 2.7-41 2.7.2.3 Physical and Chemical Parameters 2.7-41 2.7.2.3.1 Locations of Sampling Stations 2.7-42 2.7.2.3.2 Bathymetry 2.7-42 2.7.2.3.3 River Height 2.7-43 2.7.2.3.4 Water Velocity and Current Direction 2.7-43 2.7.2.3.5 Temperature 2.7-44 2.7.2.3.6 Specific Conductivity Measurements 2.7-45

-O, 2.7.2.3.7 ' Solids 2.7-46 2.7.2.3.8 Turbidity and Color 2.7-47 2.7.2.3.9 Light Penetration 2.7-48 2.7.2.3.10 pH, Alkalinity and Hardness 2.7-48 6 2.7.2.3.11 Dissolved Oxygen 2.7-49 2.7.2.3.12 Biochemical Oxgen Demand, Chemical Oxygen 2.7-50 Demand and Total Organic Carbon 2.7.2.3.13 Nutrients 2.7-51 2.7.2.3.14 Heavy Metals 2.7-53 2.7.2.3.15 Organic Compounds 2.7-54 2.7.2.3.16 Pesticides 2.7-54 2.7.2.3.17 Other Water Analyses 2.7-54 2.7.2.3.18 Sediment (Particle Size and Total Volatile 2.7-56 Solid Content) 2.7.2.3.19 Sediment (Phosphate and Heavy Metal Content) 2.7-57 2.7.2.4 Ecological Parameters 2.7-58 2.7.2.4.1 Bacteria 2.7-58

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2.7.2.4.2 Phytoplankton 2.7-60

' \ 2.7.2.4.3 . Zooplankton 2.7-65 6

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AMEND. IX OCT. 1981

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TABLE OF CONTENTS Page 6.1.4.3.1 Baseline Studies 6.1-39 6.1.4.3.2 Method for Acquring Baseline Data - Site and 6.1-40 Environs 6.1.4.3.3 Methods for Acquiring Baseline Data - Trans- 6.1-41 mission Line Rights of Way 6.1.4.3.4 Construction Monitoring 6.1-41 6.1.5 Radiological Surveys 6.1-42 6.1.5.1 Preconstruction-Construction Phase Environmental 6.1-42a 9 Radiation Montoring Program

6. 2 - Applicant's Proposed Operational Monitoring 6.2-1 Program 6.2.1 Radiological Monitoring 6.2-1 6.2.1.1 Plant Effluent Monitoring Systems 6.2-1 6.2.1.1.1 Gaseous Effluents 6.2-1 6.2.1.1.2 Liquid Discharge Points 6.2-2a 4 5.2.1.2 Environmental Radiological Monitoring 6.2-2b 6.2.1.2.1 Preoperational-Operational Phase Environmental 6.2-3 Radiation Monitoring Program - General 6.2.1.2.2 Preoperational-Operational Phase Environmental 6.2-4 Radiation Monitoring Program - Atmospheric Monitoring 6.2.1.2.3 Preoperational-Operational Phase Environmental 6.2-5 Radiation Monitoring Program - Terrestrial Monitoring 6.2.1.2.4 Preoperational-Operational Phase Environmental 6.2-6 Radiation Monitoring Program - Reservoir Monitoring 6.2.1.2.5 Preoperational-Operational Phase Environmental 6.2-9 Radiation Monitoring Program - Groundwater 6.2.2 Chemical Effluent Monitoring 6.2-10 6.2.3 Thermal Effluent Monitoring 6.2-10 6.2.4 Meteorological Monitoring 6.2-11 6.2.5 Ecological Monitoring 6.2-12 6.2.5.1 Monitoring of Moisture Impacts 6.2-12 6.2.5.2 Monitoring of Icing Damage 6.2-13 16

Amendment XI January, 1982 TABLE OF CONTENTS Page 6.2.5.3 Monitoring of Drift Impact 6.2-14 6.2.5.4 Limnological Monitoring 6.2-15 6.2.5.5 Monitoring of Circulating Cooling Water Impacts 6.2-15 6.2.5.5.1 Distribution of Fish Response to Heated Water 6.2-16 6.2.5.5.2 Heated Discharges 6.2-16 6.2.5.5.3 Entrainment (Fish Eggs and Larvae) 6.2-16a 6.2.5.5.4 Impingement 6.2-17 6.3 Related Environmental Measurements and 6.3-1 Monitoring Programs 7.0 ENVIRONMENTAL EFFECTS OF ACCIDENTS 7.1 Plant Accidents 7.1-1 7.1.1 Computational Models 7.1-2 7.1.1.1 Meteorology 7.1-2 7.1.1.2 Dose Calculational Methodology 7.1-2 l 7.1.1.3 Sodium Fire Analysis 7.1-6 7.1.2 Accident Analyses 7.1-6 7.1.2.1 Accident 1.0 - Trivial Incidents 7.1-6 7.1.2.2 Accident 2.0 - Small Releases Outside 7.1-7 Containment 7.1.2.2.1 Accident 2.1 - Tritium Release Through SGAHRS 7.1-7 11 Vent Control Valves 7.1.2.2.2 Accident 2.2 - Condensate Storage Tank Leak 7.1-8 7.1.2.3 Accident 3.0 - Radwaste System Failures 7.1-9 7.1.2.3.1 Accident 3.1 - Liquid System Tank Malfunction 7.1-10 7.1.2.3.2 Accident 3.2 - Liquid System Tank Failure 7.1-11 7.1.2.3.3 Accident 3.3 - Rupture of RAPS Noble Gas Storage 7.1-12 11 h Vessel yll 16a

Amendment XI January, 1982 O(_/ TABLE OF CONTENTS Page 7.1.2.4 Accident 4.0 - Sodium Fires During Maintenance 7.1-14a 7.1.2.4.1 Accident 4.1 - Failure of Ex-Containment 7.1-15 Primary Sodium Drain Piping During Maintenance 7.1.2.4.2 Accident 4.2 - Failure of the Ex-Vessel Storage 7.1-18 Tank (EVST) Sodium Cooling System During Maintenance 7.1.2.5 Accident 5.0 - Fission Products to Primary and 7.1-20 Secondary Systems 7.1.2.5.1 Accident 5.1 - Off-Design Transients That Induce 7.1-21 Fuel Failures Above Those Expected 7.1.2.5.2 Accident 5.2 - Steam Generator Tube Rupture 7.1-24 7.1.2.6 Accident 6.0 - Refueling Accidents 7.1-25 7.1.2.6.1 Accident 6.1 - Spent Fuel Cladding Failure in the 7.1-27 EVTM - One Percent Noble Gas and Iodine Release

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7.1.2.6.2 Accident 6.2 - Spent Fuel Cladding Failure in 7.1-29 11 the EVTM - 100 Percent Noble Gas and Iodine Release 7.1.2.6.3 Accident 6.3 - Inadvertent Opening of a Floor 7.1-30 Valve While a Reactor Port Plug is Removed 7.1.2.7 Accident 7.0 - Spent Fuel Handling Accidents 7.1-31 7.1.2.7.1 Accident 7.1 - Spent Fuel Shipping Cask Drop 7.1-31 7.1.2.8 Accident 8.0 - Accident Initiation Events 7.1-33 Considered in Design Basis Evaluation in the Safety Analysis Report 7.1.2.8.1 Accident 8.1 - Primary Sodium In-Containment 7.1-33 Drain Tank Failure During Maintenance 7.1.2.8.2 Accident 8.2 - Large Primary Coolant Sodium 7.1-35 Spill During Operation 7.1.2.8.3 Accident 8.3 - Gross Failure of Ex-Containment 7.1-37 Primary Sodium Storage Tank

(') 7.1.2.8.4 Accident 8.4 - Rupture of the Ex-Vessel Storage Tank Sodium Cooling System During Operation 7.1-40 7.1.2.8.5 Accident 8.5 - Large Steam Line Break 7.1-42 17 1

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Amendment XI January, 1982 TABLE OF CONTENTS Page Summary of Plant Accident Doses 7.1-43 7.1.3 Other Accidents 7.2-1 7.2 Fires and Explosions 7.2-1 7.2.1 Sodium Fires - Non-Radiological Effects 7.2-3 7.2.1.1 7.2.2 Oil and Hazardous Material Spills 7.2-5 l 11 VOLUME III 8.0 ECONOMIC & SOCIAL EFFECTS OF PLANT CONSTRUCTION AND OPERATION 8.1-1 Economic & Social Conditions of Site Area 8.1-1 8.1 Social-Geographic Conditions of Area 8.1-1 8.1.1 Spatial Relationships Between Project Work 8.1-1 8.1.1.1 ,

Sites, Study Area Counties and Muncipalities O

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Amendment XI January, 1982 O)

( LIST OF TABLES Table No. & Title Page 2.6-1 Maximum Recorded Point Rainfall, Knoxville, 2.6-21 Airport (1899-1961) 2.6-2 Calculated Rainfall Over Various Time Periods 2.6-22 Recurrence Interval of 100 Years at the CRBRP g Site. Area 2 . 6-3 Monthly Distribution of Severe Weather - 2.6-23 Oak Ridge City Office 2.6-4 Monthly Climatological Temperature Data, 2'.6-24

, Oak Ridge Area Station, X-10 2.6-5 Annual Joint Frequency of Wind Direction and 2.6-25 Wind Speed for Stability Class A, CRBRP Permanent Meteorological Tower, 33-Foot Level, February 17, 1977 through February 16, 1978 11 2.6-6 Annual Joint Frequency of Wind Direction and 2.6-26 Wind Speed for Stability Class B, CRBRP Is Permanent Meteorological Tower, 33-Foot Level,

\~ February 17, 1977 through February 16, 1978 2.6-7 Annual Joint Frequency of Wind Direction and 2.6-27 Wind Speed for Stability Class C, CRBRP Permanent Meteorological Tower, 33-Foot Level, February 17, 1977 through February 16, 1978 2.6-8 Annual Joint Frequency of Wind Direction and 2.6-28 Wind Speed for Stability Class D, CRBRP Permanent Meteorological Tower, 33-Foot Level, February 17, 1977 through February 16, 1978 2.6-9 Annual Joint Frequency of Wind Direction and 2.6-29 Wind Speed for Stability Class E, CRBRP Permanent Meteorological Tower, 33-Foot Level, February 17, 1977 through February 16, 1978 2.6-10 Annual Joint Frequency of Wind Direction and 2.6-30 Wind Speed for Stability Class F, CRBRP Permanent Meteorological Tower, 33-Foot Level, February 17, 1977 through February 16, 1978 2.6-11 Annual Joint Frequency of Wind Direction and 2.6-31 Wind Speed for Stability Class G, CRBRP Permanent Meteorological Tower, 33-Foot Level,

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Anendment XI January, 1982 Page 2.6-12 Annual Joint Frequency of Wind Direction and 2.6-32 Wind Speed for All Stability Classes, CRBRP 8 Permanent Meteorological Tower, 33-Foot Level, g [ ))

February 17, 1977 through February 16, 1978 2.6-13 Annual Joint Frequency of Wind Direction and 2.6-33 Wind Speed for Stability Class A, CRBRP Permanent Meteorological Tower, 33-Foot Level, g ))

February 17, 1977 through February 16, 1978 ,

2.6-14 Annual Joint Frequency of Wind Direction and 2.6-34 Wind Speed for Stability Class B, CRBRP Permanent Meteorological Tower, 33-Poot Level, February 17, 1977 through February 16, 1978 9 l ))

2.6-15 Annual Joint Frequency of Wind Direction and 2.6-35 Wind Speed for Stability Class C, CRBRP Permanent Meteorological Tower, 33-Foot Level, g l ))

February 17, 1977 through February 16, 1978 2.6-16 Annual Joint Frequency of Wind Direction and 2.6-36 Wind Speed for Stability Class D, CRBRP Permanent Meteorological Tower, 33-Foot Level, February 17, 1977 through February 16, 1978 9'

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2.6-17 Annual Joint Frequency of Wind Direction and 2.6-37 Wind Speed for Stability Class E, CRBRP Permanent Meteorological Tower, 33-Foot Level, g l j)

February 17, 1977 through February 16, 1978 2.6-18 Annual Joint Frequency of Wind Direction and 2.6-38 Wind Speed for Stability Class F, CRBRP Permanent Meteorological Tower, 33-Foot Level, February 17, 1977 through February 16, 1978 lgl))

l 2.6-19 Annual Joint Frequency of Wind Direction and 2.6-39 Wind Speed for Stability Class G, CRBRP Permanent Meteorological Tower, 33-Foot Level, g(jj February 17, 1977 through February 16, 1978 2.6-20 Annual Joint Frequency of Wind Direction and 2.6-40 Wind Speed for All Stability Classes, CRBRP Permanent Meteorological Tower, 33-Foot Level, 9 lj)

February 17, 1977 through February 16, 1978 2.6-21 Monthly Wind Data 2.6-41 2.6-22 Monthly Average Relative Humidity Values for 2.6-42 Knoxville Airport 1961-1973 2.6-22A Monthly Average Relative Humidity Values for 2.6-43 the CRBRP Site, February 1977-February 1978

Amendment XI

. January, 1982

( Page 2.6-23 Frequency Distribution and Relative Humidities 2.6-44 According to Ambient Temperatures for Bull Run 8 Steam Plant-2.6-24 Precipitation Data, Oak Ridge Area Station, 2.6-45 X-10 2.6-24A Precipitation Data for the CRBRP Site, 2.6-46 9 February 1977-February 1978 '

2.6-25 Snow and Ice Pellet Data for Oak Ridge City 2.6-47 Of fice 1948 - October 1974 8 2.6-26 Monthly Mean Number of Heavy Fog _ Days for 2.6-48 Knoxville and Oak Ridge City Office 2.6-27 Fog Occurrence Data Listing Mean Number of 2.6-49 jg Days for January 1964 through October 1970 2.6-28 Number and Percent Occurrence by Months of 2.6-50 8 9 the Pasquill Stability Classes A-G Using the CRBRP Permanent Tower Data

() 2.6-29 Fiftieth Percentile x/O Values for Various Downwind Distances, 33-Ft Wind Speed and 2.6-51 9

, Direction: 200-ft to 33-Ft Delta T Data from February 17, 1977 through February 16, 1978 2.6-30 Annual Average x/Q's (in sec/m 3 ) at various 2.6-52 k9 Downwind Distances for Each Wind Sector 8 9

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Jnr Amendment XI January, 1982 LIST OF TABLES Table No. and Title Page 7.0 ENVIRONMENTAL EFFECTS OF ACCIDENTS 7.1-1 Atmospheric Dilution Factors - 50 Percent 7.1-45 Probability f/Q Values

{ ll 7.1-2 Average Energy Per Disintegration 7.1-46 7.1-3 Inhalation Dose Conversion Factor, F 7.1-48 i

7.1-4 Population Distributors and Wind Frequency for the 7.1-50 ENE and NNW Sectors 7.1-5 Summary of Potential Doses from Plant Accidents 7.1-51 Minimum Exclusion Distance - 2,200 Feet 7.1-6 Summary of Potential Doses From Plant Accidents 7.1-52 Downwind Distance - 0.6 Mile 7.1-7 Summary of Potential Doses From Plant Accidents 7.1-53 Downwind Distance - 1 Mile

) 7.1-8 Summary of Potential Doses From Plant Accidents 7.1-54 Downwind Distance - 2.5 Miles 7.1-9 Summary of Potential Doses From Plant Accidents 7.1-55 Downwind Distance - 4 Mile 7.1-10 Summary of Potential Doses From Plant Accidents 7.1-56 Downwind Distance - 7 Miles 7.1-11 Summary of Potential Doses From Plant Accidents 7.1-57 Downwind Distance - 21 Miles 7.1-12 Summary of Potential Doses From Plant Accidents 7.1-58 Downwind Distance - 50 Miles 7.1-13 Summary of Potential Whole Body Population Doses 7.1-59 From Plant Accidents 7.1-15 Rupture of the Noble Gas Storage Vessel 7.1-61 l

l l

O 58

Amendment XI January, 1982 LIST OF TABLES Table No. and Title Page y 7.1-17 Total Excess Cover Gas Leakage for Accident 5.1 7.1-63 7.1-18 Radioactive Content of Primary Sodium 7.1-64 Coolant 7.1-19 Radioactive Content of EVST Sodium 7.1-66 6 7.1-20 Fuel Assembly Noble Gas and Iodine 7.1-67 Inventories 8 Days After Shutdown 7.1-21 EVTM Gas Activity 8 Days After Shutdown 7.1-68 7.1-22 Initial Leakage Rate Through EVTM Seals to 7.1-69 RCB/RSB Atmosphere 8 Days After Shutdown 7.1-23 Reactor Cover Gas Inventory 30 Hours After 7.1-70 Shutdown 7.1-24 Fuel Assembly Inventory and Release Rates of Long- 7.1-71 Lived Volatile Fission-Gas Isotopes with Significant Activities for SFSC Drop from Maximum Possible Height 7.2-1 BOP Chemical Storage Tanks 7.2-6 7.2-2 Estimated Sodium Hydroxide Releases for 7.2-7lb Most Limiting Potential Fire Accidents 7.2-3 CRBRP Oil Storage Facilities 7.2-8 h1 VOLUME III 8.0 ECONOMIC AND SOCIAL EFFECTS OF PLANT CONSTRUCTION AND OPERATION 8.1-1 Counties and Municipalities Constituting 8.1-22 Area of Study 8.1-2 Approximate Road Mileages Between CRBRP 8.1-23 Site and Surrounding Municipalities 8.1-3 Actual and Projected Population for Area 8.1-24 6 10 Counties and Municipalities, 1980-2030 8.1-4 Age Distribution of Anderson, Knox, Loudon, and 8.1-25 Roane Counties; 1980 and 1990.

O 59

AMEND. IX OCT. 1981

- ~s LIST OF FIGURES '

i Figure No. and Title Page 2.3-1 Archaeological and Historical Sites 2.3-13 >

8

2.3-2 Planview of Excavations, Mound Construction 2.3-14 Stages and Adjacent Midden Deposits

2.4-1 Test Boring Locations at CRBRP Site 2.4-21 2.4-2 Plan of CRBRP Main Plant Structures and Category 1 2.4-22 9 m Cooling Tower 2.4-3 Regional Physiographic Map of CRBRP Sita 2.4-23 2.4-4 Regional Tectonic Map of CRBRP Site >

2.4-24' 2.4-5 Regional Geological Map of CRBRP Site 2.4-25 2.4-6 Geologic and Physiographic Map of the CRBRP Site 2.4-26' .

2.4-7a Stratigraphic Section at Site of CRBRP Project 2.4-27 4

2.4-7b Stratigraphic Section at Site of CRBRP Project - Key 2.4-28 Section Through CRBRP Nuclear Island and Found3 tion 2.4-29

[\--)/ 2.4-8 Strata 2.4-9 Area S.,ructure Map in the CRBRP Vicinity 2.4-30 2.4-10 Area Geologic Cross Section, CRBRP Project 2.4-31 2.5-1 Topography of Clinch River Site 2.5-61 2.5-2 Norris, Melton Hill, Fort Loudoun, Tellico and Watts 2.5-62 l 9 Bar Dams 2.5-3 Flow Duration Curve 2.5-63 2.5-4 Downstream Profile of the Clinch River 2.5-64 2.5-5 Bathymetric Chart of Clinch River in the Vicinity 2.5-65 of the Intake 2.5-6 Bathymetric Chart of Clinch River in the Vicinity 2.5-66 of the Discharge 2.5-7 Cross-Sectional Profile of Clinch River in the 2.5-67 Vicinity of the Intake '

2.5-8 Cross-Sectional Profile of Clinch River in the 2.5-68 Os Vicinity of the Discharge l

67

Amendment XI January, 1982 LIST OF FIGURES Figure No. & Title Page 2.5-9 Normal Operating Level for Watts Bar 2.5-69 Peservoir 2.5-10 Velocity Response at CRM 17 to Postulated 2.5-70 Turbine Operations ORNL Steam Monitoring Locations 2.5-70a 9 2.5-10a 2.5-11 Westewater Discharges, Clinch River Watershed 2.5-71 2.5-12 Locations of Wells and Springs Within 2-Mile 2.5-72 Radius of CRBRP 2.5-13 Locatien of Public and Industrial Groundwater 2.5-73 Supplies 2.5-14 Location of Observat. ion Wells 2.5-74 2.5-15 Site Groundwater Contours, December 24, 1973 2.5-75 2.~5-16 Site Groundwater Contours, January 2, 1974 2.5-76 2.5-17 Site Geologic Profile 2.5-77 2.5-18 Site Geologic Profile 2.5-78 2.5-19 . Site Geologic Profile 2.5-79 2.5-80 9 2.5-20 Piezometer Location Plan 2.6-1 Locations of Weather Stations Near Site 2.6-53 2.6-2 Raw Count Data on Tornado Occurrence for 2.6-54 !

18 Counties Near Site, 1916-1972 2.6-3 Total Number of Forecast Days of High 2.6-55 Meteorological Potential for High Air Pollution in a 5-Year Period 2.6-4 Ar.nual Wind Rose f or the 33-Foot Level 2.6-56 from CRBRP Permanent Meteorological Tower g h1 Data for February 17, 1977 through February 16, 1978 2.6-5 Winter Wind Rose for the 33-Foot Level from 2.6-57 CRBRP Permanent Meteorological Tower Data l11 2.6-6 Spring Wind Rose for the 33-Foot Level from 2.6-58 CRBRP Permanent Meteorological Tower Data i l 68

Amendment XI January, 1982 O Page 2.6-7 Summer Wind Rose for the 33-Foot Level from 2.6-59 CRBRP Permanent Meteorological Tower Data 9 l ])

2.6-8 Fall Wind Rose for the 33-Foot Level from 2.6-60 .

CRBRP Permanent Meteorological Tower Data l11 2.6-9 Annual Wind Rose for the 200-Foot Level from 2.6-61 the CRBRP Permanent Meteorological Tower Data l 11 for February 17, 1977 through February 16, 1978 Winter Wind Rose for the 200-Foot Level from 2.6-62

?

2.6-10 CRBRP Permanent Meteorological Tower Data !Il 2.6-11 Epring W,ind Rose for the 200-Foot Level from 2.6-63 ij)

CRBRP Permanent Meteorological Tower Data 1

- Summer Wind Rose for the 200-Foot Level from 2.6-64 i 2.6-12 ^ ~CRBRP Permanent Meteorological Tower Data j l jj i

2.6-13 Fall Wind Rose for the 200-Foot Level from 2.6-65 ! jj CRBRP Permanent Meteorological Tower Data 1

() 2.6-14 2.6-15 Topography Surrounding Clinch River Site Site Topographic Map 2.6-66 2.6-67 2.6-16 Topographic Profile Cross Sections From Site 2.6-68

-69 2.6-17 Topographical Cross Section Including 2.6-70 Meteorological Tower and Center of Containment Building VOLUME II 2.7-1 Soil Types of the Clinch River Site 2.7-501 2.7-2 Soil Erodibility Interpretations, CRBRP Site 2.7-502 2.7-3 Heavy Equipment Impact Potential 2.7-503 Interpretations, CRBhP Site 2.7-4 Seedling Mortality Soil Interpretations, 2.7-504 CRBRP Site 2.7-5 Natural Productivity Soil Interpretations, 2.7-505 CRBRP Site 2.7-6 Site Study Areas and Overstory Vegetation 2.7-506

,/~S V 2.7-7 Vegetation Sampling Plots for the Clinch 2.7-510 River Site 69

AMEND. !X OCT. 1981 LIST OF FIGURES Figure No. and Title Page 2.7-A Small Mammal Sampling Locations on the Clinch River 2.7-Slla Site 2.7-B Locations of Bird Observation Transects on the Clinch 2.7-Silb River Site 2.7-C Sector Designations for 1, 2, 3, 4, 5 and 10 Miles 2.7-Silc from the CRBRP Site 2.7-0 Generalized Food Web for the Clinch River Site 2.7-511d 2.7-8 Distribution of Cimicifuaa rubifolia 2.7-511 2.7-9 Bathymetric Profile of the Clinch River Near the 2.7-512 Proposed Location of the Barge Unloading Area 2.8-1 Oak Ridge Facilities as 100 Kilometer Center 2.8-81 2.8-2 Air, Vegetation and Soil Sampling Locations 2.8-82 2.8-3 Remote Air Monitoring Location 2.8-83 2.8-4 Clinch River and Tributaries in the Oak Ridge Area 2.8-84

' 9 2.8-5 Variations in Contents of Cs-137, Co-60 and Ru-106 2.8-85 ,

With Depth in Hole 6 CRM 7.5, 1969 lg 2.8-86 l 2.8-6 Longitudinal Distribution of Radionuclides in Bottom Sediment of the Clinch River 1969 2.8-7 Radionuclide Concentrations in Bottom Muds, Clinch 2.8-87 i and Tennessee Rivers 1969 1 2.8-8 Stream Monitoring Locations 2.8-88 !

2.8-9 Curies Discharged Over White Oak Dam 2.8-89 l 2.8-10 Percentage MPC Levels in the Clinch River 2.8-90 1

O 70

Amendment XI January, 1982 1

2.6 METEOROLOGY 2.6.1 REG 10NAL CLIMATOLOGY Meteorological data from the Oak Ridge Area Station X-10,II'2) located 4.5 miles northeast of the Clinch River Breeder Reactor Plant (CPERP) Site, were used to characterize the Meteorology / Climatology of the region including the Site. Oak Ridge Area Station X-10 was a first order Weather Bureau Station from 1944 to 1964 (First order Weather Bureau Stations are usually located at major airports and are manned 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months a day. These stations record hourly visual observations as well as wind, temperature, dewpoint, etc. Second order

, stations only record and/or trane.fi data on physical phenomena.) From 1964 to 1972 only wind, temperature, dewpoint and differential temperature were recorded. The station was discontinued in December 1972. Other lg

climatological data sources used in characterizing regional climatology are the Knoxville Airport Weather Station,I3) located about 20 miles east of the Site, and the Weather Bureau's Oak Ridge City Office,I4) located 10 miles northeast of the Site. Locations of these weather stations are shown in Figure 2.6-1. General information on the climate of the State is available from the U.S. Weather Bureau I5) . Other sources of specialized data are referenced as they appear in this section.

This Site is located in Roane County, Tennessee in a broad valley between the Cumberland Mountains to the northwest and the Great Smoky Mountains to the southeast. Topography of the Site is characterized by subparallel ridges with intervening valleys, as discussed in Section 2.4. Elevations of the ridge crests range between 900 and 1,200 feet. Site elevation is approximately 820 Il feet.

Topography of the Site is characterized by a series of parallel ridges j separated by long, narrow valleys extending in a northeast-couthwest direction. The Site lies along a rolling flank of one of these ridges.

Differences in elevation influence the pat %rn of the changes in climate along [ Il a NE-SW axis; stations at a similar el tion have similar annual mean temperatures and precipitation normals .

2.6-1

Amendment XI Janua ry,1982 Prevelling winds in the region reflect the channeling of air flow caused by the orientation of valleys and ridges of the southern Appalachians; winds are generally northeasterly or southwesterly. Mean annual wind speeds are low compared to other areas of Tennessee and the United States (6) . The mean 8 speed during the 16-year period of record is 4.4 miles per hour at the Oak Ridge City Office (6) ,

The region has a mild climate, classified Caf by Koppen; it is humid, has a mean temperature for the warmest month of the year in excess of 71.6 degrees F and has no distinct dry seasonIII. March is normally the wettest month and October the driest. Precipitation is heaviest from December through March when cyclonic activity is high and in July and August when convective showers occur. Maximum recorded rainfall in a 24-hour period was 7.75 inches; this occurred at Oak Ridge Area Station X-10 in September 1944(II. Temperatures lII about 90 degrees F occur on a total of 32 to 46 days (5) in an average year.

Zero and sub-zero temperatures at the X-10 Station were observed during the months of December, January or February in fewer than half the years from 1945 through 1964. Synoptic (regional) scale weather systems move through eastern Tennessee with irregularity. These storm systems are most frequent during December end January and cause a maximum monthly number of cloudy days and extensive precipitation. Summer season storm systems are usually weaker and tend to pass to the north, leaving eastern Tennessee with sunshine interspersed with thunderstorm activity. Between 50 and 60 thunderstorm days occur per year, with a peak number of storms occuring in July (5) . About nine thunderstorms per month occur during the period of May through August. The region, including the Site, is subject to a small probability of tornado occurrence.

Humidity varies with wind direction, generally being lowest with northeast winds and highest with southeasterly to southwesterly winds. Relative 11 humidity averages lowest in the afternoons and highest at night. Average annual humidity in Tennessee is near 70 percent (6) . This is about average for most of the United States east of the 95th merldlan. ))

O 2.6-2

Amendment XI O January,1982 2.6.1.1 MAXIMUM RAINFALL Maximum recorded point rainfall for the Knoxville Airport for intervals of 5 minutes to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is listed in Table 2.6-I I0) . Maximum monthly and annual precipitation recorded at the Oak Ridge City Of fice was 19.27 inches in July 1967 and 76.33 inches in 1973, respectively I4) . Monthly and annual extremes of 14.11 inches in July 1967 and 66.20 inches in 1950, respectively, were recorded at Oak Ridge Area Station X-10(2) Maximum measured annual rainfall at Knoxville was 61.49 inches In 1957(3) Calculated rainfall for the Site l area for time periods of 0.5, 1, 2, 3, 6, 12, and 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for a recurrence interval of 100 years is given in Table 2.6-2 I9) .

2.6.1.2 SEVERE SNOW AND GLAZE STORMS Winter storms which produce a snowfall in excess of one Inch or glaze are uncommon in eastern Tennessee. The area can expect about three significant snowfalls per year (one or mor nches)(5) . It is unusual to have snow cover for more than a week at a time . Records over a period of 26 years show that, in March 1960, a single storm maximum of 21 inches accumulated, with 12 inches in a single day. Normal snowf all for March is 1.5 inches I4) . Highest average normal monthly total is 3.2 inches, occuring in January.

Glaze occurred from three to six times per year during a 28-year survey period ending in 1953(10) . Freezing rain can occur during the normally colder months of the year when rain falls through a very shallow layer of cold air from an overlying warm layer. Rain then freezes on contact with the ground or other objects to form gIaze. December through ear 1y March Is the period wIth the highest frequency of glaze storms. Based on limited periods of data l8 collection, significant glaze storms producing a glaze ice thickness of 0.25 inch or more on wires occur in eastern Tennessee on an average of one storm every two years (10) . Occurrences for glaze storms applicable to the area including the Site are as follows(10)

Thickness of 0.25 inch or greater Once every two years Thickness of 0.50 Inch or greater Once every five years Thickness of 0.75 inch or greater Once every ten years 2.6-3

. _ . - . . ~ - . - . - ,

Amendment XI January, 1982 2.6.1.3 THUNDERSTORMS AND Hall ,

Thunderstorms occur on an average of 54 days per year (4) . The month of July usually has the most. An average of about nine thunderstorm days per month occur throughout the season from May through August. As can be sean in Table 2.6-3, the months of October through January have the f ewest thunderstorms.

Hall is not too frequent but it does occur with stronger thunderstorms. On an ill index of potential hall damage to residential property, calculated for each

)

area formed by one degree of latitude and one degree of longitude, the Site is in a region of low potential loss due to hall Ill'. Maximum values of the index occur in northwest Kansas where the index is 50. The index in eastern Tennessee is about 5. Therefore, on a geographical basis, the Site is l11 situated in a region where hall is not a significant factor.

2.6.1.4 TORNADOES The Site is located in an area infrequently affected by tornadoes (12,13) .

For l11 the purpose of comparison, Tennessee ranked 25th among all states in the number of tornadoes f r >m 1955 to 1967(14) . Divided along the 86th Meridian, the western half of the entire state has reported observing three times as l11 many tornadoes as were observed in the eastern half, which includes the f))

Site Cl3) . The Oak Ridge-Clinch River area has one of the lowest probabilities of tornado occurrence in the entire State (14,15) ,

Tornado frequencies calculated by Thom Il0} for each one-degree square of Iatitude and IongItude for the perlod 1953 to 1962 show the Site to be situated in a one-degree square with an annual frequency of 0.5. Probability that a tornado will strike any point in a particular one-degree square, such as the Site, is calculated as 3.65 x 10-5 per year. Recurrence Interval is 8 one over the probability, which is once in 27,400 years. Raw count data on tornado occurrence for those counties near the Site for the period 1916 to 1972 are presented in Figure 2.6-2(12,17) . Roane County is the only one of several counties within the one-degree square used for the calculation of the tornade probability. Roane County itself has not recorded a tornado in the 57-year period of 1916 to 1972.

2.6-4

p

() Amendment XI January, 1982 2.6.1.5 STRONG WINDS AND HURRICANES Thom(18) analyzed data for all first-order weather stations in the U.S. on fastest-mile wind speed at 30 feet about ground level for recurrence intervals as Indicated below for eastern Tennessee. Fastest mile is the wind speed in miles per hour based on the shortest recorded time interval in which a " mile" 11 of wind passes a stationary point. Instantaneous gusts are thus smoothed out.

A partial record of extreme wind data is avaIlable for the Oak Ridge area.

The peak gust recorded at the Oak Ridge City Office during a 17-year period was about 59 miles per hour I4) . Fastest mile reported for the Knoxville Airport for a 31-year period was 73 miles per hour (3) . A 33-year record at l8 Chattanooga, Tennessee, shows a fastest mile of 82 miles per. hour (19) .

CALCULATED FASTEST MILES DATA VS. RECURRENCE INTERVAL IIO) p EASTERN TENNESSEE

.y Recurrence Interval (vears) Fastest MIIe (moh) 10 64 25 73 50 76 100 89 Hurricanes lose force rapidly when cut off from their source of moisture. l jj Consequently, these storms are in the post hurricane stage with diminished I

winds by the time they reach the Site area, in the past 70 years, the remnants of nine hurricanes, classified as devastating when crossing the coastline of the U.S., have crossed Tennessee (20) . Remnants of the hurricane of August 1940 caused flooding in eastern Tennessee (20) . Visible damage associated with tropical storms occurs about once every 25 years in eastern Tennessee (5) ,

O 2.6-5

Amendment XI January, 1982 2.6.1.6 INVERSIONS AND HIGH AIR POLLUTION POTENTIAL STATISTICS Hos l er(21 ) and Holzworth I22) have analyzed weather records from many U.S.

stations with the objective of characterizing regional atmospheric dispersion 8

potential. However, this data cannot be considered as directly site specific. j11 The seasonal frequencies of Inversions based below 500 feet for the region including the Site area, in percent of total hours in a year, are shown in HosierI2I' as follows:

Winter - 42% Summer - 45% Annual - 41%

Spring - 32% Fat 1 - 45%

Since eastern Tennessee is in a hilly region dominated by anti-cyclonic circulations (6) inversion frequencies are closely related to the diurnal cycle. The diurnal influence is strongest in summer and fall. [1]

Holzworth's data (22) provides an estimate of the regional average depth of vigorous vertical mixing and provides an Indication of the regional vertical 8

depth of atmosphere available for mixing and dispersion of effluents. In the region in which the Site is included, the mean maximum daily mixing depths range from about 1,475 feet in January to 5,250 feet in July. In April and October, they are about 4,100 and 3,120 feet, respectively. When mixing l11 depths are shallow, pollution potential is highest.

Holzworth(23) has presented statistics for the period 1960 to 1964 on the frequency of combinations of meteorological conditions that give rise to unfavorable dispersion characteristics as indicated by low mixing depths, light winds and no precipitation. An air pollution episode is forecast to occur in an area whenever the mixing depth is less than 1,500 m (approximately 11 5,000 feet), the mean wind speed through the mixing height is less than 4 m/sec (approximately 9 mph), no precipitation is expected to occur and these or worse conditions persist for two days. Figure 2.6-3 is a representation of the total number of forecast-days of high meteorological potential for high air pollution in five-year period. The Site is in an area where 30 to 35 days 2.6-6

Amendment XI January, 1982 of high air pollution potential treteorology occurred in a five-year period.

These values average out to six or seven forecast days per year of high air pollution potential meteorology which are high for the eastern United States but low compared to a large area of the western United States.

Other combinations of mixing height and wind speed without precipitation are summarized by Holzworth(23) . The most restrictive combination consists of a mixing height less than 1,640 feet and winds less than 4.5 mph. No episodes satisfying these criteria occurred in the area during the five year period.

For mixing heights less than 3,280 feet and winds less than 9 mph, there were seven episodes in the five-year period lasting two days or more. Holzworth's data (23 ) indicate that, in general, eastern Tennessee is in a region of l8 unfavorable dispersion with respect to the frequency of occurrence of high air pollution potential meteorology. The greater than normal expectancy of occurrence of high air poilution meteorology is not of great importance to the Site in terms of calculating site boundary doses. Since any release of g

T radioactivity would take place at ground level, the effects of lower mixing heights on such a release are insignificant. High x/Q values for ground level release are associated with stable atmosp e ic conditions rather than with low mixing heights.

Analyses of doses resulting from postulated releases are also governed by assumptions that stable air is present, in stable air, mixing height does not play a role in the calculations. Therefore, the effects of high air pollution potential meteorology at the CRBRP Site is not a major concern.

2.6.2 LOCAL METEOROLOGY The CRBRP site meteorological facilities, the Oak Ridge Area Station X-10, the 11 Oak Ridge City Of fice, and the Knoxville Airport (the latter three being the closest NOAA weather bureau stations to the Site) have been used as the primary sources of local meteorological data (1,2,3,4) with a few exceptions noted in the following discussion. Climatological statistics for these l 11 stations are believed to be representative of the Site area. Supplementary U climatclogical data were obtained from TVA on relative humidities and fog 2.6-7

Amendn2nt XI Januaryc 1982 frequencies I24) . Atmospheric dispersion characteristics for the Site have been estimated from hourly data collected at the CRBRP permanent 110-meter g meteorological tower during the period February 17, 1977 through February 16, 9 . 11 1978. i 2.6.2.1 TEMPERATURE Temperature data for the Oak Ridge Area Station X-10 show that a record high temperature of 103 degrees F occurred in July 1952 and in September 1954; a record low temperature of -8 degrees F occurred in January 1963(I) . For comparison purposes the temperature extremes in the Knoxville vicinity were 104 degrees F on July 12, 1930 for the highest and -16 degrees F in January 1884 for the iowest(3) . The annuaI average dal1y ti;aximum is 69.4 degrees F and the minimum is 47.6 degrees F, with an average of the monthly mean temperature of 58.5 degrees F. Monthly climatological temperature data for Area Station X-10 and the annual trean temperattire - data and extremes of temperature for the Oak Ridge City Of fice and Knoxville vicinity for comparison purposes are presented in Table 2.6-4. It is apparent by inspection of these data that the three sites are quite similar with respect to temperature except for the extreme low of -16 degrees F recorded in the Knoxville vicinity. This record low is a part of a much longer observation period spanning 100 years and includes more opportunities to observe extremes.

2.6.2.2 WINDS Data from the permanent meteorological tower have been used to characterize wind conditions at the Site. The period of record is February 17, 1977 8 11 O

through February 16, 1978. These data have been used to construct joint frequency distributions of wind speed and direction by stability class, 11 presented in Tables 2.6-5 to 2.6-20.

From an examination of all available data collected at or near the Site, this 11 8

one-year summary of on-site wind data appears reasonably representative of everage conditions in an average year. The CRBRP meteorological information is the best data based for characterizing dispersion conditions because it is site specific and because the measuring height conforms to NRC Regulatory Guide 1.23 and the starting threshold used to define calms (0.74 miles per 9 11 hour1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months for the wind direction sensor) is much improved over that at Station X-10.

2.6-8

Amendment XI January, 1982

/^T b Analysis of the one-year summary of on-site wind data shows an average annual wind speed of 3.5 mph at the 33-foot level and 5.6 mph at the 200-foot level. 8 11 The wind is most frequent from the west northwest at the 33-foot level and 9 from the west southwest at the 200-foot level. Analysis of the Oak Ridge Area Station X-10 data, where the wind sensor is mounted at a height of 102 feet, shows an average annual wind speed of 4.9 mph and a prevailing wind direction of south to southwest. The Oak Ridge City Office shows a prevailing wind from the southwest with a mean speed of 4.4 mph which is consistent with the other wind data discussed above. Knoxville Airport data show that the prevailing O wind is from the northeast with a mean hourly speed of 7.4 mph. A summary of jj these data is provided in Table 2.6-21.

2.6.2.3 HUMIDITY ,

A 13-year record of relative humidity by month is available for four selected observation times during the day for Knoxville Airport. A four-year record of relative humidity and temperature data from the Bull Run Steam Plant was used to generate frequency distribution of relative humidity according to ambient temperature. The Bull Run data are more representative of the CRBRP-site than the Knoxville data since the Bull Run sensor is located in a river valley similar to the Site. The river valley will affect wind flow and provide a moisture source that is reflected in the relative humidity data. Regardless of the location, the relative humidity varies inversely with temperature if the water content of the air is constant. Relative humidity is lowest at the time of maximum temperature and highest at the time of minimum temperature.

Low relative humidities are expected to occur in mid-afternoon near the time of maximum temperature and high relative humidities are expected to occur in l

early morning at the time of minimum temperature. Monthly average relative 8

humidity data for the Knoxville Airport are summarized in Table 2.6-22(3) .

i f

On-site data from the preconstruction monitoring program (see Section 6.1.3) 9 l

Is available. Monthly average relative humidity from the CRBRP site is 11 l

presented in Table 2.6-22A. These values are similar to those from the Knoxville Airport.

( The summary of the four-year Bull Run data is in Table 2.6-23. l))

l

! 2.6-9 l

Amendment XI January, 1982 2.6.2.4 PRECIPITATION Average annual precipitation is 51.52 Inches at the Oak Ridge Area Station X-10 based upon 21 years of recordIII. Winter is the wettest season when 31 percent of the annual precipitation is recorded. February and March are the cettest months when about 5.4 inches of precipitation is normal. October is the driest month, averaging only 2.82 inches. Maximum monthly rainfall and observed maximum 24-hour rainfall (12.84 and 7.75 inches, respectively) lll occurred in September (Table 2.6-24)III. Monthly precipitation from the CRBRP pre-construction monitoring program is presented in Table 2.6-24A. These values are similar to those presented for the Knoxville Airport.

Snow and Ice pellet data for the Oak Ridge City Office are summarized in Table 2.6-25(4) Data listed in the table show that the annual snowfall averages l11 about 10 inches. Maximum snowfall in the 26 year period was 41.4 inches, more than four times the annual mean. Heavy snows, when more than six inches are recorded in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , have occurred in each month from November through March (# .

2.6.2.5 FOG Incidence of heavy fog (1/4 mile or less visibility) varies greatly around Tennessee (5) . Typical annual values include 31 days at Knoxville I3) , 34 days l))

at Oak Ridge City Office (4) and 36 days at ChattanoogaIl9) .

Five months of the year have an average fog frequency of three days or more at all three stations. At Oak Ridge, October has the highest fog incidence with an average of eight occurrences. Monthly mean number of heavy fog days for Knoxville and Oak Ridge are shown in Table 2.6-26. Supplementary fog data 8 ill recorded at two sites along the Melton Hill Lake, upstream from the CRBRP site i and shown In Table 2.6-27, show that fogs which restrict the visibility to l))

1,100 yards or less are very common for observation points near the river or lake (24) . The data reported here are not completely comparable to that recorded at Knoxville or the Oak Ridge City Office because of the difference in definitions, but it does serve to point out that fogs are very common in 2.6-10

Amendment XI January, 1982 the region, including the Site. Fogs which restrict the visibility to 1,100

%) yards or less were obscrved, on the average, 91 days per year at the Buti Run Creek site (about 15 miles northeast of the CRBRP site) and 119 days per year 8 at the Melton Hill Dam site (about 4.5 miles east of the CRBRP site) for the period January 1964 to October 1970.

Fog which restricted visibility to less than 550 yards was recorded at the Melton Hill Dam site on an average of 106 days per year I24) . This values is l8 about three times that recorded at Oak Ridge.

2.6.2.6 WIND AND STABILITY DATA Source of this Information for developing a diffusion climatology to represent the Site is a one-year record of wind and temperature measurements made on a l))

361-foot tower at the CRBRP site. The year of record covers the period February 17, 1977 through February 16, 1978. The joint recovery rate for wind 9

and stability data (33- to 200-foot temperature dif ferences) is 97 percent for the 33-foot wind level end 97 percent for the 200-foot wind level. fj) h)

The method of sorting thu observations into the Pasquill Stability Classes is based on the temperature gradient scheme of NRC Regulatory Guide 1.23 which associates a Pasquill (' lass with a discrete range of temperature dif ference values for a 321-foot vertical Interval. The values obtained from the Site temperature measurements at 33 feet and 200 feet (167-foot interval) were converted to corresponding values for the larger interval of 321 feet. fg Annual wind records are summarized in Table 2.6-5 through 2.6-12 for the )j 33-foot level aboveground and in Tables 2.6-13 through 2.6-20 for the 200-foot level aboveground. These tables present the joint percentage frequency distribution of wind speed and direction for the seven Pasquill Stability Classes, A through G, and for all observations. Annual and seasonal wind roses are shown for the 33-foot level in Figures 2.6-4 through 2.6-8 and for the 200-foot level in Figures 2.6-9 through 2.6-13.

Annual, winter, spring, summer and fall wind roses for the 33-foot level show i

A)

( the tendency for the wind to align with the general west-northwest to l8 l9 l11 l

2.6-11

Amendment XI January, 1982 cast-southeast orientation of the portio:, of the Clinch River valley where the Site is located. At the 200-foot level, the tendency is toward alignment with 8 9 Il the approximately southwest to northeast orientation of the ridge in the area.

Most frequent wind dire:tions f or annual wind roses are west-northwest at 33 feet and west-southwest at 200 feet. The winter season wind roses, for both levels, show the influence of winter storms and passage of cold frontal ,

I systems by the increased percentages of winds from the west-northwest sector. 11 The summar and fall wind roses reflect meteorological conditions with a high frequency of occurrence of light winds. This is consistent with persistence of high pressure over or slightly to the north of the Site area. Pressure I6} support this patterns published in the Climatic Atlas of the United States conclusion.

The 33-foot winds for the annual period are from the west-southwest plus or i 8

minus one 22.5 degree sector 25.7 percent of the time and from the 9 11 cest-northwest plus and minus one 22.5 degree sector 25.1 percent of the time on an annual basis. The percentage of south-southeast winds increases slightly during the spring months. During the fall season the percentage of winds is very simliar (within two percentage points) to the annual wind rose.

The 33-foot modal wind speed group is 0.8 to 3 mph for the year, as can be seen in Table 2.6-12. Calms are few !n all seasons of the year. The annual ll 8

percent occurrence of calm is 3.19 percent at the 33-foot level and 0.47 percent at the 200-foot level.

The distribution of the seven Pasquill Stability Classes on a monthly basis is 11 summarized in Table 2.6-28. Adverse dispersion categories, Stability Classes l9 F and G, contribute about 85 percent of the weight in the calculation of atmospheric dilution factors. Type G stability is a minimum in the month of 8 11 January with a frequency of occurrence of about five percent. Type G is a maximum in the month of March, with a frequency of about 28 percent.

Type F stabilit$ is a minimum in January with a frequency of about six 8 11 percent. Type F stability is a maximum in the month of July with a frequency of about 25 percent and August and September are close behind with frequencies of about 24 percent in these months. At the other end of the atmospheric 2.6-12 j

Amendment XI January, 1982 stability spectrum, the combined occurrence of types A and B stabilities 8 11 occurs most frequently in the month of June with a frequency of about 6 percent. September shows the fewest occurrences of type A stability.

On an annual basis, Pasquill's type D (neutral stability) class is most common. Type D stability is a maximum in the month of January when it occurs 50 with a frequency of about 49 percent. Small frequencies of occurrence cf l9 stability types B and C are largely a product of the classification scheme used to define the range of temperature difference values that define these 111 classes, fil 2.6.3 POTENTI AL INFLUENCE OF THE PLANT AND ITS FACILITIES ON LOCAL METEOROLOGY Some influence on local meteorology will be exerted by the plant itself.

Because the plant itself will be cleared of trees, leveled, bladed, graded and black topped, it will change the albedo (reflective power) of the earth in this area and produce a small local heat Island which would be discernable with a proper set of micrometeorological measuring systems. The Increase in temper'ture would be similar to that found by Norwine(25) , which was two 8 11 degrees F for a shopping center.

The shape of the buildings erected on the plant site will create aerodynamically disturbed air flow which in turn will alter the distribution pattern and diffusion rates of windborne contaminants on the leeward side of the buildings. This effect is discussed in Section 2.6.6.1.1.

It is planned to dissipate waste heat carried by recirculated cooling weter in cooling towers. Evaporation of water into the atmosphere will form a visible vapor plume if the atmosphere is either very humid, or very cold and moderately humid. The vapor plume will alter, to a small degree, the amount of sunshine received in the smalI areas most frequently in the shadow formed by the plume. On rare occasions small cumulus clouds could form above or remote from the tower, depending on atmospheric temperature and water vapor conditions in the first few thousand feet above the cooling tower. The plume may dif f use to ground level and f orm f og, and in f reezing temperatures cause rime ice on vertical structures and road systems. These environmental impacts are discussed in Section 5.1.

2.6-13

Amendment XI January c 1982 2.6.4 TOP 0 GRAPHICAL DESCRIPTi(N The Site is on a peninsula approximately between river miles 15 and 18 on the Clinch River. This region is characterized by a series of parallel ridges oriented approximately along a northeast-southwest axis. The Site lies along l ))

a rolling flank of one of these ridges which slopes gradually toward the Clinch River. The terrain is further complicated by the generally east-southeast to west-northwest orientation of the river valley, as it cuts through the ridges for about 8 air miles. The Site is located approximately 11 midway along this stretch of the river. Normal reservoir pool elevation is 740 feet. Mean elevation of the Site is 862 feet MSL.

Figures 2.6-14 and 2.6-15 are topographic maps showing the area surrounding the Site. Topographic profile cross-sections in each of the eight cardinal compass directior.s radiating from the Site are shown in Figure 2.6-16. A topographical profile cross-section indicating the meteorological tower location, sensor heights and center of containment building with respect to the current topography is given in Figure 2.6-17. Terrain to the south of the Site, approximately 3,700 feet beyond Watts Bar Lake, rises abruptly to a height of about 240 feet above plant grade, which is 815 feet. This obstacle to air flow will influence the dispersion rate at this distance. The expected effect is discussed below. Hills or ridges of similar height are found within two miles of the Site practically every direction except towards the northwest.

The highest point within a radius of five miles of the Site is Melton Hill, elevation 1,356 feet MSL, about 4.75 miles east-northeast of the plant.

Lowest points within a radius of five miles of the Site are along the margins of Watts Bar Lake, the surface of which averages approximately 740 feet MSL. l))

It is anticipated that the Irregular terrain will have a significant effect on o j I

dispersion rates. In stable air with light winds, pockets of stagnation may develop at the base of sharply rising hilis or bluffs or near the mouths of )) l nearby creeks. This could cause r,hort-term Increases in pollutant concentrat!on levels. However, due to the increase in wind meander under 2.6-14 a

. Amendment XI January, 1982 O light winds, it has been shown that the plume effluent could spread over an angle of 180 degrees or more(26) ,

8 11 Slopes which f ace the southeast through southwest directions present a surf ace which is more nearly normal to the incidence of solar radiation. This effect will enhance and improve dispersion rates for any air contaminants approaching the slope due to the production of thermally Induced vertical air motions.

However, no credit f or this ef f ect is considered in the calculations of l11 atmospheric dilution factors.

Modification of the air mass due to travel over water is not considered to be significant as the over-water fetch is limited and the temperature contrast between air and water does not reach the magnitude required for rapid air mass l 11 modification.

It is dif ficult to generalize on the overall ef f ect of terrain on the long-term everage dilution factor. Normally, irregular terrain will promote mechanical turbulence and enhance the dispersion of effluents. But, average f)T wind speeds in the area are low and during the summer and fall seasons periods 11 of stagnation are fairly common. In most circumstances, it is believed that the net effect of the irregular terrain could be demonstrated to improve dispersion rates near the Site as observed in the Mountain Iron Diffusion Trials (27) . In these trials of diffusion over rugged terrain, valley location l11 sampling p nts were lower in concentration than ridge lines by about 50 percent (27 11 2.6.5 ON-SITE METEOROLOGICAL MONITORING PROGRAM See Section 6.1.3.1 of the Environmental Report.

2.6.6 SHORT-TERM (ACCIDENT) DIFFUSION ESTIMATES A statistical analysis using hourly data from the CRBRP 361-foot permanent 8 l11 meteorologicai tower fce the period from February 17, 1977 through February 16, 1978 was performed to estimate aimospheric dilution factors (x/Q). The 9 Pasquill stability classes were determined by temperature differences between 33 and 200 feet and wind speed and direction at 33 feet. Data recovery was 97 percent.

2.6-15

Amendment XI Janua ry,1982 O

Fifty (50) percent x/Q values representative of post-release time periods up to 30 days are presented in Table 2.6-29 for downwind distances as f ar as 50 B l9 Il miles from the reactor plant including the minimum exclusion distance (2,200 $3 feet). The fifty (50) percent value is the average value of dilution exhibited by the data and is used to assess the consequences of postulated plant releases evaluated in the Environmental Report.

2.6.6.1 CALCULATIONS Fifty (50) percent x/Q values for time Intervals up to 30 days following postulated releases were estimated for downwind distances up to 50 miles from the reacto plant. The time intervals selected f or this analysis were the same five pt ods specified in NRC Regulatory Guide 1.4; O to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , 0 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 1 to 4 days and 4 to 30 days. Other NRC Regulatory 9 Guides used in the Calculation and Methodology are Reg. Guide 1.70, Reg. Guide 4.2, Reg. Guide 1.145 and Reg. Guide 1.1!1.

A computer program was developed for x/Q calculations. At each downwind distance for each cardinal wind direction, this model calculates hourly x/Q values using hourly data from the CRBRP metecrological tower (February 17, 11 1977 through February 16, 1978) and equations to be described below. For the 0-2 hour time interval, the program ranks each sector in descending order, all x/Q values associated with each sector. A log-probability plot of the resulting ordered list of x/Q values is prepared for each of the wind directions.

For a given downwind distance, the 50 percentile x/Q values for each averaging II time, given in Table 2.6-29, are the highest of the 16 values (one for each l9 O

wind sector) determined. The highest x/Q values occurred in the northwest to II west-northwest sectors. X/Q values in Table 2.6-29 correspond to either southeast or east-southeast wind directions (i.e., wind blowing f rom the southeast toward the northwest or east-southeast toward west-northwest),

whichever provided the maximum x/Q values.

2.6-16

l Amendment XI January, 1982 m

i For time Intervals of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , Ib hours, 3 days and 26 days, the technique of overlapping moving averages is used. The resulting averages are ordered and 8 Ill plotted for each wind direction. For example, the 8-hour x/Q values are lg deiermined after all hourly x/Q values are calculated. Those x/Q values in the first 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months corresponding to wind direction north are summed and divided by eight. This procedure treats all x/Q values not associated with wind direction north as zero. Average x/Q values are determined in the same way for the second 8-hour period (hours 2 through 9), third 8-hour period (hours 3 through 10), etc. When averages are determined for each 8-hour period during the year, these averages are ranked in descending order, and the procedue at i

this point becomes identical to the 0-2 hour case. These steps are then o

repeared for each of the remaining 15 wind sectors. Time intervals of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months , 3 days and 26 days are treated in the same manner, except that averaging time of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months , 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and 624 hours0.00722 days 0.173 hours 0.00103 weeks 2.37432e-4 months , respectively are used.

2.6.6.1.1 TIME INTERV AL: 0-8 HOURS Calculation of hourly atmospheric dilution f actors are based on Gaussian dif f usion equation found in Reg. Guide 1.4 for centerline ground level f concentration from a continuously emitting source with release at ground l

' 9 level:

X/Q = 3n u oyz }

l and:

X 0

u (n a o + A/2) (2)

O 2.6-17

Amendment XI January, 1982 where:

X = Activity concentration, Curies /m3 g Q = Activity release rate, Curies /sec u = Mean wind speed at 10 *sters above grade, meters /sec !9Ill o = Crosswind dispersion parameter, meters y

07= Vertical dispersion parameter, meters A = Smallest vertical plane cross-sectional area of the reactor building, meter:

The dispersion parameters Cy end e, were evaluated in accordance with the Pasquill-Glfford curves (28) except f or stability class G which was obtained from AEC Licensing Staff, Site Analysis Branch, Directorate of Licensing (29) .

A mean wind speed of 0.74 mph was used for all hours during which calm 9

conditions occurred (wind speed less than 0.74 mph). The area (A) of the reactor containment (2415 square meters) was used for this purpose.

For alI stabtiItles and alI wind speeds, the computer program calculated x/Q l11 values from equation 1 and 2 and picked the larger of the two. f))

2.6.6.1.2 TIME INTERVALS; 16 HOURS TO 26 DAYS The equation for calculating hourly atmospheric dilution factors for postulated release times greater than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is given in Reg. Guide 1.4 and 11 here includes a correction factor (Equation 3):

2 T _ 2.03 T (3)

X Q _ (n)1/2az u 2nx' oz ux 9 y

O 2.6-18

Amendment XI

() January, 1982 where:

X = Activity concentration, Curles/m3 Q = Activity release rate, Curles/sec-op = Vertical dispersion parameter, meter x = Distance downwind, meters T = Open terrain correction factor (1 to 4) depending on distance downwind 8

This equation assumes that the plume meanders uniformly over a 22.5 degree sector. For all downwind distances, stabilities, and 9 l11 wind speeds, the effect of the turbulent wake is taken into 7- account.by adding to the dispersion parameter an effect based on

\m/ the maximum allowed under NRC Regulatory Guide 1.4 or the height of the building as suggested by Sagendorf(28) . In practice, 11 Sagendorf increases a by the square root of three or substitutes (r,2+hh)2 in Equat on (3). In this case, C is the wake factor 9 equal to 0.5 and D the building height, taken as 51.5 meters.

Equation (3) is evaluated for both changes in r, and the results are compared and the larger values used. The open terrain correction factor (T) is used to simulate the differences between g a constant mean wind direction X/Q equation and a fluctuation mean wind direction X/Q equation. This open terrain correction factor is from NRC reg. Guide 1.111, Rev. O, 1976.

2.6.7 LONG-TERM AVERAGE DIFFUSION ESTIMATES Hourly average dilution factors (X/Q) are calculated using l9 Equation (3), with the building wake factor, for the year of 11 record for downwind distances up to 50 miles using the 33-foot O. level wind data (wind speed and wind direction) and the 33- to 200-foot stability data. All X/Q values corresponding to a given 2.6-19

Amendment XI January, 1982 wind sector for the entire year are summed and divided by the total number of X/Q values for all wind sectors. This procedure is applied to all 16 wind sectors, yleiding an annual average X/Q value for each sector and a given downwind distance. Results are listed in Table 2.6-30. Il Least dilution Is found in the sectors that lie to the west-northwest and northwest of the plant which is consistent g wIth the relatively high percentage of type F and G stability conditions associated with light winds that blow from the east-southeast and southeast.

O O

2.6-20

Amendnent XI l January 1932 TABLE 2.6-1 MAXIMUM RECORDED POINT RAINFALL (8)

KN0XVILLE, TENNESSEE AIRPORT (1899-1961)

Rainfall in Indicated Periods (inches) flinutes Hours 5 10 15 30 60 2 3 6 12 24 0.58 0.99 1.37 2.57 3.52 3.57 3.97 4.88 5.60 6.20 Maximum monthly: 11.74 Maximum annual: 61.49 1

2.G-21

- . _ _ . _ , _ _ _ _ _ . _ . . _ . , _ . _ _ _ _ , _ . . _ _ _ . . _ _ _ _ _ . . _ _ . _ _ . _ . _ _ . . _ _ _ . . _ _ _ _ _ . _ _ _ _ _ _ . - _ - _ . - . ~

Amendment XI January 1982 TABLE 2.6-2 CALCULATED MAXIMUM RAINFALL OVER VARIOUS TIME PERIODS (9)

FOR A RECURRENCE INTERVAL OF 100 YEARS AT THE CRBRP SITE AREA Time Period Rainfall (hours) (inches) 0.5 2.50 1.0 3.00 2.0 3.75 3.0 4.00 6.0 4.80 .

12.0 5.80 24.0 6.50 0

2.6-22

3

!a 0 e e ;

1 -

3 t

l !

1 TABLE 2.6-3 M0!1THLY DISTRIBUTION OF SEVERE WEATHER - 0AK RIDGE CITY OFFICE

i r

Jan. Feb. Mar. Apr. May June July Aug. Sept. Oct. Nov. Dec.

! Snow, Ice Pellets +

l.0 inch or more 1 1 0 0 0 0 0 0 0 0 1 Thunderstorms ++ 1 2 3 5 8 9 11 9 3 1 1 1 i

i ?

! Ei *Mean number of days i

i **Less than one-half day

(

i +1953-1973 i

l ++1949-1964

! & 3" E2 m o.

I kN 5

L

~-

1 l

i Amendment XI January 1982 TABLE 2.6-4 MONTHLY CLIMATOLOGICAL TEMPERATURE DATA 0AK RIDGE AREA STATION, X-10(l) 1945-1964 Climatological Standard Normals 1931-1960 Mean Daily Daily Highest Lowest Monthly Maximum Minimum Temp. Temp.

Month ___(F) ( F) ( F) ( F) ( F)

December 40.4 49.4 31.3 76 -5 January 40.1 48.9 31.2 77 -8 February 41.7 51.6 31.8 77 0 Winter 40.7 50.0 31.4 77 -8 March 48.0 58.9 37.0 87 4 April 58.2 70.0 46.3 89 24 May 66.9 79.0 54.8 94 32 Spring 57.7 69.3 46.0 94 4 June 74.7 86.1 63.3 99 41 July 77.4 88.0 66.7 103 49 August 76.5 87.4 65.6 99 44 Summer 76.2 87.2 65.2 103 41 September 71.1 83.0 59.2 103 33 October 60.0 72.2 47.7 91 21 November 47.6 58.6 36.5 83 4 Fall 59.6 71.3 47.6 103 4 Annual 58.5 69.4 47.6 103 -8 Oak Ridge City Office (4)

Climatological Standard Normals 1941-1970 Annual 57.8 68.6 47.0 105* -9*

Knoxville Vicinity (3)

Climatological Standard Normals 1941-1970 Annual 59.7 69.8 49.5 104** -16**

May 1947 - October 1974

- 1874 - October 1974 2.6-24

~

Amendment XI

, January 1982

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I 2.6- 25

94 Amendment XI

& January 1982 rA e-e db 6 IL f N 4 7 mi en *= 0 m O 4 m e om @ 4 M c=

W 9 e e e e o e o e e e e e o e e e e to I en ers w ers 4 + P= 4 e N so N N >= N 3e 4 e i en en e ao @ p O en O O e *= 4 4 N c0 eJ G 0 M m e *1 e J O m La e e O N c0 m M &

w 0 P N er t & 4 4 O N O 4 e- 4 ao N e O O M 0 C7 O O O O EJ O O O O m M ** M N O 83

=. 8 O O O O O O O O O O O O O O O O *

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@ LLJ W b C "e

- 4 O O O O O O () U u O e. ao n 4 O O en N N N I g ( J , 8 0 O O L3 O O O O O O O O O O u O O *= e- e f

Q e4 __j q "I~ M ** 8 O O O O O O L3 O C3 O CJ O O O O O C3 N e

. Q g y O v e i O O O O O O O O O O O CJ O O O O O *= ']

O t e e e e o e e e e o e e e o e e e p y _ 3 " '

Q > 0 O O C kJ 2 H O & LLJ g g

.J ~ ~ J I W . e >= 0 ~ en O P. O P= Q n en - M en .n - en %

CO 3 J Q H CL U f *= O en m O ** O e= u O ett N en 4 N N 43 5ae q - M W *= 8 e= 0 m N O e= O e= 0 O O en O => tw as tp tw as F-. L. CQ O N 0 0 O O O O O O O u CA O e- '3 e- N N O P= (> e v

Q q gj N O e 1 O O O O O O O C3 O C3 O O O CJ fa U C3 P= ei p p m Z

eO O O O O O O e O.

O O O O O CD O O e o e e e e O

e g,

y g y g g e4 e o e o e e e o ,, g U E 3 US Z

c g 'S' W H h e i C) ers P* N N wi O P= O en b eJ #4 C5 O A O i*

J = e~ e e C2 m - en - m C2 e O m O m .n 4 e e e . . .

C7 LLJ 8 CJ N ** m *- N u ** u N 4 O M 4 4 ** 4 *- P= .* o La.J Z > l ' O O O O O O O O O O *= O O O O O 4 en e Z ct" & & 8 O O O O O O O (> O O LJ u O O O U O ert i**

u. ;- q e O O O <> e y 2 ,,e e O. O. O. e e O. O. e O. O. O. O. O. o. O. e O. y g y y e .-4 Z CL CD q g 5 "

-* W e e P. O P= N N N O u o es e e P. O O cs e' ' r " i O

O c.

Cf CD u- 4

e. OO **- enM men*=- UO UuuON mene eJN - O O O 9 e 4 eO O O O O O u O O O u t.2 e- LJ CJ O 4 as tw O u O O ew N o

F-Laa 3

r'

(

J Z y

e- 0 O u O O O u O O u O O O O LJ u 41 e 8 O O O O O O O (3 O u u O C3 O 4 e3

[ , e4 g n I e e e e e e e . C .3 e e *

e O. t .3 - go Z '

e [

Z O e 4 e f O u O O O CJ U O O O CJ O O CJ O O O g

o 78, m eO O O O O O O O O O O c2 O O u O O c -e o 8 43 O O O O O O O O O O O O O O O O O O -* y 0 8 G O O O O O O O u f) O u O u O O O

i CJ O O O O () O LD O O O CJ () O O O O ~~ C *;' ,*

an. eO O O O O O O O O O O O O O O O O ..

e e e e o e o e e e o e o e o e e e p * < es I @

e4 .a h

p. g N er ea O E e eO cJ u O O u o O : O O u O O O O E, '

sO O O O o o O O O O O O O O O O u are r-

,E 0 C O O CJ CD r1 O O O u O f3 O O O O O O O e in i eO O O O O O O O o o O O O O O O O o.

O

O. eO 8 O O O O O 18 O O t) O O O O E1 O O O O O O O O O f ..

A

, e O. O. O. O. e e o e e O. u. e O. e O. O. e , , ,

, ,e r

- ~ ~ ~ w w w i m 2 2 2 . e o a , ..

F 2 4 2 2 te? M en A e., ett en W 3 E E E tr tid en e Z ~ en e9 3 3 7 Z IF L3 e V3a O eas w > *f q 4

~e ra.

2.6- 26

~

_ Amendment XI

, January 1982

/ k

\ l V

a e

& tM O en go en N O N vs M en M N N eo @ M e e e e e 'e e e e e e e e o e e e e e 48 9 d aa =a =e 4 =a M en en =e en en e 4 e en m 3e 0 et 4 e= d 4 =# en e= & O N o= @ en O O @ en en O 8 *= 80 en =E3 e= N 4 m3 en e @ p so N M N =#

w I e= N =# N eD 80 ed en M e= =# M en 4 @ en en er I N M =# M N O O N O N m en N en M e= O em 8 O O O O O O O O O O O O O O O O en Oe O O O O O O O O O O O O O O O O o e e e e e e o e e o e e e e e m 4m e e e d N q N M m e e N m e M e 5 0 ** N M N N N o= e) =# N =d org o= M g K I 4 O

k p i O

e 8 O O O O O O O O O O O O O O O O O J D 8 O O O O O O O O O O O O O O O O O W W D 4 O u O O O O O O O O C D o O O O O u O w y 9 9 O O O O O O O O O O O O O O O O O e a y N 8 O O O O O O O O O O O O O O O O O g g g e 9 O Oe O o O eO Oo Oe O O Oe O O eO O Oe O e= 6 e O

e e o e e o e e N N 6 O H M C O - e= e H Q

0O O O O O O O O O O O O O (J O O O 3 lJ

e= 1 0 O O O O O O O O O O O O O O O O '

3 W N 00 O O O O O O O O O O O O O O O O O O O M ,e 8 8 O O O O O O O O O O O O O O O O O e M N 8 O O O O O O O O O O O O O O O O L3 Q

y

,o

tI eO Oo O O Oe Oo O eO O O O O O O O O e e e e e e o e e o e O

e O' 3

= E . <

O W D ^ e= t M U 3 % 4r e eO O O O O O O en u O N en N N O O O H O CD M 4 8 O O O O O O O M O O e M en us O O o O M M W 6-- *= 0O O O O O O O N O O *= N M M O O e= N e= -

N W M g q a WO e eO O O O O O O O O O O O O O O O *=

e* 0 O O O O O O O O O O O O O O O O e= e ".

g z O O N o e ee a 4 z g O

e 8 O O O O e e e e O. e O.

O O O e e e O.

O O O O O e e e o e O e e

/,

o Q o a c _ y

\ N *=* D

' O >- O O O O I /

W = H O % W

^

' , ,~ J w e -e e i N N N N N O O O O O so e =a MM =a O g J Z LaJ O 8 m e e= en e= 0 O O O O N O O 4 4 O N CD 3 J e-e O P Q. e= sM e= e= M e- O O O O c3 N N N =e =a N en M N -o q Cx" W 9 0 O O O O O O O O O O N O O N N O m O e "

p w Cc c N e 8 O O O O O O c3 O O O O O O O O O e- N v.

Q q W N Q e i O O O O O O O O O O O O O O O O e

g. g e z ee e e e O. e e o e o e o e e e e e e K.

>= M W e=4 *--e o

O 2* 3 en 8 ?$

Z *

8 em so N e= e= k. A e= en e M @ *= c =# m ee -@

W H N 4 I M w'* 4 N N e= e= N M ep 4 en N 4 O 4 m I*

D Z r=4 i N $ e e a) e= e= e0 N en =# N 80 M N =# A E0 en as C C7 W I 5 O O *= O O O O O O O N *= O N O O N ed e ** U W Z )- @ $O O O O O O O O O O O O O O O O *= e= en -en g

g

( Q q" e 8 O Oe Oe O e O eO O O O e O eO O Oe O O eO et t e e e e e o e e O

e g

D ' yg v' H WE 80 2 65 i'

Z Q. CD e eM N O ,a N 4 en en N en e M =a e N en p -evc O CL i

LL'J 4 1 N O 80 Om O e= =d ers e

=# O M N

@ N N vs o= N en 4 O 4 en M e= en d me N =# M N =@

he en O kp, g. 3 e

e3 Q" 9 0 e= e- N e=

O O e O e- =# N O O O O 80 e= e **

CO e= 8 O O O O O U O O O O O O O O O O e= N w LD T.6

_a m o s u u O O O O O u O o.

O O O g a ne e e e e e e e e o

O. O. O. e O. e e r, D_ ,

' n ,,

t, O e '0 i

'r e eN e N N M i en ~ - - M O

w. O N O O O c e O O N N

e. o O O M M O o- -

M a

g -

8 M ar) e= e= N O c ,

e= (J O O N N O O e* ** ** 3 en 4 ,

8 3 O L O O U O O O U O O U O U O O N N e

'I

Eu 9 O O O O O O U u O O O O O O O {1 Ci N '~ . , ,

e es3 (3 O O O O O O O g2 O O O O O O O I e o e e e e e o e e e e o e e e e g , p I eV 1

a#

N $

6 O O (3 O O O O O O O O U O O O O O L 8 O O O L3 43 O O O O e) O O O O L3 O O m , ,

, 8 O O O t) O O O O O O O O O O O O O O O - .e. n

[. l 9 O O O s1 O t3 O O O O O O O (3 O O O e et) -

O eO O O O O O O O O O O O O O O O

-e sO O O a O O O O O O O O O O O O O

O

=

g-O < , .

< l e o e e e o e e e e e e o e e e e ,

f l- g gp eJ sm a O v>-

end w en# esa and W a aF a a enn a e e a e a m 3 x x 3 3 3 3 3 ,3 m G

ea w j -

nw D w end e e 3 3 3 2 < J '

s\

! , .c.

-g

)

2,a

a l

i -

I l

\

2e6-27 i

( ( \ .,

E-m i. h, .-- ',_- , ,

TABLE 2.6-8 ANNUAL JOINT FREQUENCY OF WIND DIRECTIO*1 AND WIND SPEED FOR STABILITY CLf-SS D CRBRP PERMANENT METEOROLOGICAL TOWER, 33-F00T LEVEL FEBRUARY 17, 1977 THROUGH FEBRUARY 16, 1978 11 WIND SPEED (KNOTS *)

.h; .C- .7 .s- 3.0 3.1- 4.s 4.9- 6.5 6.6-10 0 10.i-16.1 te.2-21.t 21.2-99.9 nsS r=Ea AvsSeo 3: RECT!0N h .0000C0 .00E209 .003C49 .000235 .000CC0 .00C000 .000000 .000C00 98 .011493 2.5 NNE .0C00CC .0C7622 .CC4P09 .000704 .0000C0 .000000 .0C0000 .000CCC 112 .C13135 2.9

%E .00CCCC .00691? .C1CCC7 .CC2?15 .C00235 .000C00 .0CC000 .COCOCC 195 .C22269 3.4 ENE .C000C0 .014190 .0163C1 .CC4026 .000117 .00C00C .C00000 .000000 3CI .035534 3.4 L .000117 .012e66 .0CE444 .C00!21 .C00352 .C0000C .CCCCCO .00C000 191 .022399 2.9 ESE .000117 .006216 .CC4e91 .CCC235 .000CCC .00000C .CCCCCC .0000C0 96 .011252 2.8

.N SE .000C00 .C04691 .002215 .CC0117 .000000 .000CCO .000000 .C00C00 65 .007623 2.7 7 SSE 0000CC .006209 .C11??6 .CC4222 .002697 .C'117? .CCCCCC .0000C0 236 .027677 4.3

$ S .000CCC 0C5277 .CC55e4 .0C0939 .00093! .000117 .000000 .000000 112 .C13135 3.!

SSW .;000C0 .CC4EC! .004456 .CC1407 .0000CC .C00CCC .CCo000 .0000C0 91 .010672 3.3

.C00CCC .00E913 .C16?O1 .0C867* .005746 .CC14C7 .0C0117 .000000 351 .C41163 4.7 9 Sw WSW .00CC00 .011962 .016647 .00E 3 26 .007154 .C02697 .0CC117 .0C0C00 417 .046903 4.2 w .COCOCC .CCE092 .CCE!26 .C02111 .002463 001173 .CC0C00 .0CCCCC 189 .C22165 4.3 wNw .00C0C0 .CC7623 .007257 .01C672 010555 .C02!15 .CCCCCC .CCCCCD 337 .C39522 5.6 Nw .00C000 .004222 .CC5043 .CC4105 .005864 001173 .000CCO .000C00 174 .0204C6 5.3 NNw .COCCCC .006450 .002?45 .CC3C49 .000935 .C00000 .CC0CCO .COCOCC 109 .0127E3 35 Mas 2 1C92 1119 455 316 90 2 0 3076 FREQ .00C235 .128C64 .131230 .C53360 .037059 .010555 .0C02I5 .0000C0 .360736 AVGSPD .7 2.2 3.P 5.5 7.7 11.5 16.7 .0 4.1 m z 5$

1 knot = 0.515 m/sec; I knot = 1.16 trph yg ko e frequenc'.s o' : aim w is are p ien i, :.e e rst .m gees colamr, 3. 3 9. t . 11 ~S sote:

,e .7 *not u e,e s w ee,a v e . ira p rec: x u,s y g

~-

O O O

1 1

=($

P1D b =" xM u o 9 Ga 35E . $cN G] 1 1

D P _. 5 8 5 5 0 0 7 9 6 5 1 2 7 9 6 9 5 S _

G _ 1 1 2 2 2 2 1 2 2 3 3 3 2 2 2 '1 2 W_

_ 9 7 2 3 7 5 0 8 5 2 4 9 6 5 4 1 9 G _ 4 2 5 7 4 6 9 9 4 C 9 4 3 9 4 2 E E _ 5 7 2 0 6 2 1 9 9 2 E 4 4 4 3 7 4 a _ 2 1 3 4 6 9 4 8 1 6 4 5 9 6 1 3 4 F _ 1 1 1 1 1 0 1 1 1 C 1 2 2 2 2 1 6 0 0 3 0 0 0 0 0 0 0 2 C. C. C. C. C. C.

~

s _ 7 0 3 C 9 9 1 2 1 2 7 7 1 3 2 7 7 a _ 0 0 1 2 5 7 2 6 0 5 2 1 5 4 5 1 5 w _ 1 1 1 1 1 1 1 1 1 2 2 2 1 1 2 R 2 O

_ F 9 _

_ 0 C 0 C 0 0 0 0 0 0 0 O 0 0 C 0 C D L 9 _ 0 0 0 C C 0 0 0 C 0 0 C C 0 D 0 C E E 9 _ C 0 0 C 0 0 0 0 0 C 0 C 0 0 C C 0 C

- _ 0 0 0 C C 0 C 0 0 0 0 C 0 0 0 0 D C.

E V 2 _ C 0 0 C 0 C C 0 C 0 0 0 0 0 0 0 C P E _ 0 0 0 0 0 0 0 0 0 0 0 S L 8 1 _ C. C. C. C. C. C.

7 2 _

D T 9 l

r 0 1 1 _

I 0 _ O 0 0 0 0 0 O 0 0 0 0 C C 0 0 C 0 W F , 1 _ C 0 0 0 0 0 C 0 0 0 0 C C 0 G 0 0

- 6 2 _ C 0 0 0 C C C 0 0 0 0 C C 0 C C 0 0 0

- _ 0 0 0 0 C 0 C 0 0 0 0 C C 0 0 0 0 D 3 1 2 _ 0 0 0 0 C C 0 C 0 0 C C C 0 0 0 0 l

t 3 _ 0 0 0 0 0 0 0 0 0 0 0 A Y 4 _ C. C. C. C. C. C.

R 1 _

1t R A 0 E U ) 1 _

1 E W R

_ 0 0 0 0 C 0 0 6 0 0 7 5 0 2 7 0 7 T O B S 6 _ 0 C 0 0 0 0 C 5 0 0 1 3 C 5 1 0 0 1 _ 0 0 0 0 0 0 0 5 0 C 1 2 0 3 1 0 2 4 4

_ 9 E S C S T E T F 0 - _ 0 0 C 0 0 0 0 C 0 C 0 C 0 0 0 0 1 1 l 1 _ 0 0 0 C 0 0 0 C 0 O 0 O 0 0 0 0 C 1

- R A L i

_ 0 0 0 0 0 0 0 0 0 1 3

_ 6 I L A H K (

0 _ C. C. C. C. C. C. C. C.

D C C G

^s) 1 _

2 I U ..

/N E D

4 f

Y G O D T O R E 0 _

_ 7 C 5 0 5 9 0 2 5 4 2 9 4 9 6 7 0 _ 1 0 3 0 3 6 C 4 3 0 4 5 0 5 s 3

0 c

L I I L H E 1

_ 1 7 2 m B W L O T P 1 0 2 0 2 4 0 6 2 7 6 7 7 7 5 1 8 A I R S - _ 0 0 0 0 0 0 0 1 0 C 1 1 0 1 0 C 8 0 6 _ 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 C 1 7 i

. T F B O 7 _ 0 0 0 0 0 0 0 0 0 0 0 0 0 0 e O A E 7 D 6 _ C. C. C.

a.or.

T T 9 4 f _

Y S E 1 I cs C M W 5 _ a t

i , _ 0 0 6 4 6 _ C 0 6 0 2 e 7 1

5 P 5 7 3 3 2 5 9 2 9 3 C 3 4 5 3 4 6

5 2

2 e.es E T 7 : n U l t 1 _ 0 C 5 7 5 1 2 9 9 4 9 3 7 9 0 5 e 1 5 o

Q E - _ 0 0 D 0 C 0 0 0 0 1 C 2 1 2 3 0 h 7 ,P E N Y 9 _ 0 0 L 0 C 0 C 0 0 C C C 0 C C C t 1 5

- c

_ 0 0 0 0 0 0 0 0 0 0 R A R 4 _ C. C. C. C. C. C. C. e F M A _ ,e rts R U -

T 4

t E

P R

B 8 _

_ 2 8 2 5 5 5 1 6 0 7 6 5 7 0 6 5 1 h

usn i I E 4 _ 5 3 3 0 2 5 2 6 8 C 6 8 5 6 6 2 4 c rw O P F _ 3 9 9 1 5 C 2 1 5 4 1 6 8 1 1 5 6 6 7 n r e

- _ 0 0 2 6 1 1 0 3 2 3 6 7 5 3 1 9 6 e J R 1 6 mn B 1 _ 0 0 C 0 0 0 0 C O 0 0 0 0 0 0 0 3 4 3 1

_ 0 0 0 0 0 0 0 0 0 0 0 0 L R 3 _ C. C. C. C. C. ef

_ A C _

1 ro U = d nee 1

tt 0 _

t' - es t _ 0 7 7 3 5 3 0 8 7 6 1 C 9 5 3 6 5 o A 3 _ 1

_ 6 4 3 4 1

1 1 9 7 6 2 0 4 5 6 e 9 2 7 7 7 9 5 8 1 5 1 5 1 0 3 6 2 2

6 k n i. s l

_ - _ 1 C 9 8 5 7 2 2 7 3 8 4 E 6 4 1 7 4 2 _ 1 1

0 0 0 0 C C.

1 C 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 1 C.

1 5 2 0 1 1 1 1 c

+l t a

s

_ e s

sre t 7 _ /

m :e1

_ 9 2 2 2 6 C 5 7 5 7 9 5 6 7 2 7 1

_ 6 5 5 5 2 C 3

_ 4 3 3 3 5 C 2 1

1 3

2 1 1 6 3 a 4 2 5 1

1 5

3 1

1 0 6 9

7 5

1 e1 e

t

- _ 0 0 C 0 0 0 0 0 C C C C 0 C 0 0 4 4 5 0 _ 0 0 0 0 0 0 0 0 C O O 0 0 0 0 0 0 0 0 0 G.

0 0 0 C. C. C.

0 0 0 0 C.

0 0 0

=

m. o 7 m

_ ee D

t o nTr E E E t E E w . W W w w s Q P n k

N N N N E s S S s s s 5 a N N N a E S e N E E S S W w N w R G 1 V

F A

m

~

_ (\

_ N7@

.I 1 ?2 f j1 j] ii j ! ll ,){ fj! )!l 1, ! j , bi 4

knendment XI

, January 1982

.-e O 8

& 8 N e= N N N e- N N Pe N C. m 4 4 e= *= N a 8 e e e e e e o e e o e o e e e e

%S I e. e- s- e- e- e- e- e- .- e- e- e- *- s= e= e. s=

> 0 at I c O 4 em N e. 4 M >= J @ N so *= 80 M N a 8O ,e* en en ** N P1 e @ m3 m O 4 e= en N **

end 1 M s= en e P. e M e N *9 O em O N e em W 4 e em mm O O s= N en N M 4 m3 N en e- Pm M m 8O O O ** e- e. N s- O O O O *= e- ** O en Oe O e O oO Oe Oe O o O eO Oe Oe O e O eO Oo Oe o e=

e e e H I e 4 e= O e- OM e- M e mm @ >= 80 e em o

% er 69 4 e a '> o=0 & Me- N N M e O N .= & cs= O Z 8 e-O M w

L e 8 C J e 8 O O O O O O O O O O O O O O O O O w LU & 8 O O O O O O O O O O O O O O O O O w > @ t O O O O O O O O O O O O O O O O O O O a w 8 i O O O O O O O O O O O O O O O O O e g g g N 9 O O O O O O O O O O O O O O O O O g

1O O eO Oo O e O oO Oe O O O O O O c - , - , e e e O. O. O. e e o e e e Z O ~

e-* O e- 8 3 L

I C e iO O O O O O O O O O O O O O O O O O- M o-8O O O O O O O O O O O O O O O O O m

e-4 N 1O O O O O O O O O O O O O O O O O O O 8 00 0 0 O O O O O O O O O O O O O O e Q , y y Ne aOIO O O O O O O O O O O O O O O O O O

.- % < e e e e O. O. Oe O eO O e Oe O oO Oe O O eO O e e e e o O

e e- 8 O W D ^

- L 3 % *

8 H C C3 W e eO O O O O O O O O O O O O O O O O O O M k- WH e aO O O O O O O O O O O O O O O O O ee w w L O e- eO O O O O O O O c; O O O O O O O O O O ,

g g q J g - g 4 7 g Z 8 8O O O O O O O O O O O O O O O O e- 8 O O O O O O O O O O O O O O O O O * *'

O -

, a y y a v e eU O O O O O O 8 e C. O. O. O. O. O. O. O. O. n m - , e e e e O. e O.

o >. e C o .

LJ Z H O % W O e J *-* M -.J I W cc 3 J O H C. e 8 O O O O O O O O O O O O O O O O O -

< w M M O I O O O O O O O O O O O O O O O O O

== 8 O O O O O O O O O O O O O O u O O O O p 6 gn O rw I I O O O O O O O O O O O O O O O O O e

?e O < gWg Nm Oz * ' O O O O O O O O O O O O O O O CJ O y g g g - ee e8 eO O e Oe Oe O e O eO eO Oe Oe O e O eO O e Oe O e e e O

e e,

G E 3 ' p Z

T; c 8 '

W H N

8 P-O O O O C3 O O O O O O O O O O A "D Z W e I e=

O W 0 O O O O O O O O O O O O O O **

7 .

W Z >-

8 *= O O O O O O O O O O O O u O O *= ** M g < M 0 IO O O O O O O O O O O O O O O O O e -s O 8 O O O O O O O O O O O O O O O O O e '

.- 4 p g eea ie O eO O e Oo Oe O e O o O eO O e Oo Oe O o O eO oO e e O t -

e

f. 7 6- LJ d Z C. CD e g 1 ~E

~ W e iN P. N en O en O >= N >= O M O si O N O O C- L r e i 4 8 *= >= em em O M O .= e= e= 0 P. P. O s= M c. e o d e e= e- M N O N O e- e- e o e- 4, e- O w N = c E '

CO 8 8O O O O O O O O O O O *= 0 ** O O M 4 * -

J g *= BC O O O O O O O O O O O O O O O OM e q y

8O O o O eO Oo 0e O e O eO Oo Oe O e O eO O O O . 6 g m B e e e e o e e - * .

Z '

Z O e a 7.

[

4 e I e M 00

.a en ** N P= @ c P=

P* e >= O e W O ao M O O e e e en e e so M P. N e 4

$C i*

9 eD em M 51 e W 4 *e en s" N w N 4 m O & O N * . .

8 f J J @ @ O O O 4 N M M e w M O N O N * **

80 I O O O O e= e- N *- O O O O s= ** O O e= ** *-

e 9f e C Oe O e O eO Oe Oe O eE3 e O O Oe O e O eO O s* e- = +s e e e e e e U rs e 0 *

,. . ~ _ .

e IN O A O O e e e O O e p e N e O N /g 8 em o O e o are N w) O O c e N em N e e sf4 t ?

IM e v o-4 O O N e=O O O O 4 e P* e 4 N O N ~

[t 8 8O O u o N O O O s= 0 O d - O O .- e

$ a;'

O. 8O O O O O O O O O O O O O O O O w e o 5 8O I e O e O eO Oo Oe O o O eO Oe Oe O o O O e Oe O O

e o e e o e ai g L G g e i El O w w w w w w Qm

,1 O

a m z e z ted en' W 3 3 3 e o a e a a e i z z z W M

3 3 3 en a &

w o

.g e,

3 E F Z W G S 9W * * ".

w- W en 2.6-30

i e-4

<j-

.ee-2 Amendment XI cn January 1982 M

J e 4

& 9 O O o- *= C3 O e- e- o & N r C3 t3 e-d 4: O. e e e o e o e o e a e e N. e e e

- 69 8 >= e- e= o= en o= e= ** e= e= e- e= e- e. e=

lp 8 og g

@ N O P O N en O ^ >= su en e A el m 4 en E9 9 en N e * >= @ e- e o *= 0 ** L3 en en e3 em nas 1 Pm N == =# P. @ 4 O & en e= . N (> N P. N C3 a

er 8 ** 4 .a & e e- er) 43 m en =# 4 O e= M M. m em 4 O O O C3 **

N ** O O O C3 e- e= O O ,e 1

O E3 (3 Q O (3 (3 rJ (3 L3 (3 e.

a e o e O. e e e . O. s e e O. e O. O. .

e e" en e e e- m N .o .s .o O + m m e N .o u I

G m ee 43 *F G 4 en m we 84 en @ O m N N 2 9 ** e= N e= N M e=

O 4

La o e

iO O O O O O O O O O C3 O O O O O O a J O.t O O O O C3 O (J Q O O O O O O O O O y w @ 8 u O O () O O O U L3 O O O u O O O O O L3 y y 4 8 O O O O 43 O O O (3 O L3 O O C1 O L3 0 o O- N $ (3 O U uO O O u L3 U U U O u o O

9O O

m- J CO O O eU u O o C3 O O u u eO E3 O O N

e~ 9 e N e O. e e e e e e e e u. e e e O H Ch

= O M e- t 4 >-e O . 4 O O O O O O O O O o O O O u O O O 3 e c= eO O O u O O O L3 O u O O O u O (3 0 La,,. Ne 8eOOO OO uO oO o O u u O O u u O o u O u O

!. a,, m e, O O O o u O u O o o O u o e 9 - m N* eO eO o O uu o O uu o o u c) o O O u u o i

< >- O s3 g e e O. O. O. e O. u. . ae . O. e u. O. e o. O. u.

d *= 0 Z m<

a O w a^ - e I

w Q E M +

i O O O O O u O O C3 83 O O CJ O O O ,O H. O m m e i O O O u O O O O O O ts u u O O u O

, o m H w H -e eO O O u O O O o O (s O O uu u O O O O ,;

4

~, w m w og O o O O O O (3 O O v u u ou u o

- t Oo O O ()

u * --

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. t u o o O c3 O c3 o u O O u O O O ?

4 @~ -J < -

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v g

e e e u. e O. u. O E3 (3 o e . e o. u. ue o. O. o. o. e3

. o O U U t.D O.

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O >- 0 O O e c e

w .= H O_s& rLaJ

,,,.3 - w O. 8 O o O Q

c. O o o u O u to O u OO o 8 O u O O o o uo O uC3 oO o o o u O u

- I u O O O ik o

c3 .

m 3 J Qm Hg . Q. u O u o G L3 O La O rJ -3

!. 4 m e eO O O o O O O o .O. O O O O o c3 o O e g g g o p.,,, e* an '

c3 O O o o o oo 43 O o O se O O O g e e . ". ". e . ". . ". " . * ". ". "e ' . ' ".

O < W N O C'

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l >- m W - ~ .0 j U E 3 en I cr Z *

I O u O O O O (3 O O b u (* A sa u o i$

LaJ, H N e8 O O O O O O O O O O u O *= u o o N.

e 1 ---

Z ,e 8 O O O O O O C1 O u LJ u &6 ** u u u *- o- ea */, E 4 g Laj y

i 0 O O O O O O O O u E3 O u O O O O O e 6 g y O B4 D O O (J O Le o O L3 C2 O O O O O cs O e - *

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>-e l

1 O,

Q LLA La ,

4 9 O O O *= - O O == 'u u O ==

eu o u e- -- o La e- u La u e-e-

e-

- O u e- Le u e O

r-(s c*

- g 8 0 0 O O O O (3 O O O O u O O L3 O L3 SJ en. ,

r.

g.g == 8 u L3 u O u L3 o t3 L3 O O u uu u se OM e- ae g . 5 O u t3 33 O eJ (3 (3 g3 e3 Q t) O r3 a3 O O @--

< U " ' * * * * * * * * * * * * * * * *

D

- 4" Z e a eE o.

r Z O. 9 LP es @ ** N en ** wp ert et e. CJ et, e= N *# '1g l < m ee M .n O,- O A -s O m - en # N e. O e M,

- o =

e v. c .,s es m e ee <> ms e u es <> .s a sn N i

e a- m - e. e o e,n

- as n. . m e o e m N as e- e. .w -g;.

8 O O O E* *- e- N e- t> O O aJ e- L3 (3 O O N *- e* * *e a.s 6 O g3 O g.3 t) O c3 e3 g3 e3 43 O o (3 e= e- *# #

I e e e e . e e e o. e O. e o e y w ,

I 4

id*

Ph $ % u.m e8 9 9 O 4s of N Li O N N %R N U N 96 N N em E e

' eu e 0 N,

- en # a- 4 e u en o e o en e - ,,,

Q" O O er* A e orn N ist 4s ee fu *) L3 M 4 m #1 ef) U Pm -. e. O e

$ 0 O () t3 ** f e- M wa ..) .f 3, O O O N (J O N en c, eO o ., o e ,3 oo o u o o u o o o - -

40

$[

. ef3 t.3 t) u.

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( J.

O g **

i . . * . e e . .

O. ,

7 Ch

8 O

.h

- e e e ene ens and LA ens e .nas.

3 3 e o o . e e e i e "3

e. ,ts, &, -

C i e., e .

,=

t, e .e.

e .o.

. o e 3 a e x a u -

i p% - aw pcr er 4

. g bi i

i f 2.6- 31 i

n ~+.rv.. y m. , .

e m _a - , . - . , , . , . . . .

TABLE 2.6-12 ANNUAL JOINT FREQUENCY OF WIND DIRECTION AND WIND SPEED FOR 11 ALL STABILITY CLASSES CRBRP PERMANEf1T METEOROLOGICAL TOWER, 33-F00T LEVEL FEBRUARY 17, 1977 THROUGH FEBRUARY 16, 1978 WIND SPEED (KNOTS *)

^~

! '9.. . y .0- .7 .8- 3.0 3.1- 4.8 4.9- 6.5 6.6 10.0 10.1 16.1 16.2 21.1 21.2-99.9 HRS FREQ AVGSPD N .000821 .02c739 .004508 .0C0586 .000586 .000000 .000000 .000000 256 .033541 2.0 NNE .001407 .027090 .007271 .001876 .000117 .000C00 .000000 .000000 322 .037762 2.2 NE .002463 .026029 .01698? .005277 .001055 .C00000 .0C0000 .CCC000 458 .053712 2.8 ENE .002463 .040812 .023103 .006802 .000704 .CCCCCO .0CCCC0 .00C0C0 630 .0738E3 2.7 E .C01055 .055588 .012079 .002345 .000704 .00000C .000000 .0C0000 512 .071772 2.1 ESE .CO2463 .C34045 .DCcE 02 .0007C4 .000566 .C0CCCC .0C0000 .000C00 386 .045503 1.8 m SE .C0o333 .062859 .00387C .000586 .000000 .COCCCC .CC0CCG .000C00 628 .C73648 1.4 SSE .00269' .C51366 .016301 .006C92 .004456 .001994 .0C0000 .00000C 707 .082913 2.7 to S .C00586 .019350 .005679 .002111 .0C1173 .CCC117 .C00C00 .00C000 273 .032016 2.8 N

SSW .00CS21 .313956 .007857 .CC3e36 .0007C4 .C0CCCC .CCCOCC .00C0C0 230 .C26973 2.9

.011255 .CC0117 .00C000 667 9 SW .00187e .C24745 .024629 .013721 00187e .076222 4.2 wsw .0007C4 .038935 .C29905 .0136C4 .011141 .0C4339 .CCC117 .000C00 942 .098745 4.0 W .001759 .046200 .017591 .005395 .0C5395 002111 .CCCCCC .CC0000 656 .C80450 3.1 whw .002932 .347965 .016777 . C 16 418 .019819 .004339 .CCCCCO .00CC00 906 .106251 4.0 Nw .C02550 .C31195 .0CE561 .CC6326 .C12548 .CC1290 .000CC0 .00C000 550 .064501 3.7 NNw .C00932 .C27911 .0C4222 .CC4222 .0C2515 .00C0C0 .CCCCCC .000000 342 .040108 2.5 HR$ 272 4943 176E 762 623 137 2 0 8527 FREQ 031899 .579668 .207341 .09170C .073062 .C160c7 .00C235 .C00000 1.0000C0 AVGSPD .7 1.5 3.8 5.5 7.8 11.7 16.7 .C 3.0

1 knot = 0.515 m/sec; 1 knot = 1.16 mph Ck ce so C 3

.1 M 5 are gisee in the #irst eind s3eed "3I ,-a. Lbl' 11 03 9-

0 t e : 'ae 'retenc'e5 1 # a lat me . 7 anot 's tae all scees 3* tne ens P rect ce seascr. Q@

=

W C+

0 N

O O O

O O O V V V TABLE 2.6-13 ANNUAL JOINT FREQUENCY OF. WIND DIRECTION AND WIND SPEED FOR STABILITY CLASS A 11 CRBRP PERMANENT METEOROLOGICAL TOWER, 200-F00T LEVEL FEBRUARY 17, 1977 THROUGH FEBRUARY 16, 1978 WIND SPEED (KNOTS *)

CNC .0- .7 .8- 3.0 3.1- 4.8 4.9- 6.5 DE:*,w . 6.6-10.0 10.1-16.1 16.2-21.1 21.2-99.9 HR$ FREG AVGSPD N .000000 .000000 .000C00 .000000 000000 .C00000 .000000 .000000 0 .000000 .0 NNE .000000 .000000 .000000 .000000 .000000 .000000 .000000 .000000 0 .000000 .0 NE .000000 .000000 .000C00 .000000 .000118 .000118 .000000 000000 2 '.000235 10.6-ENE .C00000 .000000 .000000 .000000 .000000 . 00C000 .000000 .000000 0 .0000C0 .0 L .000000 .000000 .000000 .000000 .000000 .000000 .0000C0 .000000 0 .000000 '.0 na ESE .C0000C .000000 .0C0C00 .000000 .000118 .0000C0 .000000 .000000 1 .000118 7.4

'cn SE .00G000 000C00 .0CCC00 .000000 .00C000 .00CC00 .000000 .000000~ 0 .000000 .0 b

SSE 00CC00 .000000 .00CC00 .000000 .000000 .C00000 .000000 .C00000 0 .0000C0 .0 S .00000C .00C000 .000000 .00000C .C0C000 .000000 .000000 .000000 C .000000 .0 9 SSW .C00CCD 000000 .00CC00 .0 LOC 00 .000000 .00000C .000000 .CCCCCC 0 .0000C0 .0 SW .C00C00 .00C000 .000000 .000000 .000C00 000000 . 000000 .C00000 0 .C00C00 .0 WSW .0000CC 00C000- .CC011P .0C0235 .000523 .000706 .000235 .000353 21 .002469 12.0 w .0000C0 .00CC00 .C00000 .0C0119 .000118 .C00588 .0C0470 .000000 11 001294 12.9 whw .C0C0C0 .0CC000 .0C0000 .0C0C00 .000582 .001999 .0000C0 .C00000 22 .002587 10.7 hw .000000 .000000 .CCCCCO .CC000C .000670 .C01294 .CCCCCC .000000 15 - .C017e4 10.6 Nhw .C0C000 .COCCCO .CCCC00 .0C0000 .000000 .. . C 0 C C C C .000000 .00CCCC C .0C0C00 .0 Hns 0 0 1 .I 19 40 6 3 72 FREG .000000 .00C000 .COC118 .000!5! .002234 .004704 .000706 .00C353 .006467 AVGSPD .0 .0 4.7 6.1 8.7 11.2 12.7 23.0 11.4 cs p

1 knot = 0.515 m/sec; 1 knot = 1.16 mph. 58 Qg Note: The frequencies of cale wines are given in tne 'irst wi90 speed colume. 3.0-0.7. ~h The .7 6not is tre steli speed cf the wind direction sersor, y ro -

TABLE 2.6-14 ANNUAL JOINT FREQUENCY OF WIND DIRECTION AND WIND SPEED FOR STABILITY CLASS B 11 CRBRP PERMANENT METEOROLOGICAL TOWER, 200-F00T LEVEL FEBRUARY 17, 1977 THROUGH FEBRUARY 16, 1978 WIND SPEED (KNOTS *)

                  .0-    .7       .8- 3.0        3.1- 4.8         4.9- 6.5          6.6-10.0 10.1-16.1 16.2-21.1 21.2-99.9 Mp5     FREQ AVG 5PD
 @e ".. . n-k          .000000         .000000          .000000           .000115          .000000      .000000  .CC0000  .000C00   1  .00G118         5.9 NNE         .COCCOC         .000000          .000112           .CC0000          .000000      .C00000  .000C0C  .0C000C   1  .00011!         6.7 ht        .00000C         .00C00C          .0000C0           .00C!5?          .000923      .000470  .000000  .GCC000  14  .CC1646         9.1 ENE         .000000         .000000          .COGC00           .CC0!5?          .000235      .000C00    000C0C .0000C0   5  .C00568         6.5 E         .G00:CC         .000000          .00C118           .CCC11P          .000235      .CCCC00  .00CCCD  .000C00   4  .000470         6.3 y    ESE         .00CCCC         .00 00C          .CCCCCC           .CCCCCD          . C 0 0118   .CCC00C  .CCCCCC  .000000    1 .0CC11?         9.4

, SE .00C00C .0 C000 .300000 .C00000 .000CCC .00000C .0C0000 .00C000 C .000CCO .0 b SSE 0000C0 .000CZ .C CCCC .CCCCC0 .;CC11? .000118 .DCCCCC .CCOCOL 2 .200235 9.3 5 . 0000C 300000 .;CCCCC . C C C C ;,0 .00C112 .30000C .0CCCCC .0000C 1 .20C118 7.6

                                                                                                                             ;                        9 SLw         .0000C0         .00C000          .000235           .CCGC00          .00:000      .CCCCCC  .000C0C  .CC0000      .0C0235         3.3 sw        .00000:         .000CGC           .0CCCCO          . 0 C C 1 15     .0007Ce      .000000  .0C0000  .C000CC   7  .0C0623         7.4 wsw         .COLOCC         .00G000           .00C235          .CC1411          .301764      .;C1:5E  .GCO!53  .00C470  45  .C0 52 92      10.0 m         .000000         .000000           .0CCCCC          .CC011'          .0CCP23      .C0105#  .00C235  .CCO235  21  .CC2469        12.6 WNw         .00CC00         .000000           .CCCC0C          .:Co0CC          .00C5EP       .CC1646 .0CC235  .CC000C  21  .002460        11.5 Nw        .00000C         .00COCC           .CC0C00          .CCC11E          .0C2117      .CC1529  .G00000  .0C0000  32  .003763         9.8 NNw         .C00000         .C00000           .GCCC00          .0C011'          .000235      .C00235  .DCCCCC  .000CC0   5  .000568         8.6 HES               C                0                e                ;4              e'          52         7       6  162 8sto         . COG 000       .C0CCCC           .CCC'05          .CO2?22          .007??9      .0C6115  .000223  .0007C6      .01905C avGspo             .0               .o             4.1               5.7              ?.3        12.0     18 2    22.6                        9.9 IN 3 (D

1 knot = 0.515 m/ sect I knot = 1.16 mph ES N B Nc te : Tr.e f-e;uencies c' tal* winds are given in the 'irst w$r.c speed coipr, 0.0-C.7, $

rt T r.e ' sect 's tne 4ta' spee: Of the wind dire: tier sensor. CO >s Nm O O O

h

-\

(O y /. TABLE 2.6-15 ANNUAL JOINT FREQUENCY OF WIND DIRECTION AND WIND SPEED FOR STABILITY CLASS C CRBRP PERMANENT METEOROLOGICAL TOWER, 200-F00T LEVEL FEBRUARY 17, 1977'THROUGH FEBRUARY. 16, 1978 11

                                                                                                    .JIND SPEED (KNOTS *)
                                          .0-   .7      .8- 3 0      3.1- 4.8         4.9- 6.5     6.6-10 0 10.1-16.1 16.2-21.1 21.2-99.9                        Has       FREQ AVGSPD N       .000000       .00G235        .CCC235          .000119      .000113             .CC0000          .000000         .000000     6  .COC706        4.3 hhE      .00G000       .000235        .CCl294          .300353      .000235             .C00353          .000000         .C000C0    21  .CC2469        5.2 NE      .0000CC       .000118        .002234          .002469      .003293             .00C470          .000000         .0000C0    73  .C08584        6.2 Eht       .0C0000       .00C118        .000061          .001294      .000706             .C000C0          .000000         .40CCCO    26  .CC3C57        5.3-E       .00C0C0       .00C0CC        .00C353          .0007C6      .000470             .000C00         . 0C0000         .00CCCC    13  .C01529        5.9 y                    E5E       .0C00CC       .000CCC        .000582          .CCC353      .000118             .C0000C          .000CG0         .CCCCCC     9  .C01058        4.7
        'm                      SE      .0000C0         000C00       .000118          .0CG119      .0C0118             .00C000          .00CC00         .00C00C     3  .G00353        5.7 b

55E .;0000C .00:2G0 .CCC11e .GCC470 .000582 . 000000 .00011! .G00C00 .11 .CC1294 7.5 5 .00CCCC 00C00C .;CC235 .000353 .000235 .00C112 .0C00C0 .C000CC- ! .C0C941' 6.8 Siw .C00000 .CCC000 .CCC235 .002353 .CC;?!3 .COCCCC .0CC0C0 .CCCCCO ! .CC09 1 5.2 g SW .00C0C0 .C00235 .C C C 9 41 .0C1o46 .001E61 0CG7C6 .000118 .000000 47 .C05527 7.1 W5W .000000 .00:0CC .CC2587 .CO2234 .002469- .C0152C .CCC235 .00CCCC 77 .CC9C55 7.3

                                .      .00G000        .CCC11P        .CCC706          .001055      .00C961             .C0070e          .00:11%         .000235    33  .003291        4.5 w%w       .C00000       .CCC00C        .0CC035          .0CC!t!      .G02940             .001646          .CCC235         .0C0C00    4E ~.G05644        9.0 hw      .0C0000       .00COLO        .00011?          .C057t e     .001499             .CC1294          .GCCCCC         .CCGCCC    35  .004116        9.0 N h '.    .0000CC       .COC000        .0CC!53          .CC011!        000???            .CCC23!          .DCOCCC         .00GCCC    1!  .001529        7.4 Hns            C             G             91             11C           147                 60                    7           2   431 FREC       .;0CC00       .;0105!        .011289          .012035      .017286             .C07C5e          .0C0223         .COC235        .05CeE2 AVGSPD           .0-          2.1            4.C              !.6          7.2                12.C             12.P            22.7                        7.1 IN

ro

1 Hot = 0.515 m/sec; 1 knot . 1.16 mph f.0:t 5ds ==

                                     %e deeLen;ie5 o' :airr .1635 a re gi ver. )r the 't est w nc $Deef CLI1'm. C.0-0

i

                                     %e ' eno: is :ne stal speec c' tne winc cirectice sen sor,-                                                                                                        h 11 - r+

to CC >< Nm

TABLE 2.6-16 AtlNUAL JOINT FREQUENCY OF WIrlD DIRECTI0tl AND wit 40 SPEED FOR STABILITY CLASS D CRBRP PERMANENT METEOROLOGICAL TOWER, 200_F00T LEVEL 11 FEBRUARY 17, 1977 THROL'GH FEBRUARY 16, 1978 WIND SPEED (Kt40TS*) 6.6-10.0 10.1-16.1 16.2-21.1 21.2-99.9 HR5 FREQ AVGSPD fyhy3 .0- .7

                                   .8- 3.0    3.1- 4.8    4.9- 6.5 N       .C000C0         .002469       .001176     .000588          .001058          .00000C   .000000   .000000      45   .005292         4.1 NNE       .C00000         .004821       .004468     .001294          .000941          .C00118   .000000   .000000      99   .011642         3.6 NE     .CCC000         .008819       .G16228      .007291         .009290           .G01529  .000000   .000000    367    .043156         5.0 ENE      .CCC000         .007173       .01C936      .0C9525         .007173           .000470  .000000   .000C00    300    .0!S278         4.9
                .0000CC         .G36937       .C06115      .001881         .00105F           .C00116  .0000C0   .000000    154     .016109        3.5 E
                .000000            002587     .006468      .C01411          .C00235          .C00000   .0CC000  .00000C      91   .010701         3.7 no      ESE
                 .000000        .001646        .002352     .0C0353         .000119           .CCCCCC  .000CCO   .000000      32   .004468         3.5 en        SE
                 .LOGC00        .003057       .004E21      .002469         .0C1294           .000470  .CCO353    .CCCCCO    1C6    .012465        5.1

[a SSE

                                 .001646       .005174      .005056         .005762          .CC2222   .000353   .00G235    179    .C21049        6.9 s       .000000
                                 .002822       .005409     .004116          .002E22          .00C223   .0C000C   .G00000    136    .015992        5.1     q ssw       .C00000                                                                                                                                  ~
                 .G00000         .C03281       .012562      .010563         .G13993          .CO3281   .000470   .G00C00    366    .045390        6.4 sw
                                 .005762       .015287      .008114         .008347           .CC6115  .001999   .00C823    395    .046449        6.9 wsw       .000000 m       .00C000         .005527       .007879      .002940         .003293            006585  .001058   .000223    239    .028104        7.3 WNw       .G00G00          .002222      .003175      .003645         .011524           .01C230  .0C1999   .000000    2 64   . 0 3 3 3'e s   8.8
                                                             .0C1999         .006938          .00446e  .0CC823   .000000    1E1    .021284        7.5 Nw      .CCOCCO         .002940      .0C6116
                  .00CC00         .002117      .001646      .001764           002705          .000235  .000C00     000000      72  .00P467         5.3 NNw hrs              0           570          917          536             651               322        60        to  3072
                                  .067027       .107832      .C63029         .076552          .CI7865   .007056   .0018E1           .361242 FREQ         .0000CC 2.2          3.9          5.6             8.0              12.3      17.8     23.4                            6.0 AVGSPD              .0 S$

Ea

1 knot = 0.515 m/sec; kr.ot
1.16 mph gg

                                                                                                                                                            %c m the first wir,c s:4e c e l u- r. . 0.5-C.7.                                                           3
     'ete: The frehencies cd calm winds are tiiver t r.                                                                                                Il      et The .7 Mot is tnt stall speec c' t u .inc cirectior senso*.

b O O e

Amendr.ent XI

                                                                                                ,                                             January 1982

' A / \ t i 'h%j .-e

                                                                                                                                                               ,-4 C3 i A 1@ O              P*   4          4 O N N                   m        N w N                   so e p .            e    e       O.         e o      e O. e.       e N. e .      e             e d3m 6 9 M N 4 4 M m M 4 e en en en en 4 en M                                                  4 at 6 e 4 en m P6 4 4 4 e                       P=   4   *O en d O so                 4 GG@            p 4 @          4 en en           m 4 en O O Pm 4 m                          4 w 40                e=   c ** O O           P.== c m P6      eo .= es e O                 4 m i N         &.* en e .- *- en en 4                   m N e Pm en @                      4 em OO          e-    N fw N ** O O *=               N. P4 er) N- *= - O e                                     e t1 O                   O            O O O. O. O. e         e O. O. O.         e O. C.L e       e   O. O. O.           N.

gg a I 93 N d N O # m 4 e en N @ N N .r1 @O O '

O ** * ' * *
O ' N ** ""
g "z e e N N e- ."- O.- N N' N .- .- N

                         -J CD         LAJ                        e LAJ        >                  &. 9 O O O O O O O O u O O O en O O O 4 O O O O O O O O O O O O m o g3 O m

LAJ LAJ (e* org CL J O 8 O O O O O O u O O O O O N O O O N N en W (Q 0 0 0 O O O O O O O O O O O O U O L3 O e p g N 0 O O O O O O O O O O u O O fl O O OM Q O O * ' O O O O O O O O C3 E O O O O O N M OM L.A. 3 e a e- e O@ . I O O O O O O O e o re isJ O eo O & Q O .-. *- eQ O O O O u O a.u

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C.3 e O. O e O. e-g J . - . *-e J I LAJ O e c CO 3 JO P CL e ee er> eo N o e to e en so o en P. O e- e en 4 - Cf W O e& eo e o O O .= 0 P6 en m e- o .o ao O N -6 H L L. CD O IN *- 8 N in e N P* A e- N .= Q & e- o es as P- e e o 8 O < w rN O s t - O e e O O O O m .= ,a e en en m O O P. e H H @ @ l O O O O O O O O O O O O O O O O d 4 A y y g La,j ,, .Z. . 8 O. O. O. O. O. O. O. O. O O e o g 3 e j O. O. O. O. e e O. O. O. gg z . o W H b g o Z - c. e. . O N e to e e o. O - e - . o - en ;* CT LAJ 4 4 a3 O *= N P= en r= 0 4 4 N en en & c en M LAJ Z >= 0 are N J en .= 0 ** P6 @ @ e2 M O 4 ore e M @ $h cr < ce e O - m en - - O O N N 4 O.n ,s - N O ~ to . 6-L.L. E < o eO O O O O O O O u o s; O O O O O m m en g ** gg 3

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I

Amendment XI e January 1982

                                                                                                                    ~ . - ~
                                                                                                                                                      -4 O 8 IL I ene Oo ese ae m o a N oe me Me 4 o N so tn i e P. P%      N             N e    o     e   o       e              e o eN N N m N                   p.    ,e   ,. N m m n N N N N                                       cy 3m 8 4 9 N eO en *= a) u se               =#   ee iO m C3 c O N m3                           P.

O l 50 u M *= wt N w e= Pm ere 4 N Pe. 4 4 N e3 w $ Ph 4 P ** P= e0 4 *- ** O @ ert a0 M 4 en Ok M l en Pm N 4 m o =0 eo & Pw 7% @M 40 ao M N

4 O O *- == e- O O O O O O e- e- O O O en Oe O oO Oe Oe O eO Oo O e O oO Oe O e O O Oe e=

o e e o e e M 8 @ M O O P6 as en G m) O en o so e- N O e-E E 8 4 @ ** N o- en e e Pw 4 e *= Pm em M O O I I e- e e ,io. e m L.L. ** J Q LAJ

I y >
8 O O O O O O O O O O O O O O O O O' 8 u O O O O O O O O O O O O Q O O O

y y O g @ 8 O O O O O O O O O O O O O O O O O O O W I I O O O O O O O O O O O O O O O O O e W N O O O O O u O O O O O O O O O O O O O O Ch *

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4 I Q I 8 O O O o O u O O O O O O O O O O e 8 o O O O O O O O O O O O O O O O O

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                 *-* D              e 8 O O e O O O O O Oe O O O O O O O O                                                     O e                -

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            ,e   g           w    O 9 m *= m en              e- O O O en O N e O N m m
                                                                                      =0 M 4 e m en e                          ai O                g p_   g g g s                     *- t N ** N O *= 0 O O M e                              2 Pm N a3 N N m o                           @           q 4 y g g                 i 8 O O O             e-  O O O O O O sJ                    e-    O O O O 4 Pm                      e b H O -.          *~

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       -)        Z      ,4          e 0 0 O         e- =#    e o as en en O 4 o c a; e a3                                      r-                 fe 1,.

I (y w 4 5 N O *= 4 O O == M M 0 4 O P* Pm & N *- O e P- O ** N N 4 *= 0 ** ** N O g w y =# P= e- *= P* en .' g Qg i i O O e- *= 0 O O O O O e- = e O O O & O e s k *s

                   '              & 0 0 0 O O O O O O O O O O O O u u                                                          e-    e          ;- *;

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i m3 0 O O O O *- O O O O O O e- O O O O O O *= - ~= ?' ' '
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0 50 to u en O O O en m O at M O O en O e E 7,
s- - O m O O O M e u - e o o - O 4 m t .

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F 9 . L . 0 0 0 0 0 0 0 0 0 0 0 G C 0 0 C 0 D E 9 . 0 0 0 0 0 0 C 0 0 C 0 0 C 0 0 0 0 E V 9 . 0 0 0 0 0 0 0 0 0 0 0 0 C 0 0 0 0 0 0 E E - . 0 0 0 0 0 0 0 0 0 C 0 0 C 0 0 0 0 P 2 . 0 0 0 0 0 0 0 0 0 0 0 0 C 0 0 0 0 L 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 8 1 C. C. _ T 7 2 . D 0 9 N 0 1 1 I F 0 0 0 0 0 0 0 C 0 0 0 0 0 0 0 0 0 W - , 1 2 C 0 0 C C 0 C 0 0 0 0 C 0 0 0 0 0 0 0 0 0 C 0 0 C 0 0 0 0 0 0 C 0 0 0 0 0 6 - 0 0 0 0 0 0 0 0 C 0 0 0 0 0 0 C 0 D 0 1 2 0 C 0 0 0 0 0 0 C 0 0 C C 0 0 0 0 N 2 . 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 A Y 6 . G. G.

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       - R A L                N     . 0        0 0 0 0                 0 0 0 0 0 0 0 0                      0   1 6        L A H K                      C.                  C. _ C.

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                                    . 0 0 3 6 8 3 8 9                  3 0 4 4 6 8 8 0                      1 e

r 0 . 0 0 2 0 1 1 1 1 5 7 9 6 7 1 1 0 9 L I I B W L O T P L H E 1 . 0 0 5 7 1 1 1 1 3 4 2 7 1 1 1 0 2 2 6 ac A I R S - . 0 0 0 0 0 0 0 0 0 0 1 1 1 0 0 C 6 7 6 . 0 C 0 0 0 0 0 0 0 0 0 0 0 0 0 C 0 7 T F B O 7 . 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 c. O A E 7 D 6 . G. e T T 9 N . sr.o p Y S E 1 I es C M W 5 . ,n n N , . 0 0 6 2 3 0 0 0 2 9 4 C 6 3 5 8 4 e 6 0 7 2 2 0 0 0 1 2 6 4 2 3 6 .s E T 7 0 1 1 U N 1 0 0 1 2 2 C 0 C 1 5 7 4 6 2 2 1 ! 4 5 t n Q E - . C 0 1 2 0 0 0 0 0 1 1 3 1 C 0 0 2 4 4s,tio E N Y 9 . 0 0 C C 0 0 0 0 C 0 0 O 0 0 0 0 1 1 5

                                    . 0 0 0 0 0 0 0 0                      0 0         0 0 0 0              0               < c R       A R           4 .                                    C.          C.                                               e F       M A               .                                                                                        ,. r$

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w./ l TABLE 2.6-21 l11 MONTHLY WIND DATA CRBRP Meteorological Tower *+ Oak Rid;e City Office

Kr. w ille Airport ** Area Station X-10I 33 Foot level 200 foot Level Average Average Average Average Average Speed Prevailing Speed Prevailing Speed Prevailing Speed Prevailing Speed Prevailing

             !!onth         (xch)_ _  Direction    _,(Eph)    Direction _     (rph)      Dire: tion  (eph)    Direction       (mph)     Direc,+1on January              4.8          SW          8.2          NE           5.3         SSW       4.5         WNW          7.5          WNW Fe::ruary            5.0        ENE          8.7          NE           6.0         SSW       4.4         WNW          7.5           NE
          ' arch              5.3         SW          9.2          NE           6.8         WSW       4.3          SSE         7./          WSW April                 5.7         SW          9.3        WSW            7.0         SSW        3.7        WSW          5.9          WSW
         !!ay                 4.5         SW          7.4          SW           6.2           :E      2.8          ENE         4.4           NE 8

1 Jane 4.2 SW 6.7 SW 6.4 WSW 3.3 SW 5.3 WSW i J;1y 3.9 SW 6.3 WSW 4.2 SSW 2.8 WSW 4.! WSW 2.6 4.1 WSW 9

-       Aegust                3.7          E          5.7          NE           1.5         SSW                     SW Septe.-ber           3.8          E          5.9          NE           2.9         NNE       2.4            E         4.1           NE Cctober              3.6          E          5.9          NE           2.9         NNE        3.0        WNW          4.8          WSW

f. oven er 4.1 E 7.2 NE 3.2 N 3.3 WNW 6.0 ENE Cece-ber 4.5 SW 7.6 NE 4.3 NNE 4.0 WNW 6.8 WSW Annual 4.4 SW 7.3 NE 4.7 SSW 3.5 WNW 5.6 WSW

              *16 , year recced on wind speed,13-year record on prevailing direction I4)
            "31-year record on wind speed,14-year record on prevailing direction (3)
              +1-year record (26) (102 feet, sensor elevation)                                                                                        a
            ++1-year record, February 17, 1977 - February 16, 1978                                                                                    $

C 3 CJ CL 7 3

                                                                                                                                                      % rD
                                                                                                                                                      ~5 m

CO X Nm

Amendment XI January 1982 TABLE 2.6-22 MONTHLY AVERAGE RELATIVE HUMIDITY VALUES (3) FOR KN0XVILLE AIRPORT 1961-1973 Relative Humidity at Indicated Time (E.S.T.) Month 0100 0700 1300 1900 Average January 76 79 63 64 71 February 71 77 60 59 67 March 69 78 54 54 64 April 70 78 51 52 63 11 May 77 83 54 56 68 June 84 88 59 62 73 i July 86 90 62 66 76 ! August 87 92 61 66 77 ) September 86 91 58 66 75 ! October 83 88 55 62 72 November 78 83 59 65 71 l December 76 80 64 67 72 Year 79 84 58 62 71 l O l 2.6-42 l t I

Amendment XI January 1982 O'# TABLE 2.6-22A 11 MONTHLY AVERAGE RELATIVE HUMIDITY VALUES FOR THE CRBRP SITE FEBRUARY 1977 - FEBRUARY 1978 Relative Humidity Month in Percent (%) February 60 March 64 April 69 May 77 g June 77 July 77 August 81 September 86 October 80 November 80 December 74 January 75 Annual Average 75 l. O 2.6- 43

TABLE 2.6-23 l 11 FREQUEtiCY DISTRIBUTI0tl 0F RELATIVE HUMIDITIES ACCORDIt1G TO AMBIEtiT TEMPERATURES FOR BULL RUN STEAM PLAtlT Temp., 55 65 75 85 93 97 100 15 25 35 45

      *F         5 0.01   0.01  -0.01   <0.01   -0.01   0.01
                      <0.01  <0.01  <0.01    <0.01   <0.01
      -25      <0.01
                                                              <0.01  <0.01  <0.01   <0.01   <0.01   0.01
               <0.01  <0.01  <0.01  <0.01    <0.01   <0.01
      -15
                                                              <0.01  <0.01  <0.01   <0.01   <0.01   0.01
                      <0.01  <0.01  <0.01    <0.01   <0.01
         -5    <0.01 0.08   0.12   0.09     0.02   0.03   0.05
               <0.01  <0.01  <0.01  <0.01    <0.01   <0.01 5

0.29 0.12 0.01 0.01 0.01

                      <0.01   0.01  <0.01     0.14    0.30     0.40 m      15    <0.01 1.08   1.00   0.72    0.16    0.05   0.04
               <0.01  <0.01  <0.01   0.15     0.57    0.96 25
  $                                                            0.98    1.42   1.19    0.22    0.10   0.07
               <0.01  <0.01   0.01   0.20     0.43    0.76 32 1.20   1.46   1.48    0.31    0.09   0.06
               <0.01  <0.01    0.05  0.32     0.51    0.78 37 2.44   2.81   3.91    1.38    0.81   0.29
                      <0.01    0.20   0.78     1.40    2.01 45   <0.01 1.86   2.55   3.92    2.49    1.35   0.59
               <0.01    0.01   0.31   1.00     1.46    1.74 55 2.25   3.58   7.14    3.26    2.13   0.84
                <0.01   0.01   0.38   1.00     1.27    1.64 65 4.00   4.67     1.54   0.45   0.21 0.02   0.23   0.69     0.97    2.07     3.23 75     0.01 1.01   0.10    0.01    0.01  <0.01 0.03   0.26     0.82    2.15     2.4a 85     0.02  <0.01 0.02   0.01  <0.01   -0.01    0.01  <0.01
                       <0.01  <0.01   0.02     0.05    0.11 95    <0.01
                                                               <0.01  <0.01  <0.0'     0.01  -0.01  <0.01 ETF 0.01   <0.01 105    <0.01  ~0.01  <0.01  <0.01                                                                 Ea
                                              <0.01    0.01    <0.01  <0.01    0.01  <0.01     0.01 <0.01  g g.
                <0.01  <0.01  <0.01  <0.01 115                                                                                              *8 G"

Rsd O O e t- - .

s y) Amendment XI January 1982 TABLE 2.6-24 l 11 PRECIPITATION DATA 0AK RIDGE AREA STATION, X-10(l) 1944-1964 Monthly Monthly Monthly Maximum Average

Maximum Minimum in 24 Hours Month (inches) (inches [ (inches) (i nches)

December 5.22 10.28 1.98 4.23 January 5.24 12.37 1.11 3.96 February - 5.39 10.01 1.89 3.23 Winter 15.85 f~'N C/ March 5.44 9.69 2.06 3.84 April 4.14 8.54 1.25 2.39 May 3.48 7.01 0.90 2.09 Spring 13.06 June 3.38 7.55 1.18 3.08 July 5.31 10.19 2.14 3.74 August 4.02 10.31 0.50 3.31 Sumer 12.71 September 3.59 12.84 0.21 7.75 October 2.82 6.43 0.00 2.32 November 3.49 12.00 1.01 3.20 Fall 9.90 Annual 51.52 12.84 0.00 7.75

Standard climatological normals (1931-1960)

IA) '% J 2.6- 45

                                                                          .~ -

Anendment XI January 1982 TABLE 2.6-24A PRECIPITATION DATA FOR THE CRBRP SITE FEBRUARY 1977 - FEBRUARY 1978 Precipitation Month in Inches February 1.44 March 4.81 April 6.95 May 1.36 9 June 3.55 July 1.01 August 4.22 September 8.96 October 4.36 November 6.55 December 3.37 January 5.21 Annual total 51.79 l l O 2.6-46

4 i } i Amenduent XI i January 1982 4 TABLE 2.6-25 l 11 i l SNOW AND ICE PELLET DATA FOR 0AK RIDGE CITY OFFICE I4) f 1943 - OCTOBER 1974 ,4 I l Snow, Ice Pellets (inches) f Mean* Maximum Maximum In ! Month Total Monthly 24 Hours ! i January 3.2 9.6 8.3 l February 2.9 11.3 9.1 March 1.5 21.0 12.0 April T 0.3 0.3 May 0.0 0.0 0.0 L June 0.0 0.0 0.0 > luly 0.0 0.0 0.0 August 0.0 0.0 0.0 September 0.0 0.0 0.0 l October T T T ; November 0.5 6.5 6.5 , December 2.2 14.8 10.8 i Year 10.3 21.0 12.0 ! Maximum Annual 41.4 inches (1959-1960 snowfall season) ; i

                                                            *1949-1973 T = Trace                                                                                                   ,

i-9 l 2.6-47 8'

t TABLE 2.6-26 l 11 MONTHLY MEAN NUMBER OF HEAVY F0G DAYS FOR KN0XVILLE

AND 0AK RIDGE CITY OFFICE Foq Days (mean number) Jan. Feb. Mar. Apr. May Jun. Jul. Aug. Sept. Oct. Nov. Dec. Annual Knoxville 3 2 1 1 2 2 2 3 4 5 3 2 31 Oak Ridge 1 1 1 1 2 2 3 4 4 8 6 2 34

                                   ?
                                  $

Visibility less than 1/4-mile

                                                                                                   **31-year record (1943-1973)(3)
                                                                                                    +14-year record (1951-1964)(4)

E;" E Ee 4& i wg

                                                                                                                                                                                                 $5 l

l ! O O O

/~'t Amendment XI bl January 1982 TABLE 2.6-27 l 11 F0G OCCURRENCE DATA LISTING MEAN NUMBER OF DAYS FOR JANUARY 1964 THROUGH OCTOBER 1970(24) (Visibility Less Than Stated Value) Melton Hill Lake at Bull Run Creek, Melton Hill Lake at Dam, Clinch Rivr. Mile 46.4 Clinch River Mile 23.1 Month <l100 yards <550 yards <1100 yards <550 yar January 3.08 2.00 4.46 4.31 February 3.29 1.57 5.00 4.29 March 1.86 1.14 5.14 4.14 rm April 2.29 0.86 6.00 4.86 'v May 5.86 3.71 8.43 7.14 June 6.71 3.29 11.71 9.86 July 12.29 7.43 12.57 10.14 August 14.71 9.42 14.14 12.43 September 13.43 7.56 16.00 15.00 October 10.00 8.43 14.86 14.00 November 11.00 6.17 12.83 12.17 December 6.00 2.84 8.33 7.67 Annual 90.52 54.42 119.47 106.01 v 2.6-49

Amendment XI January 1982 . TABLE 2.6-28 O l 11 NUMBER AND PERCENT OCCURRENCE BY MONTHS OF THE PASQUILL STABILITY CLASSES A-G USING THE CRBRP PERMANENT TOWER DATA l 11 Stability Classes A B C D E F _G Ma rc h Number 2 9 37 249 165 69 208 1977 Percent 0.27 1.22 5.01 33.69 22.33 9.34 28,15 April Number 19 20 24 235 156 67 194 1977 Percent 2.66 2.80 3.36 32.87 21.82 9.37 27.13 May Number 1 13 44 253 158 143 128 1977 Percent 0.14 1.76 5.95 34.19 21.35 19.32 17.30

 . lune      Number      17      21        51       196     153      82       95 1977        Percent      2.76     3.41     8.29     31.87   24.88   13.33     15.45 July        Number       3      14        82       241     114     175       67 1977       Percent      0.43     2.01    11.78     34.60   16.38   25.14      9.63 August      Number       1      11        40       245     185     175       76           9 1977        Percent      0.14     1.50     5.46     33.42   25.24   23.87     10.37 September Number         0        2       17       239     241     176       4.

1977 Percent 0.0 0.28 2.37 33.38 33.66 24.58 5.73 October Number 6 14 37 205 227 148 101 1977 Percent 0.81 1.90 5.01 27.78 30.76 20.05 13.68 November ' lumber 3 14 19 276 218 84 106 1977 Percent 0.42 1.94 2.64 38.33 30.28 11.67 14.72 December Number 3 11 26 287 232 91 78 1977 Percent 0.41 1.51 3.57 39.42 31.87 12.50 10.71 January Number 14 23 24 364 239 44 36 1978 Percent 1.88 3.09 3.22 48.92 32.12 5. 91 4.83 February Number 3 10 30 283 161 47 87 1978 Percent 0.48 1.61 4.83 45.57 25.93 7.57 14.01 Annual

Number 72 162 431 3072 2249 1301 1217 Percent 0.85 1.90 5.07 36.12 26.46 15.30 14.31 oNkruary 17, 1977 - February 16, 1978 2.6-50 L

Amer:dment XI January 1982 n TABLE 2.6-29 l 11 FIFTIETH PERCENTILE x /Q VALUES FOR VARIOUS DOWNWIND DISTANCES 33-FT WIND SPEED AND DIRECTION: 200-FT TO 33-FT DELTA T DATA FROM FEBRUARY 17, 1977 THROUGH FEBRUARY 16, 1978 Distance 50th Percentile x/Q Values (sec/ma ) (miles) 2-hr 8-hr 16-hr 72-hr 624-hr 0.1 1.02E-2 1.50E-3 1.60E-3 9.72E-4 1.16E-3 0.2 3.07E-3 4.53E-4 4.61E-4 2.82E-4 3.35E-4

0. 3 1.53E-3 2.45E-4 2.21E-4 1.37E-4 1.62E-4 0.34 1.22E-3 1.94E-4 1.75E-4 1.0SE-4 1.28E-4 0.42 1.01E-3 1.55E-4 1.23E-4 7.69E-5 9.06E-5 0.5 S.25E-4 1.27E-4 9.28E-5 5.78E-5 6.76E-5 0.6 7.16E-4 1.07E-4 6.91E-5 4.30E-5 5.02E-5

,- 0.7 6.19E-4 9.29E-5 5.43E-5 3.36E-5 3.93E-5 '/ i_ s 1.0 4.29E-4 6.51E-5 2.70E-5 1.67E-5 1.93E-5 1.5 2.81E-4 4.30E-5 1.07E-5 6.69E-6 7.73E-6 2.0 2.08E-4 3.03E-5 5.61E-6 3.50E-6 4.06E-6 9 2.5 1.59E-4 2.30E-5 3.58E-6 2.29E-6 2.60E-6 3.0 1.26E-4 1.83E-5 2.58E-6 1.60E-6 1.85E-6 3.5 1.03E-4 1.49E-5 1.96E-6 1.19E-6 1. 60 E-6 4.0 8.69E-5 1.24E-5 1.55E-6 9.35E-7 1.11E-6 4.5 7.49E-5 1.09E-5 1.26E-6 7.66E-7 9.06E-7 5.0 6.58E-5 9.46E-6 1.06E-6 6.42E-7 7.64E-7 7.0 4.21E-5 6.04E-6 5.87E-7 3.66E-7 4.32E-7

7. 5 3.90E-5 5.57E-6 5.28E-7 3.30E-7 3.88E-7 9.0 3.07E-5 4.44E-6 4.27E-7 2.65E-7 3.10E-7 10.0 2.73E-5 3.99E-6 3.77E-7 2.31E-7 2.72E-7 15.0 1.70E-5 2.46E-6 2.28E-7 1.36E-7 1.63E-7 20.0 1.21E-5 1.76E-6 1.56E-7 9.47E-8 1.14E-7 21.0 1.14E-5 1.66E-6 1.47E-7 8.91E-8 1.07E-7 25.0 9.26E-6 1.34E-6 1.17E-7 7.22E-8 8.67E-8 (h

x_ ,/ 35.0 6.43E-6 9.33E-7 7.98E-8 4.89E-8 5.82E-8 45.0 4.88E-6 7.60E-7 5.89E-8 3.71E-8 4.37E-8 50.0 4.32E-6 6.25E-7 5.16E 8 3.29E-8 3.90E-8 2.6-51

TABLE 2.6-30 ANNUAL AVEUGE X/Q'S (in sec/3) AT VARIOUS DOWNWIND DISTANCES FOR EACH WIND SECTOR 11 Downwind Distance Wind _Qi.tettion e (milesL N NNE hE ENE E E5E SE SW $ 5fW SW MW W Wu % hw 0.1 2.95E-4 3.40E-4 4.20E-4 6.23E-4 8.05E-4 6 60E-4 1.29E-3 9.29E-4 2.51E-4 2.21E-4 3.91E-4 5.13E-4 6.57E-4 7.58E-4 4.88E-4 3. 69E-4 0.2 8.44E-5 9.78E-5 1.21E-4 1.80E-4 2.32E-4 1.91E-4 3.74E-4 2.68E-4 7.22E-5 6.38E-5 1.12E-4 1.47E-4 1.89E-4 2.18E-4 1.40E-4 1.06E-4 0.3 4.18E-5 4.84E-5 5.99E-5 8.88E-5 1.15E-4 9.34E-5 1.83E-4 1.32E-4 3.58E-5 3.15E-5 5. 61 E- 5 7.34E-5 9.31E-5 1.07E-4 6.89E-5 5.21E-5 0.34 3.35E-5 3.86E-5 4.78E-5 7.08E-5 9.08E-5 7.39E-5 1.44E-4 1.04E-4 2.85E-5 2.51E-5 4.50E-5 5.88E-5 7.40E-5 8.55E-5 5.49E-5 4.16E-5 0.42 2.43E-5 2.77E-5 3.42E-5 5.06E-5 6.47E-5 5.24E-5 1.02E.4 7.41E-5 2.05E-5 1.79E-5 3.25E-5 4.2SE-5 5. 30E- 5 6.12E-5 3.95E-5 2.99E-5 0.5 1.86E-5 2.10E-5 2.59E-5 3.81E-5 4.88E ' 3.92E-5 7.59E-5 5.57E-5 1.56E-5 1.35E-5 2.47E-5 3.24E-5 4.03E-5 4.63E-5 2.93E-5 2.27E-5 0.6 1.41E-5 1.58E-5 1.94E-5 2.85E-5 3.64E-5 2.92E-5 5.62E-5 4.14E-5 1.18E-5 1.01E-5 1.86E-5 2.44E-5 3.02E-5 3.47E-5 2.25E-5 1. 71 E-5 0.7 1.12E-5 1.25E-5 1.53E-5 2.24E-5 2.86E-5 2.89E-5 4.39E-5 3.25E-5 9.28E-6 7.92E-6 1.47E-5 1.93E-5 2.39E-5 2.74E-5 1.79E-5 1. 36E-5 1.0 5.49E-6 6.03E-5 7.41E-6 1.03E-5 1.37E-5 1.10E-5 2.11E-5 1.56E-5 4.46E-6 3.80E-6 7.04E-6 9.31E-e 1.16E-5 1.33E-5 8.79E-6 6.65E-6 1.5 2.32E-6 2.45E-6 2.97E-6 4.24E-6 5.39E-6 4.33E-6 8.20E-6 6.19E-6 1.81E-6 1.49E-6 2.81E-6 3.77E 6 4.73E-6 5.37E-6 3.66E-6 2. 76 E-6 CS e 2.0 1.13E-6 1.24E-6 1.52E-6 2.22E-6 2.81E-6 2.30E-6 4.41E-6 3.23E-6 9.07E-7 7.77E-7 1.42E-6 1.83E-6 2.39E-6 2.74E-6 1.84E-6 1.38E-6 $ 2.5 7.07E-7 7.77E-7 9.56E-7 1.39E-6 1.78E-6 1.46E-6 2.82E-6 2.05E-6 5.10E-7 4.89E-7 8.82E-7 1.18E-6 1.51E-6 1.73E-6 1.16E-6 8.70E-7 3.0 4.97E-7 5.5.E-7 6.80E-7 3.96E-7 1.27E-6 1.05E-6 2.03E-6 1.47E-6 4.06E-7 3.50E-7 6.27E-7 8.36E-7 1.07E-6 1. 23 E- 6 8.18E-7 6.15E-7 3.5 3.70E-7 4.13E-7 5.09E-7 7.47E-7 9.56E-7 7.89E-7 1.53E-6 1.11E-6 3.04E-7 2.62E-7 4.67E-7 6.23E-7 8.04E-7 9.21 E-7 6.12E-7 4.60E-7 4.0 2.91E-7 3.26E-7 4.02E ' 5.91E-7 7.39E-7 6.27E-7 1.22E-6 8.79E-7 2.40E-7 2.06E-7 3. 68E-7 4.90E-7 6.35E-7 7.26E-7 4.8?t-7 3.62E-7 4.5 2.36E-7 2.65E-7 3.'6E-7 4.80E-7 6.18E-7 5.11E-7 9.97E-7 7.16E-7 1.95E-7 1.69E-7 2.97E.7 3.97E-7 5.17E-7 5.92E-7 3.92E-7 2. 94 E-7 5.0 1.97E-7 2.22E-7 2.73E-7 4.03E-7 5.20E-7 4.31E-7 8.42E-7 6.03E-7 1.63E-7 1.42E-7 2. 4 9E-7 3.32E-? 4.34E-7 4.97E-7 3.28E 7 2.46E-7 7.0 1.08E-7 1.23E-7 1.52E-7 2.25E-7 2.93E-7 2.43E-7 4.79E-7 3.40E-7 9.10E-8 7.95E-8 1.37E-7 1.83E-7 2.42E-7 2.77E-7 1.82E-7 1.36E-7 7.5 9.66E-8 1.11E-7 1.37E-7 2.03E-7 2.63E-7 2.19E-7 4.32E-7 3.07E-7 8.18E-8 7.15E-8 1.23E-7 1.64E-7 2.17E-7 2.49E-7 1.63E-7 1.22E-7 9.0 7 59E-8 8.76E 8 1.08E-7 1.61E-? 2.10E-7 1.75E-7 3.46E-7 2.45E-7 6.48E-8 5.68E-8 9.67E-8 1.29E-7 1.72E- 1.98E-7 1.29E-7 9.67E-8 10.0 6.60E-8 7. 64 E-8 9.42E-8 1.40E-7 1.84E-7 1.53E-7 3.04E-7 2.14E-7 5.65E-8 4.97E-8 8.41E-8 1.12E-7 1.50E-7 1.72E-7 1.12E-7 8.4 5 E-b 15.0 3.81E-8 4.47E-8 5.53E-8 8. 27 E- 8 1.09E-7 9.14E-8 1.82E-7 1.27E-7 3.31E-8 2.93E-8 4.88E-8 6.52E-8 8.83E-8 1.01E-7 6.54E-8 4.92 E-8 20.0 2.61E-8 3.10E-8 3.83E-8 5.75E-8 7.61E-8 6.40E-8 1.28E-7 8.92E-8 2.30E-8 2. 34 E-8 3.37E-8 4.49E-8 6.14E-8 7. 04 E-8 4.52E-8 3.40E-8 21 0 2.45E-8 2. 91 E-8 3. 59E -8 5.40E-8 7.15E-8 6.02E-6 1.20E-7 8.38E-8 2.16E-8 1.92E 8 3.15E-8 4.21E-8 5.76E-8 6.61E-8 4.25E-8 3.19E-8 25.0 hy 1.95E-8 2 33E-8 2.88E-8 4.34E-8 5.76E-8 4.85E-8 9.74E-8 6.76E-8 1.73E-8 1. 54 E-8 2.52E-8 3.37E-8 4.63E-8 5.31E-8 3.40E-8 2.56E-8 35.0 1.27E-8 1. 54 E-8 1.902-3 2.88E-8 3.86E-8 3.25E-8 6.57E-8 4.54E-8 1.15E-8 1.03E-8 1.66E-8 2.21E-8 3.06E-8 3.52E-8 2.22E-8 1.68E-8 5@ 45.0 yQ 9.31E-9 1.14E-8 1.41E-8 2.14E-8 2.89E-8 2.43E-8 4.93E-8 3.39E-8 8.54E-9 7.67E-9 1.22E-8 1.63E-8 2.28E-8 2.61E-8 1.64E-B 1.24E-8 k@ 50.0 8.23E-9 1. 02 E-8 1.25E-8 1.91E-8 2.58E-8 2.17E-8 4.41E-R 3.03E-8 7.61E-9 6.84E-9 1. 08E-8 1.44E-8 2.02E-8 2.32E-8 1.45E-8 1.10E-8 gr+ an< Nw

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Amendment XI l January 1982 2.0 2.5 N 2.2 NNW 7 NNE 12 3.7 NW NE 4.0 * , 2.7 WNW ENE 3 3.1 W - Mm 3.2 MM E 2.1 9 l WSW ESE 4.0 1.8 SW - SE 4.2 1.4 SSW SSE 2.9 S 2.7 2.8 *

             *Value denotes average wind speed for each sec*c .                                                                                              l 11 Figure 2.6-4                       ANNUAL WIND ROSE FOR THE 33 FOOT LEVEL FROM CRBRP PERMANENT METEOROLOGICAL TOWER DATA                             l11 FOR FEB. 17, 1977 THROUGH FEB. 16, 1978 2.6-56

[ Amendment XI January 1982 O l 1.6 l

1.9 N 2.0 '

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                                                                                 ^            NNE
                                        $2 2.7 NW NE g

> 6 i 2.6 i 5.4 ENE WNW 3 i 1 4.2 W -MM l.1 M E 1.8 (. 9 t WSW ESE 5.5 2.0 I I SW SE 6.0 1.3 SSW .- SSE 3.6 S 3.0

3. 3

j *Value denotes average wind speed for each sector. l11 Fiqure 2.6-5 WINTER WIND ROSE FOR THE 33-F00T LEVEL FROM CRBRP PERMANENT METEOROLOGICAL TOWER DATA l11 2.6- 57

Amendment XI January 1932 0 1.6 3.3 N 1.9 NNW NNE 12 43 2.7 NE 9 6 4.0 2.7 WNW ENE 3 3.1 W - EMM 3.4 MM E 2.2 O i 9 WSW ESE 4.3 2.0 SW SE 4.6 1.5 SSW SSE 3.1 S 3.6

3. 2 *

                 *Value denotes average wind speed for each sector.                                                          Ill Figure 2.6-6         SPRING WIND ROSE FOR THE 33-F00T LEVEL FROM CRBRP PERMANENT METEOROLOGICAL TOWER DATA                   l11
                                                                    ?.6-58

Amendment XI January 1982 O i 1.9 2.4 N 2.3 N NNE l2 3.0 3.0 NW NE 9 i 3.2 2.7 WNW ENE i 3 2.5 W - IM 44 MMI E 2.2 9 ESE WSW I' 3.4 l ! SW SE 1.3 2.9 l SSw SSE 2.3 b 2.0

2. 6 *

                         *Value denotes averar? wind speed for each sector.

O Figure 2.6-7 SUMMER WIND ROSE FOR THE 33-F00T LEVEL FROM CRBRP PERMANENT METEOROLOGICAL TOWER DATA l11 2.6- 59

Amendaent XI January 1982 0 1.9 2.4 N 2.3 NNW NNE 12 3.0 3.0 NW g NE 6 3.2 2.7 WNW ENE 3 s i

2. 5 W -

M 4.4 MM E 2.2 l

                                                                                                                                                                 '9 WSW,                                                                                                                                ESE 1.7 3.4 SW                                                                                       SE 2.9                                                                                                 1.3 SSW                                           SSE l

2.3 S p. 3

2. 6

l11

                *Value denotes average wind speed for each sector.

Figure 2.6-8 FALL WIND ROSE FOR THE 33-F00T LEVEL O , FROM CRBRP PERMANENT METEOROLOGICAL TOWER DATA l11 2.6-60

Amendment XI January 1982 O 3.4 4.1 2.9 N 6.1 NW 4.5 l 9 i G 7.2 4.3 WNW ENE 3 i 5.6 W - MM .47 MIE E 7.9 i 9

ESE ;

WSW 3.1 5.6 SW SE 5.8 2.6 SSW SSE 4.5 S 3.9

5. 3 *

Valse denotes average wind speed for each sector. l11 Figure 2.6-9 O ANNUAL WIND ROSE FOR THE 200-F00T LEVEL FROM THE CRBRP PERMANENT METEOROLOGICAL TOWER DATA FOR FEB.17,1977 THROUGH FEB. 16, 1978 l11 2.6-61

l Amandment XI January 1982 O 1.8 3.2 N 2.3 NNW NNE 12 4.3

                   "#                                                          NE 9

6 3.8 9.0 ENE WNW 3 I I 8.0 gmmm .

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     *Value denotes average wind speed for each sector.                                                l11 Figure 2.6-10 WINTER WIND ROSE FOR THE 200-F00T LEVEL O

FROM CRBRP PERMANENT METEOROLOGICAL TOWER DATA l11 2.6-62

Amendment X1 January 1982 0 2.7 4.2 N 2.9 NNW NNE 12 5.6 4.6

NW NE g 6 6.6 4.0 WNW ENE 3 l l , 6 .0 W - M 1.4 mm E 3. 3 O 9 WSW ESE 6.0 3.9 E SW SE 6.3 3.1 SSW SSE 4.9 S 5.0

6. 3 *

           *Value denotes average wind speed for each sector.                                                l11 O                            ,4,u,e 2.6 1,   s,R1,s mimo Rose ,oR 1,z 200.,001 <<,,<
                                                    , ROM CRBRP PERMANENT METEOROLOG1CA< TOWER DATA          l11 2.6-63

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                                                                         /vnendment XI January 1982 0

3.3 4.2 N 2.8 NNW 7 NNE

4.5

                                                                           .0 NW 9                                         NE 6

3.8 4.1 WNW ENE 3 1 3.3 W - MM .34 m E 2.6

                                                          )                                O ESE WSW 4.4                                      .

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3. 5 *

   *Value denotes average wind speed for each sector.                                      l11 1                                                                                               ,

Figure 2.6-12 SUMMER WIND ROSE FOR THE 200-F00T LEVEL , FROM CRBRP PERMANENT METEOROLOGICAL TOWER DATA l11 1 2.6-64

Amendment XI January 1982 O 4.1 4.1 N 3.1 ' NNW NNE 12 6.5 4,4 9 NE l 6.1 4.5 WNW / ENE ' 3 ' 4.5 W - MMM .05 mm E 2.9 O l 9 ! WSW ' ESE 4.9 2.8 SW SE 4.7 1,9 SSW - SSE 3.8 S 2.3

4. 4 *

          *Value denotes average wind speed for each sector.                                                                    l11 Figure 2.6-13 FALL WIND ROSE FOR THE 200-F00T LEVEL FROM CRBRP PERMANENT METEOROLOGICAL TOWER DATA                              11 2.6-65

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                                                                                           -                                                                                  O Figurg 3.4-                               ITE LOCAT10y 3.4-17 i

Amenduent X December, 1981 TABLE 3.5-2 (Continued) Im Level Activity (2) Intermediate Activity (3) Isotope Hal f-Li fe Monitor Tank (C1) Storage Tanks (C1) Pu-242 3.8E5Y 3.45E-13 3.48E-12 Np-238 2D 1.12E-17 5.09E-14 Np-239 2.4D 5.15E-14 2.46E-10 Am-241 433Y 1.02E-13 4.81E-10 Am-242;n 152Y 4.01E-15 1.90E-11 Am-242 16H 4.01E-15 1.90E-11 Am-243 7.4E3Y 1.64E-lS 2.23E-11 On-242 163D 7.15E-14 3.42E-10 On-243 30Y 9.90E-16 4.72E-12 On-244 18Y 2.07E-14 9.81E-11 (1) 0.1% failed fuel for fissien proi cts and 50 ppb in the primary sodium, 30 years irradiation and 10 days decay of fission and activated corrosion products. Decay due to collection, 4 10 processing and holip are neglected. (2) Im activity is based on Table 3.2-1 with a DF=105 for all isotopes except iodine (T=104 ) and tritium (T=1) 2400 gallon monitoring tank volume. (3) Intermediate Activity is based on 40,000 gallon storage capacity containing the activity inventory in 16,000 gallons of acid etch and in 24,000 gallons of sodium cleaning solution. A decontamination factor of 105 is applicable to all isotopes except iodine (T=10 4 ) and tritium (T=1). 'Ihis is a worst cmbination of expected operations, with the decontamination acid etch fr m one PHTS pump decontamination, which occurs three times in the life of the plant. O 3.5-23

Amendment XI January, 1982 TABLE 3.5-3 OWCENIPATICN OF RADIONUCLIDES AT DISCHARGE

                    'IO CLINCH RIVER: EXPu,Tw VAWES Low Activity        Intermediate        'Ibtal Activity Isotope Half-Life   (# Ci/cc) (1)

Activity (M Ci/cc)(2) (# Ci/cc) (3) H-3(4) 12.3Y 9.53E-10 3.26E-8 3.36E-8 lIl Na-22 2.6Y 1.95E-14 4.84 E-14 6.79E-14 Na-24 15Y 2.22E-15 6.00E-14 6.22E-14 Cr-51 28D - 2.63E-12 2.63E-12 Mn-54 312D - 1.89E-ll 1.89E-ll Co-58 71D - 1.71E-10 1.71E-10 Co-60 5.2Y - 4.81E-ll 4.81E-ll Fe-59 45D - 1.25E-12 1.25E-12 Sr-89 51D 4.93E-17 5.10E-14 5.10E-14 Sr-90 28.8Y 3.47E-17 3.68E-14 3.68E-14 Y-90 64.lH 3.47E-17 3.68E-14 3.68E-14 Y-91 58D 4.90E-17 1.50E-14 1.50E-14 Nb-95 35D 7.60E-17 1.26E-ll 1.26E-ll 8 10 Zr-95 64D 7.60E-17 1.26E-ll 1.26E-ll Mo-99 67D - 3.llE-15 3.llE-15 Ru-103 40D 1.12E-16 1.66E-ll 1.66E-ll Ru-106 lY 1.41E-16 2.53E-13 2.53E-13 Rh-106 2.2H 1.41E-16 2.53E-13 2.53E-13 Ag-111 7.5D - 1.01E-15 1.01E-15 Sb-125 2.7Y 2.47E-16 6.71E-15 6.96E-15 Te-127m 109D 1.00E-16 1.04E-13 1.04E-13 Te-127 9.35H 1.00E-36 1.04E-13 1.04E-13 Te-129m 34D 4.00E-16 3.14E-13 3.14E-13

 'Ib-129      70M      4.00E-16             3.14E-13             3.14E-13 f Te-132       78H      2.14E-16              2.25E-13            2.25E-13 l   I-131     8.lD      1.08E-13              5.84E-12            5.95E-12 l   I-132    2.3H       2.03E-14              5.52E-13            5.72E-13 Cs-134     2.lY       5.26E-15              2.66E-13            2.71E-13 Cs-136       13D      6.53E-13              2.67E-13            2.73E-13 Cs-137       30Y      4.33E-14             1.05E-ll             1.058-11 Ba-140    12.8D       1.95E-17              9.10E-12            9.10E-12 l La-140       40H      1.95E-17              9.10E-12            9.10E-12 l Ce-141    32.5D       5.16E-17             3.35E-14             3.35E-14 Ce-143    32.5D       1.69E-17              5.90E-14            5.90E-14 Pr-143    13.7D       1.69E-17             5.90E-14             5.90E-14 Ce-144     285D       2.30E-17              2.41E-14            2.41E-14 Pr-144       17M      2.30E-17              2.41E-14            2.41E-14 Nd-147    ll.lD       9.90E-18             7.42E-15             7.42E-15 I Pm-147     2.7D       1.31E-17             7.42E-15             7.42E-15 Eu-155     1.8Y          -

1.32E-15 1.32E-15 Ta-182 115D - 8.13E-12 8.13E-12 Pu-238 86Y 4.00E-17 1.49E-15 1.53E-15 Pu-239 2.0E4Y 1.09E-17 4.00E-16 4.llE-16 L 3.5-24

Amendnent X Decenber,1981 CJ Iow Activity Intermediate Total Activity Isotope Half-Life (ACi/cc) (1) Activity (ACi/cci(2) ,ACi/cc) ( (3) Pu-240 6.7E3Y 1.43E-17 5.23E-16 5.47E-16 Pu-241 13Y 1.18E-15 4.42E-14 4.54E-14 Pu-242 3.8E5Y 3.02E-20 1.12E-18 1.15E-18

      !(>-238                       2D      4.62E-22                        1.64E-20               1.69E-21 Np-239                   2.4D         2.12E-18                        7.94E-17               8.15E-17 Am-241                   433Y         4.20E-18                        1.55E-16               1.59E-16 Am-242m                  152Y         1.66E-19                        6.13E-18               6.29E-18 Am-242                      16H       1.66E-19                        6.13E-18               6.29E-18 Am-243              7.4E3Y            6.80E-20                        7.19E-18               7.26E-18 On-242                   163D         2.95E-18                        1.10E-16               1.13E-16 Cm-243                       30Y      4.08E-22                        1.52E-18               1.52E-18 cm-244                      18Y       8.55E-18                        3.16E-17               4.02E-17 Notes of Table 3.5-3 (1)    Iow Activity Licuid Waste Assucptions a)         0.1% failed fuel and 50 ppb Pu in the primary sodium, 30 years m                    irradiation and 10 days decay of fission and activated corrosion

, products. Decay time in collecting, processing and holdup are ignored, b) 850 gallons per d 10-4 M Ci/cc is decontam by a factor of 10 p except containingiodine (DF=10 4 ) and tritium (DP}1nated released to the cannon plant discharge header of 3.1 x 10 1 g) and cc/ year. 8 10 c) h e activity level of 10-4 ACi/cc canes from spillage of 3.5 lbs per year of primary sodium into the drainage stream of 850 gallons per day. (2) Intermediate Activity Lionid Waste Assumtions a) 0.1% failed fuel and 50 ppb Pu in the primary sodium 30 years irradiation and 10 days decay of fission and activated corrosion pro & cts. Decay time in collecting processing and hol& p are ignored. b) 4,000 gallons per year discharged to the conmon plant discharge header. his activity is based on the inventory in 1600 gallons of acid e ADF=10gchandin2,400gallonsofsodiumcleaningsolution. is used for all isotopes except iodine (DP = 104) and tritium (DF=1) .

    ) (3)    Sum of columns 3 and 4.

(4) BOP discharge concentration of 7.0E-7 /4Ci/cc is not included. 3.5-25

Amendment XI January, 1982 TABLE 3.5-4 RAPS PEREORMANCE SJMMARY DATA l10 Cover Gas Cover Gas RAPS Output Cryostill Inventory

Concentration Concentration ** Decontamination gi Isotore Curies W Ci/sec)

W Ci/sec) Factor I Xe-131m 8.6E-1 7.4E-2 1.8E-6 >>l.5E4 Xe-133m 2.8El 2.4E0 5.4E-5 >>l.5E4 Xe-133 5.0E2 4.2E1 1.0E-3 >>l.5E4 Xe-135m 1.2E2 1.lEl 2.0E-6 >>1.5E4 Xe-135 2.2E3 1.9E2 2.6E-3 >>l.5E4 Xe-138 2.0E2 1.8El 2.8E-6 >>1.5E4 Kr-83m 7.4El - 2.2E-5 >l.5E4 10 Kr-85m 1.8E2 1.6El 1.3E-4 >1.5E4 4 Kr-85 1.6E-2 1.4E-3 3.4E-8 >1.5E4 Kr-87 2.0E2 1.7El 3.8E-5 >1.5E4 Kr-88 3.4E2 3.0El 1.6E-4 >1.5E4 Ar-39* 3.lE-1 2.7E-2 2.7E-2 1.0E0 Ar-41M 1.4El 1.2E0 7.6E-2 1.8E0 Ne-23

8.9ES 7.7E4 9.4E-3 1.2E0 H-3 M 1.7E-4 1.5E-5 1.5E-5 1.0E0

*After 1 year of operation end with 0.1 percent failed fuel

- Concentration in cryostill effluent
Inventories independent of failed-fuel percentage O

3.5-26

1 O TABLE 3.5-10 ESTIMATES OP SOLID RADWASTE SHIPRENTS PER YEAR II IN TERMS OF ANNUAL QUANTITIES If l Estimated Volgee Weight Activity fft i fiba.) tcil Commenta 10 Compactible Solids

210 1.2E4 <0.02 Ci Rags, paper, and seals Non-Compactible Solids

, Scrapped Components 600 7BD MD valves, vapor traps 8 l Resina 125 5.6E3 280 Activated corrosion and fission products Pilters 100 1.5E4 22 Activated corrosion and fisalon products ta Solidified Liquid [ Radweste 1000 1.4E5 2.8E3 Concentrated evaporator bottoes Solidified Tritiated Water 80 2.0E4 78 RAPS and CAPS Metallic Sodium 15 7.5E2 40 Sodium from Reactor Refueling l Operation

Sodium Bearing Solide 735 TBD TBD Small components Total 2865 1.9E5 3.2E3

      ' Assume compaction has decreased volume by factor of 10.

10 EE aa

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l l Amendnent X Deceber, 1981 TABLE 3.5-11 WLID RADWAS'IE SIIPMDMS PIR YEAR Shipnents Volpe Containers Material Per Year .ift 1 Per Year Canpactible Solids 0.2 210 28 Non-Caupactible Solids l 4 8 . Scrapped Cornponents l 6 600 82 Filters and Resins 0.6 225 30 Solidified Liquid Radwaste 9 1000 135 10 o 10

 *55-gal Drums                                                                  l l

l 9 l l l 1 0 3.5-34 l

Amendment XI Jamary,1982 (r~') Oil will be stored in accordance with the Environmental Protection f9 Agency Regulations on Oil Pollution Prevention (3) which will minimize the potential impacts of oil contamination on the local surface and groundwater systems. Chemicals will be stored in 11 accordance with the Environmental Protection Agency Proposed Hazardous Substance Pollution Prevention Regulations.(3a) A list of the on-site chemical storage tanks and a description of the Secondary Containment Systems are found in Section 7.2. No environmental impact is anticipated under normal conditions from the stored chemicals. Storm water collected by the roof and yard drains is sent via the 6 11 storm drainage system to the impoundment ponds for settlement. Impoundment pond effluents are released from a controlled pond discharge and are transported to the Clinch River via existing natural water courses. A portable oil skimmer vill be available should a visible oil slick appear on the surface of an impoundment ( ,) pond. Any collected oil would be disposed of off-site by a licensed contractor. 5.4.4 EFFECTS ON GROUNDWATER A total of 110 wells and springs are located within a 2-mile radius of the Site. Nearly all of the wells are of limited capacity and serve as small domestic wells as shown in Figure 2.5-12. All of these wells are located to the south of the Clinch River which serves as a " barrier" between the Site and these wells. There are no wells or springs on the Site. Within a 20-mile radius of the 11 Site there are 13 public water supplies that use groundwater as listed in Table 2.2-14. p C 5.4-12a

_, a ,,,,,- ,a . w ,,,,,,,,a,, ---- a,a w.--a -- - _,aw , ,,,_ m_- a w _ _ _,, s 2 ,,_ ,,, h , ,_ l e I i 4 I l l i l i INTENTIONALLY BLANK I l O 1 l O

Amendment XI January, 1982 Deternination of any possible impact on the local groundwater quality and quantity is of great environmental concern. The local groundwater system, as described in Section 2.5, could be affected by plant operation in five ways: (1) contamination from liquid or

           -solid' wastes, such as holding ponds, sanitary lagoons or solid waste l            disposal areas; (2) seepage from contaminated bosias of surface water; (3) deposition from cooling tower drift; (4) accidental l            leakage from storage facilities of chemicals and fuel; and (5) depletion of the water source by over-withdrawal.             However, the CRBRP will be designed Eo that none of these will affect the local groundwater.

As described in Sections 3.6 and 3.7, the facility will have no liquid or solid sanitary waste disposal areas on the Site. The sludge from the extended aeration package will be trucked off-site 8 for disposal. Recharge to the aquifers is through surface soils and [ ) joints in the rock strata. Discharge from aquifers is through soil and rock joints, and the Clinch River is a groundwater sink into which the discharge =from the. aquifers flow. Cooling tower drift will have no effect on groundwater, shown in Section 5.4.6.5. Storage facilities of chemicals and oil will be constructed to prevent leaks and spills to the surrounding soils. The plant will not use groundwater <for industrial or drinking purposes. Thus, the operation of the CRBRP is not anticipated to have any impact on the quality or quantity of the local groundwater system. 5.4.5 EFFECTS FROM COOLING TOWER DRIFT Drift from the CRBRP cooling towers will become deposited in the sur-rounding vicinity. Whether this deposited material will have any im-pact on the local soils, vegetation or waters of the Clinch River is of environmental concern. Calculated drift depositions are given in f O l 5.4-13

AMENDMENT VI April 1976 Table 10.l A-16 of the Appendix to Section 10.1, and serve as the basis for evaluating any impacts on the local terrestrial and aquatic ecosystem. Amendment VI revisions to the ER include new design parameters for the CRBRP cooling system. Table 5.1-13 includes both old and new design fea-tures for the cooling tower. A review of these changes indicates that most of the critical parameters (evaporation rate, drift rate) have decreased slightly in value. It is anticipated that the net effect upon potential atmospheric impact would be to slightly reduce the extent of visible plume, ground fogging and icing potential as well as the drift deposition rate. The changes in the magnitude of the critical parameters associated with any potential impact of the cooling system amount only to a few percent and can be considered to be well within the realm of accuracy of the cal-culation made. Therefore, it is felt that the original analysis based upon the original design parameters is still applicable to the slight modifica-tion made in the new design. Since the original analysis in Appendix 10.1 of the ER is considered to be on the conservative side, drift deposition values were not computed for the new cooling system design. 5.4.5.1 CHEMICAL COMPOSITION OF DRIFT Examination of Table 5.4-7 which lists the composition of the Clinch River waters that will serve as makeup water for the cooling towers and will be the source of the drift, indicates that the major anionic constituents of this river are bicarbonate ions and the major cations are calcium and mag-nesium. The drift will probably' consist mainly of calcium and magnesium carbonates, some calcium and magnesium sulfates and smaller quantities of sodium and potassium chloride. The drift will also contain 2.5 fold of the trace element concentration of these waters. O 5.4-14

Af1END. IX OCT. 1981 these solids. These solids normally would not be present in a sample []J L obtained from a well properly flushed prior to sampling. Therefore, the data obtained from the unpumped wells did not properly represent the quality of water in the formation at the Site. An evaluation of the data obtained from the pumped well showed that at the site groundwater quality was good. Concentrations of dissolved solids were low, averaging 230 mg/1. Concentrations of analyzed nutrients and metals were normally low and on many occasions below detectable limits. (-) 5 /"T V 6.1-29a a

Amendment XI January, 1982 6.1.3.1 METEOROLOGY Sources of meteorological data for the CRBRP area are completely referenced in Section 2.6 and include local and regional climatological records; hourly wind direction, wind speed and stability data from the CRBRP on-site permanent meteorological 9 o tower (110-meter), and statistical Information on severe weather 11 phenomena. Local climatological data are drawn from the National Weather Service records for Chattanooga, Knoxville, and Oak Ridge, Tennessee, and from TVA fog observation stations along Melton Hill Lake on Clinch River upstream from the Site. Regional information on low-leel Inversion frequency, mixing depths, wind speed, and air pollution potential is taken from publica1!ons by Hosier (25) and Holzworth(26,27) , Hourly wind direction, wind speed, and low-level atmospheric stab!Ilty data were obtained from the CRBRP on-site meteorological tower. Hourly dry-bulb temperature and dew point data f or 1970 and 1973 f rom the Bull Run meteorological facility

  ; .n l l e s northeast of the Site and based at 1,042 feet MSL) were Jsed to obtain the results in Section 5.1, Effects of Operation           g of Heat Dissipation System.

Tornado occurrence statistics are taken from publications by the (28,29) Tornado occurrence NOAA Climatologist for Tennessee . probability at the Site is calculated by Thom's method and based on his frequency data (30) . Information on hall damage potential at the Site is based on Changnon I3I) . Extreme rainfall for 9 periods ranging from 5 minutes to 24 hours are from Knoxville records (32) . Historical data on glaz6 storms are from the U.S. Army Technical Report EP-105(33) and information on passage of tropical cyclones through the eastern Tennessee area is drawn from a U.S. Department of Commerce publication on North Atlantic hurricanes. 6.1-30

Amendment XI Janu ry, 1982 O v 6.l.3.1.1 TEMPORARY MONITORING SYSTEM Collection of on-site meteorolog! cal data at the temporary meteorological facility (Fig. 6.1-12) located about one-fourth mile west-southwest of the plant reactor site began on April 11, 1973 and ended March 1, 1978. Data was collected by the " Pulse-0-Matic" system during the period April 11, 1973 to June 21, 1977. Data was collected by the " Nova" System during the period February 11, 1976 to March 2, 1978. Data from the 200-foot tower (based at 772 MSL) Initially included temperature, wind direction, and wind speed at the 75- and 200-foot levels and temperature difference (delta-T) between these two levels. The 75- and 200-foot levels were selected as representative heights for Identifying the low-level wind and stability patterns over the heavily wooded, irregular terrain. Had the general site area been relatively level and without heavy timber, 33 feet and 150 feet aboveground would have been considered the more representative levels as suggested in Regulatory Guide 1.23 and based on past meterological experience. The wind and temperature o data from the temporary meteorological facility were collected by a k Pulse-0-Matic automatic data logging system. The facility was also equipped with backup analog strip-chart recorders for both wind end temperature data. A number of modifications were made to the temporary meteorological facility during the period of operation. 8 9 A hygrothermograph was installed in May 1973. In April 1974, dry bulb temperature, wind speed and wind direction sensors were added at the 33-foot level. Also at this time the delta-T system was converted to a direct measurement system between the 75- and 200-foot levels. As of February 11, 1976, the collection of meteorological data was upgraded by the addition of a more sophisticated data acquisition system. This sytem l9 utilized a Nova minicomputer to collect the meteorological data for futher {9 analysis. The Pulse-0-Matic system was left in operation to assure optimum data recovery. At the same time, the temperature system was upgraded so that the 33-foot temperature could be included in delta-T measurements within the accuracy requirement of NRC Regulatory Guide 1.23. 6.1-31

Amerdment XI January, 1982 A dew-point system based on an optical dew-point sensor was installed at the 7 33-foot level and became operational in May 1976. 8 l9 6.1.3.1.2 PERMANENT MONITORING SYSTEM [9 l9 Tha terrain on and around the CRBRP slie is complex and wooded. Because no j g single location was found that satisfied the documented and experience-based requirements for acceptable exposure under all meteorological conditions, two meteorological sites were selected: a 110-meter tower at site B and a 10-meter tower at site A. The locations for these towers are indicated on Figure 6.1-12. Collection of onsite meteorological data by a NOVA System began on February 16, 1977, was suspended after March 6, 1978. Measurements obtained at site B were those normally carried out at the permanent 9 mateorological f acility supporting the operation of TVA nuclear plants. Measurements at site A were wind direction and wind speed only. Simultaneous m asurements at the temporary and permanent facilities were made during an overlapping period from February 16, 1977 to March 2, 1978. Planned construction activities are not expected to conflict with r.eteorological m nsurements at the permanent locations. Th3 data collection and processing high speed digital computer system was located at site B with the 10-meter wind measurements at site A telemetered to l 11 site B for processing. Although monitoring was suspended in 1978, the towers remain in place. It is 9 Il planned that monitoring will be resumed in order to satisfy NRC data requirements for operating licensing application. The Instrumentation at site A consisted of wind speed and wind direction s:nsors at 10 meters. Site B was Instrumented for (1) wind speed and wind 8 9 11 direction at 10, 60, 110 meters; (2) temperaturo at 10, 60, and 110 meters; (3) dew point at 10 meters; and (4) solar radiation, atmospheric pressure, and rainfall at 1 meter. 6.1-32

Amendment XI

     -)                                                          January, 1982 The following is a more detailed description of the meteorological sensors used and the*r levels on the                                        9 meteorological tower.

Site A Sensor Height (Meters) Description 1 Wind Direction 10 Climet Instruments, Inc. Model 012-10, horizontal

only; l9 calibrated range, electrical, 0-539 , mechanical, 0-360 continuous: data recording range, 0-540 , linearity 1 0.5 percent; accuracy 13 ;

l damping ratio 0.6 standard. lIl Starting threshold, 0.75 mph. Wind Speed 10 Climet Instruments, Inc., Model 011-1; starting

l9 O' threshold, 0.6 mph; operating range, 0-110 mph, calibrated range, 0.6-90 mph; data recording range, 0-99.9 mph; 8 accuracy within il percent or 0.15 mph, whichever is greater from 0.6 to 90 mph.

l11 Site B Wind Direction 10, 60 and 110 Climet instruments, Inc. 9 012-10, horizontal

I only; calibrated range, electrical, 0-539 ,

mechanical, 0-360 , continuous; data recording range, 0-540 ; linearity

1 0.5 percent; percent Il 13 ; damping ratio 0.6 standard. Starting threshold 0.75 mph.

A replacement sensor of a different manufacturer or model will 9 meet or exceed NRC Regu l atory Gui de 1.23.

6.1-32a

Amendmont XI January, 1982 Wind Speed 10, 60 and 110 Climet Instruments, Inc. Model 011-1; starting

threshold, 0.6 mph; operating range, 0-110 9

W mph; calibrated range, 0.6-90 mph; data recording range, 0-99.9 mph; accuracy within 11 percent or 0.15 mph, 8 whichever is greater from 0.6 to 90 mph. Temperature ** 10, 60 and 110 Aerodet (ARI Industries, Inc.) Model R-22.3-E100,* ohms, RTD 9 (Platinum Wire Resistance Temperature Detector); mounted in motorfan aspirated solar radiation shield, Climet instruments, Inc., Model 016-1 at the 60- and 110-meter levels and Model 016-2 at the 10-meter level. Data recording range,

                                           -9.9 F to 99.9 F; RTD accuracy

A replacement sensor of a different manufacturer or model will meet or 9

exceed NRC Regu l atory Gui de 1.23.

- Temperature difference MT) is calculated in the mini-computer, from the temperature values provided by these sensors. 8 O

6.1-32b

4 Amendment XI January, 1982 {')) The photography o A mosaic of aerial photography was prepared. was at a scale of 1 inch equals 1,000 feet. Aerial 4 photographs were taken on February 25, 1981. o A clear overlay with the circle and sector figure Inscribed on it was placed over the mosaic. The center of the figure was placed on the reactor site, o Within each sector, structures which were houses or apartments were identified and counted. Apartments were distinguished from houses by identifying apartment parking lots from the photographs f ollowed by a f ield check to 10 identify the actual number of apartments when necessary. In cases where the structure could not be identified, it was assumed that the structure was a dwelling.

       )    o          Using the 1980 Preliminary Population and Housing Unit Counts, 34a en average number of persons per housing unit was                                  11 obtained for Roane and Loudon Counties.

o The persons per housing unit calculated above was applied to the structures counted. This procedure provided a sector by sector estimate of the people within 5-miles of the site. 5- TO 50-MILE ALLOCATION OF POPULATION The allocation of population between 5- and 50-miles of the site was performed using Census County Division (CCD) maps (CCD's) and assuming that the population tsj geographically, evenly distributed within the county divisions. The steps in the allocation process were: b) 6.1-38a A . . . - . - ____ _ _ _ _ . - . , . . , - . _ _ _ . . _ . . . _. _ _ - _ . _ _ -

Amendment XI January, 1982 o Obtain the CCD maps. The 1980 maps were unavailable at the time of the study. As a consequence, 1970 CCD maps were used. The Bureau of the Census reported that only Knox County of the study area counties had changes from 1970 to 1980 in the CCD bounderles.34b These changes were 11 incorporated into the CCD map. o A composite of the CCD maps of Tennessee, North Carolina, and Kentucky was prepared. o The circle and sector figure was placed on the CCD composite map. o The areal proportion of a Census County Division or town which lies in a sector is calculated.* 10 l o The 1960 population for the CCD or town is multiplied by the proportion calculated above. This process !s repeated for f each CCD or town which lies totally or partially within a wheel sector, o The sector popu l ation estimates are cai r! 6 ated by summing the separate CCD or town estimates. This method's assumption that the population is evenly distributed over the area of the CCD or town is realistic for Tennessee. Except for national parks and national forests, the state has a relatively dense rural population. 6.1.4.2.2 POPULATION PROJECTIONS Population projections for the study area f or 1990, 2000, 2010, 2020, and 2030 were generated using the Greenberg and Krueckeberg

OThe Census County Division maps provides boundaries for the county, its county divisions, towns of 100 or more persons, and unincorporated towns of 2,500 persons or more. For each of these entities, the census provides a population estimate. l 6.1-38b l

h Aaendment XI January, 1982 ratio-trend methodology.34c in this methodology, U.S. Census 11 Bureau Projections 34d corrected for the 1980 census performance were used as controlled totals. Projections for Tennessee, II Kentucky, and North Carolina were available only to year 2000.34" Historical data, the ratio-trend methodology, and the U.S. control totals were used to extend these projections to 2010, 2020, and 2030. State projections were " stepped-down" to county and census civil 10 division (CCD) levels. Ratios of county to state populations were obtained from the Tennessee State Planning Office 3df or by lII the ratio-trend methodology using historical data for Kentucky and North Carolina. Census civil division projections were

 ,            " stepped-down" from the county level using CCD to county ratios obtained from the Tennessee State Planning Office or by the ratio-trend methodology.

l t l O 6.1-38c

O INTENTIONALLY BLANK i j O

i l Amendment XI January, 1982 ( 7.1 PLANT ACCIDENTS

Eight classes of postulated accidents are examined in this section. The NRC, in Regulatory Guide 4.2, has defined a spectrum of accident 8 classes with potential impact ranging from trivial to serious for light water reactors. To the extent possible, Regulatory Guide 4.2 was used for selecting and classifying postulated accidents for the CRBRP. 8 Consequences of most of the postulated accidents are dependent on the activity levels of the primary sodium coolant and/or the reactor cover gas system. The CRBRP design basis for these activity levels is continuous plant operation with one percent failed fuel. However, the maximum expected fuel failure rate is lower by a factor of 10. Consequences of the postulated accidents were determined based on continuous plant operation with 0.5 percent failed fuel. Use of this value provides an adequate measure of potential () radiological impact, without introducing undue conservatism. Atmospheric dispersion was based on the assumption of ground level release. This type of release assumption results in higher concentrations at the Site boundary compared to elevated releases and thus provides a conservative assessment of environmental impact. For each postulated accident, the environmental consequences are evaluated in terms of the maximum individual whole body and organ doses at the nearest Site boundary. Doses at a number of other downwind distances of interest are also presented. An estimate of the whole body population dose resulting from each accident is made. A summary of all the individual doses computed for each accident, as well as the appropriate 10 CFR 20 and 10 CFR 100 limits for 11 8 comparison, are provided in Tables 7.1-5 to 7.1-12. Population dose estimates are summarized in Table 7.1-13. A U 7.1-1

Amendment XI Jmitary, 1982 O 7.1.1 COMPUTATIONAL MODELS 7.1.1.1 METEOROLOGY Diffusion calculations for the accident analyses were performed using the meteorological data provided in Section 2.6. A statistical analysis of dilution factors (x/0) computed from hourly on-site data was performed to define the 50 percent probability x/0 values as a function of downwind distance from the plant. These values represent median atmospheric dilution conditions; dilution will be poorer (less dispersion) 50 percent of the time and better 8 (more dispersion) 50 percent of the time. The x/Q's as a function of downwind distance from the plant are listed in Table 7.1-1. 0 11 Use of these 50 percent x/Q values, representative of the median atmospheric dilution conditions, is consistent with the realistic approach to the evaluation of accidents as required for Environmental Reports. 7.1.1.2 DOSE CALCULATIONAL METHODOLOGY For each of the accidents evaluated, the following doses were 11 considered: o Whole body dose = Sum of the external whole body gamma dose and the whole body dose from the inhalation of radioactive material; o Lung dose; o Bone dose; o Thyroid dose; and o Population dose O 7.1-2

Amendment XI Jmumq,1982 Not all of the accidents evaluated resulted in releases leading to ( ) bone, lung or thyroid doses. The radionuclides released for each accident determined which of the doses itemized above were non-zero. Doses were based on an exposure time equal to the duration of the o li accident. Doses to an individual (whole body, lung, bone and I thyroid) were computed at each of the following locations:

1. 2,200 feet, minimum exclusion distance;

2. 0.6 miles, nearest residence;

3. 1 mile, nearest recreational area;

4. 2.5 miles, low population zone radius l

5. 4 miles, nearest dairy;

6. 7 miles, nearest population center >2,500 (Kingston);

7. 21 miles, nearest population center >100,000 (Knoxville);

and

8. 50 miles.

yll O) Whole body gamma dose was computed based on a semi-infinite spherical cloud model as follows: D

                      =0.25(X/Q){(A)g(E)$

where, Dy = Whole body gamma dose, rem (E lr i = Average gamma energy of isotope, i, pe,r disintegration, MeV, Table 7.1-2 (A); = Activity of isotope, 1, released to the environment, over time interval considered, Curies

           */Q = Dilution factor appropriate for time interval and downwind distance, sec/m 3 , Table 7.1-1.

O R/ 7.1-3

Amendment XI January, 1982 Doses to the whole body and various organs from the inhalation of radionuclides were computed as follows: D Inh =(X/Q)B{(A)$ Wj where, D Inh = Dose to organ under consideration, rem B = Reference man-breathing rate, for 8 hour period, 3.47 x 10-4 m3 /sec (F)i = Dose conversion factor of isotope, i, for organ under consideration, rem /Ci inhaled, Table 7.1-3 (A)i = Activity of isotope, i, released to the environment, over time interval considered, Curies

         */Q = Dilution factor appropriate for time interval and downwind distance, sec/m 3 , Table 7.1-1 Average gamma energies employed in this analysis were taken from                 11 several sources.(2,3,4) Gamma energies include x-rays. No allowance for attenuation in tissue was included. Thus, the energies provide a conservative estimate of the actual absorbed energy.

Conversion factors for internal doses from the inhalation of radionuclides were taken from Regulatory Guide 1.109.IN An estimate of the whole body population dose that could result from l cach accident was made. The model used is as follows: DP = r [0.25 I (A)$ (E )$ + B E (A)$ (FWB)i 3 (X/Q)j(P)jk 1 (r)3 (min) O 7.1-4

Amendment XI January, 1982 where, DP = Whole body population dose, man-rem (*/Q)j = Dilution factor appropriate for time interval and downwind distance (r) j , sec/m3 ( A)i = Activity of isotope, i, released to environment over time interval considered, Curies (E7 )i = Average gamma energy of isotope, i, per disintegration, MeV B= Reference man breathing rate, 3.47 x 10-4 m3 /sec (FWB)i = Whole body dose conversion factor of isotope, i, rem /Ci inhaled (P) jk = Population in radial increment rj to rj+1 and azimuthal sector k (r) 3 = Downwind distance at midpoint of radial increment r 3 to r$+1 The model for calculation of whole body population dose includes both the contribution of the internal whole body dose due to inhalation of radioactive material and the external gamma dose. To provide an estimate of the maximum and minimum population dose that could result from each accident, depending on the wind

direction during the accident, two azimuthal sectors were used in I

the evaluation. The maximum population dose was determined assuming ( that the wind was persistent (constant direction) for the duration l of the accident and towards the E,..the sector with the highest g . b l 3 ( */Q) 3 ( P) j k . Minimum population dose was determined by assuming wind persistence towards the NNW, the sector with the lowest f(X/Q)j (P) jk. A measure of the probability that either of these situations exists is the respective annual average wind frequency, (f)k, for each sector. Both the minimum and maximum population doses are based on sector centerline doses and thus are conservative w since meandering of the wind within the sector is neglected. 7.1-5

Am:ndm5nt XI January, 1982 Wind frequency and population distribution per radial increment for both the E and NNW sectors are shown in Table 7.1-4. The 50 percent l11 N/Q values defined at the midpoint of each radial increment are included in Table 7.1-1. Population distribution is the projected distribution for census year 2010. 7.1.1.3 SODIUM FIRE ANALYSIS The pressure-temperature history of inerted cells following postulated sodium spills is computed using the SOFIRE II and SPRAY-3 computer codes. SOFIRE II and SPRAY-3 calculations have been g compared f avorably to experimental results. (6) Two versions of SOFIRE II have been written to simulate fires in a single )) containment volume and in an interconnected double cell. In air-filled cells, the pressure-temperature histories are calculated using the SPRAY-3B and SPCA codes. Time behavior of aerosols generated during sodium combustion was computed using the HAA-3 computer code.(7) The code provides for 8 both one and two compartment modeling. Effects of Brcwnian agglomeration, gravitational agglomeration, settling, wall plating and leakage are included in the program. In addition to predicting a number of time-dependent parameters descriptive of the aerosol, the program computes, as a function of time, the plated, settled, suspended and leaked masses. The latter is of particular interest in determining potential environmental impact resulting from postulated sodium spills. 7.1.2 ACCIDENT ANALYSES 7.1.2.1 ACCIDENT 1.0 - TRIVIAL INCIDENTS These incidents are included and evaluated in Sections 5.2 and 5.3 under routine releases in accordance with Regulatory Guide 4.2. O 7.1-6

Amendment XI January, 1982 ( ) 7.1.2.2 ACCIDENT 2.0 - SMALL RELEASES OUTSIDE CONTAINMENT To demonstrate the minimal environmental impact resulting from small tritium releases outside containment, two postulated releases are evaluated in the following sections. 7.1.2.2.1 ACCIDENT 2.1 - TRITIUM RELEASE THROUGH SGAHRS VENT j) CONTROL VALVES The event which would result in the largest release of steam from the Steam Generator System (SGS) due to operation of the Steam )) Generator Auxiliary Heat Removal System (SGAHRS) Vent Control Valves has been identified as the loss of the main condenser during full power operation. Design basis frequency for the loss of main condenser is 10 over the life of the plant. However, it is expected that the actual frequency is lower than the design basis. l'h (_) Following the postulated loss of a main condenser, heat removal would be accomplished by venting the steam in the SGS to the atmosphere through the SGAHRS Vent Control Valves. Venting 11 continues until the heat load is reduced to 45 MWT at which time a (~1.0 hour) the SGAHRS is capable of removing heat in a closed loop 11 fashion. For the accident postulated, release of all the available steam / water in the SGS and the normal feedwater deaerator tank is 6 assumed. This assumption is a conservative estimate of the maximum water volume released during steam venting. Apptaximately 353,000 pounds of water is assumed to be released to 11 6 the atmosphere. The only radioactive material present in the water is tritium which has entered the system by diffusion through the heat exchanger tubes in the steam generators and superheaters. The O O 7.1-7

Am:ndment XI January, 1982 calculated level of tritium in the SGS at the end of plant life (30 11 years) is 0.62 pCi/g resulting in a tritium release to the atmosphere of 99 Curies during the steam dump. Maximum off-site whole body dose from this postulated release is 8 5.50 mrem. Doses at specific downwind distances and estimates of 4 11 the potential population dose are provided in Tables 7.1-5 to 7.1-13. 7.1.2.2.2 ACCIDENT 2.2 - CONDENSATE STORAGE TANK LEAK For this accident, a leak in a condensate storage tank containing 11 tritiated water was postulated. The following conservative assumptions and conditions were used to evaluate potential environmental impact;

1. The condensate has attained the same equilibrium tritium concentration as is found in the steam generator lh

( 0. 6 2pci/cc) ;

2. The storage tank releases water via a valve leak at a rate of 10 gpm to a drain which empties directly into the river, and

3. The flow rate of the Clinch River at the point of discharge Il is 4,339 cfs (Low flow - spring average) .

This postulated accident leads to a release rate of 23.5 mci / minute to the river and a do,wnstream concentration of 3.18 x 10-6 pci/cc of 11 tritium. This concentration is about three orders of magnitude below the limits set forth in 10 CFR 20, Appendix B and will be of limited duration; as such, no adverse environmental impact would result from this postulated leak. O 7.1-8

Amendment XI January, 1982 (O_) 7.1.2.3 ACCIDENT 3.0 - RADWASTE SYSTEM FAILURES Intermediate activity level liquid process streams and storage tanks are located in concrete cells below grade in a non-hardened portion of the Reactor Service Building. Floors and walls of the cells are painted with an epoxy coating to prevent leakage of contaminated II water to the outside groundwater and to facilitate decontamination, if necessary. Floors of all cells in the basement are protected with a pliable undercoat to prevent in-leakage of ground water to 11 the cells. Each cell is provided with a floor drain whose effluents are routed to a sump. Sump pumps are then used to transfer spilled fluids to any desired tank. Because the cleaning precess used to remove contaminated sodium from components yields salts which are expected to remain stable during processing in the radwaste system, the liquid radwaste tanks contain

  <~s  no gaseous radioactive species.      In the event of tank failure,
    -  malfunction or operator error, resulting in a spill, the only mechanism for radioactivity release is the evaporation of water containing tritium as HTO.

The CRBRP gaseous radwaste system consists of two subsystems that process radioactive gases; the Cell Atmosphere Processing Subsystem (CAPS) and the Radioactive Argon Processing Subsystem (RAPS). RAPS l processing components are located in the RCB, and CAPS components 11 are located in the RSB. l . - CAPS processes gas streams that normally contain low level radioactivity prior to their discharge from the plant. RAPS processes the more highly radioactive cover gases from the primary 11 , sodium system. f l (J

\~

l 7.1-9

Amendment XI January, 1982 Because RAPS receives and processes gases of much higher activity 11 levels than CAPS its process components are located in the RCB. Rupture of the Noble Gas Storage Vessel (NGSV) is included in the accidents in the subsequent sections since it is the limiting gaseous radwaste system accident. 7.1.2.3.1 ACCIDENT 3.1 - LIQUID SYSTEM TANK MALFUNCTION A malfunction or equipment leakage of a liquid storage tank releasing 25 percent of the average inventory of the tank is postulated. The liquid release, 5,000 gallons of water, would 6 contain 13,000 pCi of tritium as HTO. The floor area of the cell 1 housing the storage tank is 1,000 square feet and the cell volume is 39,000 cubic feet. Spilled fluid would be transferred to an 11 unfaulted tank by a sump pump, designed for a flow capacity of 50 gpm. Time required for spill cleanup is 1.7 hours. Evaporation ( rate of the liquid tritium during the time period when the liquid is being pumped into an unfaulted tank was assumed to be constant. ! Rate of tritium evaporation was computed using the experimental results of Horton, et al. (0) The total tritium release from the 8 pool by evaporation during the 1.7 hour cleanup time is 25 pCi. Direct release of the evaporated tritium to the atmosphere via the 6 Reactor Service Building ventilation system was assumed. 11 The maximum off-site whole body dose resulting from this event is 1.4x10-6 mrem. Doses at specific downwind distances, based on 6 exposure for the duration of the accident, are presented in Tables 7.1-5 through 7.1-12. Estimates of the potential population dose g are presented in Table 7.1-13. i O 7.1-10 l l

Amendment XI January, 1982 As the above analysis indicates, a realistic assessment of this postulated fault results in exposure orders of magnitude less than 10 CFR 20 limits. To further demonstrate the minimal environmental l11 impact of this postulated event, an upper bound limit to potential off-site exposure was computed by unrealistically assuming that the total HTO inventory, 13,000 #Ci, of the spilled fluid was evaporated and released directly to the atmosphere. In this case, the maximum whole body dose would be 7.2x10-4 mrem. Even for this upper-bound unrealistic evaluation, the doses are well below 10 CFR 20 limits. 11 7.1.2.3.2 ACCIDENT 3.2 - LIQUID SYSTEM TANK FAILURE This event is similar to ACCIDENT 3.1 except complete release, 100 percent, of the average inventory of the tank is postulated. In j this case, 20,000 gallons of water containing 50,000 pCi of liquid HTO are assumed spilled. Spill cleanup time is 6.7 hours. The 0 p total tritium evaporated during this time is 95 pCi. Direct release of the evaporated tritium to the atmosphere through the Reactor 11 Service Building ventilation system was assumed. The maximum off-site whole body dose resulting from this event is 6 8 5x10-6 mrem. Summaries of the whole body doses at specific downwind distances, based on exposure for the duration of the accident, are presented in Tables 7.1-5 through 7.1-12. Estimates of the potential population dose are presented in Table 7.1-13. l8 AswasdoneforACCIDENT3.1,anuhperboundlimittooff-site exposure was computed for this event by assuming complete evaporation and release of the 50,000 pCi of HTO contained in the l6 11 spilled fluid. This was done only to demonstrate the minimal environmental impact of this unlikely fault because the assumption of complete tritium release as vapor is unrealistic. Even for this worst case assessment, the resultant whole body dose, 2.8x10-3 mrem,l 6 8 is well below 10 CFR 20 limits. 11 7.1-11

l Am:ndm:nt XI January, 1982 7.1.2.3.3 ACCIDENT 3.3 - RUPTURE OF THE RAPS NOBLE GAS STORAGE VESSEL The RAPS noble gas storage vessel (NGSV) normally contains radioactive gas which is off-loaded annually from the RAPS )) cryostill. It contains mainly argon (including argon-39) but also krypton and xenon isotopec, both stable and radioactive. The gas is bled slnwly from the vessel into CAPS so that its pressure normally decreases over the annual period. A rupture of this vessel or of associated piping and components could release radioactive gas at above-ambient pressure into the NGSV cell. Although such a rupture is not expected, it is assumed to occur. For the purpose of the accident analysis, it is conservatively assumed that the reactor has been operating sufficiently long with gaseous fission products from 0.5% failed fuel for steady-state isotopic composition to exist in the cover gas system and that 1 years' accumulation by the cryostill of noble gas isotopes, under that condition, has been off-loaded to the NGSV. Furthermore, it is assumed that some unspecified maintenance operation has required that the new fresh cryostill charge also be off-loaded to the storage vessel, this in quick sequence, so that the storage vessel contains two charges and is approximately at maximum pressure. Assuming the vessel (260 actual cubic feet volume) is at 1 atmosphere pressure absolute before the two cryostill off-loadings (1.5 cubic feet of liquid argon each) , it will contain 2640 scf of gas prior to the accident. O 7.1-12

Amendment XI January, 1982 ( Following the assumed storage vessel rupture, the NGSV cell H&V radiation monitor will sense the presence of radioactivity, sound an alarm, and initiate a signal which will cause the cell vent line to close. The cell (whose net volume is 3560 actual cubic feet includ-ing the vessel volume) pressure will-then increase to 9.8 psig, assuming instant temperature equilibration to ambient. The initial radioactivity inventory and amount leaked to the environment are

shown in Table 7.1-15.

The accident scenario assumes the RAPS NGSV cell leaks at a rate consistent with its design leak rate of 1%/ day at 3 psig. This is a reasonable assumption since the cell will be periodically tested to insure that its design leak rate is met. The off-site doses are further limited by the low leakage rate of the RCB, which is assumed to isolate immediately following the event. The design leak rate of the RCB is 0.1%/ day at 10 psig.

       / Also, for the analysis, a constant 1 psig c6ntainment pressure was assumed. This 1 psig pressure is a conservative allowance for building heatup following containment isolation.

The maximum off-site whole body dose resulting from this event is 7.71x10-1 mrem. Summaries of the whole body doses at specific ! downwind distances, based on exposure for the duration of the accident, are presented in Tables 7.1-5 through 7.1-12. Estimates of the potential population dose are presented in Table 7.1-13. As these Tables indicate, large margin's exist between the potential doses and the applicable regulatory limits. It is concluded that the postulated Noble Gas Storage Vessel rupture will not result in unacceptable environmental consequences. O 7.1-13

r Amendment XI January, 1982 To further demonstrate the minimal environmental impact of this postulated event, an upper bound limit to potential off-site exposures was computed by also assuming that the NGSV cell is not a leakage barrier, which is an extremely conservative assumption. For this assumption, the radioactivity is assumed to be released directly to the RCB. The off-site doses still are limited by the U low leakage rate of the RCB, which is assumed to isolate immediately following the event. The maximum off-site whole body dose resulting from this exagger.jped event is 4.46 mrem. 7.1.2.4 ACCIDENT 4.0 - SODIUM FIRES DURING MAINTENANCE Postulated sodium fires could possibly result in the dispersion of some radioactive materials to the atmosphere. Fires involving primary sodium coolant are of most concern since this sodium circulates through the reactor core and accumulates radioactivity due to neutron activation and entrainment of fission products leaking from defective fuel. Postulated fires involving sodium used in the Ex-Vessel Storage Tank (EVST) cooling system could also result in radiological releases. The EVST sodium is essentially non-radioactive at the beginning of plant life. However, during refueling a small quantity of primary sodium is transferred to the EVST along with each irradiated assembly, resulting in a slow buildup of radioactivity in the EVST sodium. Accidents discussed in this section involve postulated sodium spills during maintenance. Detailed maintenance procedures for the CRBRP are not yet completely defined. However, recognizing the potential hazard associated with postulated sodium fires, a set of design guidelines have O 7.1-14

Amendment XI January, 1982 () been established to limit the consequences of postulated sodium fires during maintenance by limiting residual sodium content and equipment being maintained as follows:

1. The maximum inventory of primary sodium in an open, de-inerted cell, able to communicate with the environment, shall not exceed 130 pounds;

2. The maximum allowable spill of EVST sodium in an open, de-inerted EVST cooling system cell shall not exceed 250 pounds.

l If during maintenance inside containment, the potential exists for a postulated primary sodium spill exceeding 130 pounds into an open de-inerted cell, the RCB/RSB Hatch will be closed, insuring containment integrity. Large sodium spills inside containment during maintenance and large sodium spills during (A,) operation are extremely unlikely events and are discussed in ACCIDENT 8.0. To determine the potential radiological impact of sodium fires j during maintenance, two accidents, one involving primary sodium and the other EVST sodium, have been postulated. Consequences of these fires, presented in the following sections, have been conservatively evaluated taking no credit for the fire protection systems, fallout of combustion products during transit downwind, or aerosol plateout and settling within buildings. 7.1.2.4.1 ACCIDENT 4.1 - FAILURE OF EX-CONTAINMENT PRIMARY SODIUM DRAIN PIPING DURING MAINTENANCE < The ex-containment primary sodium storage vessels are located in a cell on the lowest level of the Intermediate Bay of the Steam Generator Building (SGB). Vessels are connected to process 7.1-15 .

Amendment XI January, 1982 systems within containment by fill and drain headers. Headers o are valved off at the containment penetrations, During normal plant operation the vessels are essentially empty; the drain 11 lines are also expected to be empty. It is postulated that the storage vessel cell is opened by pulling a plug in the cell ceiling and is entered for tank inspection. The cell atmosphere is then open to the atmosphere of the Intermediate Bay of the SGB above the cell. Maximum potential sodium spill under these conditions is limited to 130 pounds

and for the postulated 77 accident it is assumed that this quantity of sodium is instantaneously spilled to-the cell floor. Although postulated, it should be noted that a spill of this magnitude is not expected because operational procedures dictate that the system will be drained before permitting access.

It is assumed that the cell is opened for inspection or maintenance-after the sodium has undergone radioactive decay for 10 days. Actual decay. time before entry to the cell is expected to be longer. It is further assumed that the accident occurs near the end of plant life (30 years) when the activity of the sodium has reached its peak. The radioactive content of the 8 sodium under these conditions is shown in Table 7.1-18. , The radiological impact of this postulated spill was determined 1 as follows: 1

1. Complete combustion of the spilled sodium is assumed to occur in less than 2 hours. It is assumed that 27% of 11 the burned sodium is released from the surface of the l

  *For purposes of this analysis, it is postulated that the drain l

piping between the containment isolation valve and the storage j vessels is filled and the drain piping ruptures at the worst location. h 7.1-16

                 - - _ ,                     . - - . - . .                     _ .     ~ . - - - - -   ._      . - . - - .

, 'y i Amendment XI I l January, 1902 2' ; () burning pool to the cell atmosphere (10) . in the release-of 47 pounds of Na 2 O aerosol containing This resulta j; ; e 35 pounds of sodium. s 3

2. Radioisotope concentrations in the aerosol are jj proportional by elemental weight to the initial l

t' concentrations in the sodium; - t l 53 . The aerosol is released directly to the atmosphere via ( the Steam Generator Building ventilation system; [ Ly ,4. Radioactive decay during the accident is neglected; and j L, I

             ,,-                          5.                .No credit for plateout or settli ng of th e aerosol in the l

Intermediate Bay of the SGB or in the ventilation system

!                                    u*

l

                                        ^                   'was taken.

j,7

d '

Rapid combustion (< 2 hours) of the spilled sodium results

- ;, *because it was assumed that the spilled sodium spreads evenly 11 t2 J over-thi entire floor area (2,400 f ) of the storage tank cell.

j< .,This assumption results in the, maximum possible sodium pool area 0 andetherefor'e,;the maximum burning rate. A more realistic ,

      .                            assumpdich,sku'ldbeamuchsmallerpoolinthevicinityofthe

a

                                , postulated leak and consequently, a slower burning rate.

y - ", 1 i _ , lUsir,g the above as'sumptions, the total Na O2 aerosol released tc ( ,f ' "'6he atmosphere is'47 p'ounds. The maximum off-site whole body

! >< dose is 2.37 x 10-2. rem. Doses at specific downwind distances 4 8 Il ie , and estimates of the population dose are provided in Tables 7.1-5

  ,    a through 7.1-13.

t 4

                   ;+                                                       f<
                                                                           ,5 A

k 4.,. 3 /y

          /              75             .

{ ,f fj ,,

                                               ' .\
                                                                                     ~
                  .,-                      ,               e    :,

l ~ '~ ' , 7.1-17 4

                         .-__,_.-__...,+

t. 1_- -

1 Amendment XI Jmumry,1982 1 7.1.2.4.2 ACCIDENT 4.2 - FAILURE OF THE EX-VESSEL STORAGE TANK (EVST) SODIUM COOLING SYSTEM DURING MAINTENANCE l There are three EVST sodium cooling circuits, two normal and a backup. The normal cooling circuits are used alternately to cool sodium circulated to and from the Ex-Vessel Storage Tank (EVST). Each circuit is located in a separate cell, inerted with nitrogen u during circuit operation. For the accident postulated it is assumed that a normal cooling circuit cell is de-inerted to permit personnel access for maintenance. During maintenance, the sodium loop will be isolated from the EVST and will be drained 6 prior to opening the cell. Consequently, a major spill involving a siphoning of the EVST, as described in ACCIDENT 8.4, is not considered a credible event when the cell is de-inerted and open. A shielded door or plug, approximately seven feet high by three I feet wide, is opened, permitting the cell atmosphere to communicate with the atmosphere of the Reactor Service Building. l For the purpose of the analysis it is assumed that the loop is ll not drained, and during this time, a leak in the isolated sodium loop is assumed to occur. The maximum potential sodium spill under these conditions is 250 pounds and for the postulated accident it is assumed that this quantity of sodium is 6 instantaneously spilled to the cell floor. Although postulated, . 1 it should be noted that a spill of this magnitude is not expected because the system will be drained before de-inerting the cell. For conservatism it was assumed that the postulated spill occurs near the end of plant life when the EVST sodium activity has reached its maximum value. It was further assumed, for conservatism, that the postulated accident occurs shortly after l III l l l 7.1-18

Amendment XI January, 1982 s initiating of a refueling operation before Na-24, transferred to the EVST along with irradiated assemblies, has had sufficient time to decay. The EVST sodium activity content for this jj condition is shown in Table 7.1-19. 8 The radiological impact of this postulated spill was determined 11 as follows:

1. Spilled sodium burns releasing Na 2O aerosol. It is assumed that complete sodium combustion occurs in less II than 2 hours resulting in the release of 91 pounds of Na2 O aerosol containing 68 pounds of sodium;

2. Radioisotope concentrations in the aerosol are 11 proportional by elemental weight to the initial concentrations in the sodium; ;

3. The aerosol is released directly to the atmosphere via the Reactor Service Building ventilation system;

4. Radioactive decay during the accident is neglected; and

5. No credit for plateout or settling of the aerosol in the Reactor Service Building or in the ventilation system was taken.

Rapid combustion (< 2 hours) of the, spilled sodium results

                          ,                                                           j) because it was assumed that the spilled sodium spreads evenly over the entire floor area (280 ft 2) of the cell. This assumption results in the maximum possible sodium pool area and therefore, the maximum burning rate. A more realistic assumption would be a much smaller pool in the vicinity of the postulated leak and consequently, a slower burning rate.

7.1-19

Amendment XI January, 1982 The total Na 2O aerosol released to the atmosphere is 91 pounds. 4 8 The maximum off-site whole body dose is 8.75 x 1G-3 rem. Doses 11l h ct specific downwind distances and estimates of the population dose are provided in Tables 7.1-5 through 7.1-13. 7.1.2.5 ACCIDENT 5.0 - FISSION PRODUCTS TO PRIMARY AND SECONDARY SYSTEMS Environmental consequences of plant operation with cladding defects (failed fuel) were considered in Sections 5.2 and 5.3 of this report. The assesssment was conducted realistically assuming continuous plant operation with 0.1 percent failed fuel. The environmental impact of tritium, produced in the reactor core during normal operation, and diffused through the fuel and control rod cladding to the primary and secondary systems to the f steam generator, was also considered in Sections 5.2 and 5.3. Environmental consequences of transient-induced fuel failures coupled with a steam generator leak are typically addressed in light-water reactor environmental reports. However, the design of the CRBRP Heat Transport System (HTS) is such that radioactivity released to the primary coolant is effectively isolated from the steam generators. Primary sodium coolant removes heat from the reactor core and blanket and transfers this heat to the intermediate sodium through the Intermediate Heat Exchanger (IHX). Primary sodium then returns to the reactor vessel. In the intermediate system, sodium, heated in the IHX, is circulated to the Steam Generator (SG) where its heat is transferred to a water-steam mixture which drives a conventional turbine-generator unit. This configuration provides a double barrier, the IHX and SG tube wall / tube sheets between the primary sodium and the steam system. In addition to the double barrier inherent in the HTS design, the operating pressure of the intermediste sodium is slightly higher than that of the primary 0 7.1-20

Amsndment XI January, 1982 /~N () sodium. As a result, leakage of primary sodium into the intermediate system is avoided, further reducing the possibility of radioactivity release through the Steam Generator. Significant fuel failures resulting from off-design transients are not anticipated in the CRBRP. As discussed above, even if some unexpected fuel failures are postulated, release of radioactivity through the steam generator is avoided. Environmental release of radioactivity following a postulated fuel failure would be limited to noble gas leakage. The release of noble. gases through this system during normal operation with 8 0.1 percent failed fuel was considered in Sections 5.2 and 5.3. A postulated fuel failure would result in an incremental surge of noble gas activity into the reactor cover gas space. This surge of activity would be subject to normal processing and leakage. Potential environmental impact of this event is discussed in the

s. following section.

V The possibility of non-radioactive intermediate sodium interacting with water / steam via a Steam Generator tube rupture has also been investigated. Environmental consequences of this event are discussed below. 7.1.2.5.1 ACCIDENT 5.1 - OPP-DESIGN TRANSIENTS THAT INDUCE FUEL FAILURES ABOVE THOSE EXPECTED Significant fuel fail,ures resulting,from off-design transients are not anticipated in the CRBRP. However, potential environmental consequences associated with a postulated transient-induced fuel failure have been evaluated. The evaluation is based on the following assumptions:

1. 0.02 percent of the end-of-cycle equilibrium core

(~ inventory of noble gases and halogens instantaneously k-)) released to the primary coolant; 7.1-21

Amendment XI January, 1982

2. Cover gas and primary coolant activity prior to the postulated transient based on continuous operation with 0.5 percent failed fuel; and

3. Normal operation of CAPS and RAPS prior to and following the postulated transient.

Assuming no decay time for the noble gases as they rise through the sodium coolant, this postulated accident results in an instantaneous release of noble gases to the reactor cover gas volume. Because of the strong chemical affinity of liquid sodium for halogens, release of halogens from solution to the cover gas can be neglected. Radioactive argon, neon and tritium concentrations in the reactor cover gas are unaffected by this postulated fault. These isotopes principally arise from neutron activation and no additional activity from these isotopes will be introduced to the reactor cover gas as a result of the postulated cccident. Therefore, the postulated accident results in an incremental surge of radioactive xenon and krypton to the reactor lll cover gas. Normal steady-state radioactive cover gas inventory for continuous operation with 0.5 percent failed fuel, due to xenon and krypton, totals 19,500 Curies. The postulated surge of xenon g and krypton into the cover gas adds 37,100 Curies. Total cover gas radioactive inventory due to xenon and krypton immediately following the postulated transient is, therefore, 56,600 Curies. 11 This surge activity, as well as the normal steady-state activity, is subject to normal processing and cleanup through RAPS and is clso subject to normal cover gas leakage. O 7.1-22

Amendment XI January, 1982 The accident was evaluted in terms of the total excess cover gas activity released to the environment as a result of the transient compared to that normally released, assuming continuous plant g 11 operation with 0.5 percent failed fuel. Excess activity leakage will continue until the cover gas system returns to its normal steady-state concition. The inventory of each xenon and krypton isotope will asymptotically approach a steady-state condition. For the evaluation, the recovery time required for the inventory of each isotope to reach a value within one percent of its steady-state value was determined. The recovery time for each isotope is dependent on the isotope's half-life, the purge rate of the reactor cover gas to RAPS and the decontamination factor for the isotope in RAPS. The longest recovery time for any of the xenon or krypton isotopes is 15 hours (for Kr-85). Total excess cover gas leakage during the 15-hour recovery time is only 0.0014 Curies (see Table 7.1-17). More than 75 percent l of this activity leaks in the first two hours following the postulated transient. Major leak paths from the cover gas system are reactor head seal leakage and leakage of recycle cover gas through buffer seals in the reactor head. For conservatism, no delay factors in the movement of gases to or through these seals were included in the analysis. Delays in gas movement through these seals resulting in radioactive decay and reduced releases are expected. Further, all seal leakage was assumed released directly to the atmosphere via the Reactor Containment Building ventilation system. 4 8 11 The maximum off-site whole body dose from this postulated accident is 8.4 x 10-5 mrem. Doses at specific downwind distances and estimates of the potential population dose are provided in Tables 7.1-5 through 7.1-13. I 7.1-23

Amendment XI January, 1982 7.1.2.5.2 ACCIDENT 5.2 - STEAM GENERATOR TUBE RUPTURE The steam generator modules are designed and manufactured to the 6 n highest quality industrial standards. A broad base DOE development program supports the design and manufacture of the CRBRP units. The water-intermediate sodium boundary will be designed and fabricated to have a high degree of integrity. Failure of the boundary is expected to have a relatively small, although finite, probability. Conservative estimates indicate that approximately 0.5 to 1.0 tube leaks / year could occur for the plant. It is anticipated that the majority of these leaks will be very small in size. Appropriate procedures will be provided to shut down the system in a controlled fashion following the indication of leaks, without release of sodium-water reaction products to the environment. In the unlikely event of a larger leak, such as a single guillotine tube failure, the reaction of water with sodium creates a rapid generation of hydrogen gas, sodium oxide, sodium hydride and sodium hydroxide. High pressure h generated within the module is then relieved by ejecting sodium and sodium-water reaction products through rupture disks to the Sodium Water Reaction Pressure Relief Subsystem (SWRPRS). The SWRPS then separates the gaseous reaction products from the liquid sodium and solid reaction products and burns the hydrogen rich gaseous products. Within the SWRPRS the sodium, gaseous reaction products and possibly steam, are directed by piping to a reaction products separator tank located within the Steam Generator Building. In 6 the reaction products separator tank, gross separation of the i sodium and solid and liquid sodium-water reaction products from the gaseous sodium-water reaction products and any steam 011 remaining takes place. Gaseous reaction products and any entrained particles will then be exhausted from the Reaction O 7.1-24

Am:ndment XI January, 1982 () Products Tank, through vent piping to the atr.osphere. is provided to ignite the hydrogen gas generated in the An igniter sodium-water reaction as it leaves the vent piping. The affected steam generator loop will be isolated, the sodium pump shut down and the loop depressurized by opening the Power Relief Valves. Following a postulated single tube failure in the steam generator module, approximately 669 pounds of reaction products and entrained sodium will be carried into the reaction products separator tank. Within the reaction products separator tank, the sodium and reaction prodicts enter tangetially. The tangential motion results in separation of the liquid, solid and gaseous products and in addition, some of the entrained particles are separated. It is conservatively assumed for this evaluation that no separation of the entrained particles occurs within the reaction products separator tank. () During the short time period (28 seconds) while the SWRPRS is venting to the atmosphere during the design basis leak (DBL) and 11 the SGS is blowing down, small amounts of primary sodium might leak into the intermediate sodium. However, this sodium would not be transported to the superheater inlet during the period of time that this steam generator system is being blown down, due to the length of the piping between the IHX and the superheater inlet and the reduced sodium flows during this event. Therefore, ! no allowance has to be made for venting of primary sodium to the atmosphere. After the venting and blowdown is completed, there could be a trace of this primary sodium mixture vaporized and transported out the SWRPRS vent, however, this would be a negligible amount compared with the 1.4 pounds of primary sodium estimated for the IHTS sodium spill.

7.1-24a I

Amendment XI January, 1982 is released with the reaction products has been evaluated. The Tritium concentration in the Steam Generator System at the end of plant life (30 years) is 0.62 xCi/g and the Tritium concentration 11 in the IHTS sodium is 0.13 ,uci/g for a hydrogen background level in the IHTS of 200 ppb of hydrogen. During a DBL, 204 pounds of water combines with 465 pounds of sodium and the conservative assumption is made that all the sodium-water reaction products are discharged to the atmosphere. Depressurization of the isolated loop by opening the Power Relief Valves will result in the release of all water / steam in the loop to the atmosphere. The total mass released is 5,040 pounds. Using the end of life (30 years) tritium concentration, 0.62 pCi/g for the steam sy.ctem, the total tritium release through the 11 Power Relief Valves for this postulated accident is 1.417 Curies. Thus, the total radioactivity released to the atmosphere as a result of the postulated steam generator tube failure is 1.50 8 11 Curies of tritium, 0.083 released through SWRPRS and 1.417 released through the Power Relief Valves. The maximum off-site whole body dose for this postulated release is 8.3 x 10-2 mrem. Doses at specific downwind distances and 4 11 estimates of the potential population dose are provided in Tables 8 7.1-5 through 7.1-13. , 7.1.2.6 ACCIDENT 6.0 - REFUELING ACCIDENTS In accordance with Regulatory Guide 4.2, the refueling accident evaluations used in connection with light-water reactor environmental reports are generally analyses of radioactivity releases caused by dropping a spent fuel bundle into the open reactor vessel or the open spent fuel storage pool, dropping a O l 7.1-25

Amendment XI January, 1982 () heavy object onto the core when the reactor head is removed for refueling or onto the open spent fuel storage pool and dropping of an open loaded spent fuel shipping cask. These incidents are mechanistically related to the fuel handling system for light-water reactor plants. The refueling system to be used on the CRBRP doec not use an open reactor vessel, an open fuel storage pool or a removable reactor head. Hence, the CRBRP refueling system is not realistically subject to these same kinds of accidents. An alternative set of three postulated events, more representative of the CRBRP refueling system, has been defined. These events, selected af ter careful review of the CRBRP refueling procedure, represent the most severe radioactivity releases associated with postulated refueling system faults. Each postulated fault, although none of them is expected to occur

     ,  during the life of the plant, was evaluated and then potential
   ~    radiological consequences determined.

The three postulated faults, discussed fully in the following sections, are:

1. Spent fuel cladding failure while in the Ex-Vessel Transfer Machine (EVTM) resulting in the release of one percent of the noble gases and iodines contained in the irradiated assembly to the interior of the EVTM;

2. This event is similar to (1) above except that the total inventory, 100 percent, of the noble gases and iodines contained in the irradiated assembly, are assumed released to the interior of the EVTM. This represents an extremely conservative upper limit; and O

7.1-26

Amendment XI January, 1982

3. Inadvertent opening of a floor valve while a reactor port plug is removed. Complete release of the radioactive reactor cover gas through the resulting opening is assumed.

7.1.2.6.1 ACCIDENT 6.1 - SPENT FUEL CLADDING FAILURE IN EVTM

            - ONE PERCENT NOBLE GAS AND IODINE RELEASE The earliest scheduled time for the handling of any fuel essembly         11 with the EVTM is 8 days after shutdown (based on anticipated fuel handling efficiency). At that time, the noble gas and iodine fission product inventories of an average powered fuel assembly, based on end-of-cycle equilibrium core (peak fission product            8 inventories), are shown in Table 7.1-20.

The postulated accident is the instantaneous release of one percent of the noble gases and iodines from the fuel assembly to the interior of the EVTM. This represents a possible consequence 11 of a loss of cooling of the EVTM cold wall. Radioactive gases released to the EVTM interior can then sicwly diffuse through the seals of the EVTM to the Reactor Containment Building (RCB)/ Reactor Service Building (RSB) atmosphere. During refueling the large equipment hatch connecting the RCB and RSB is 'll open. Based on the 47 cubic feet of EVTM gas space being filled with reactor cover gas prior to the fuel cladding failures, the f8 isotopic concentrations of the noble gases and iodines within the EVTM immediately following the assumed one percent release are shown in Table 7.1-21. All seals in the EVTM are double seals. All dynamic or movable seals are, in addition, supplied with a pressurized buffer gas bstween the seals that is monitored for leakage. Thus, leakage O 7.1-27

hrendment XI January, 1982 q 1 of EVTM gases due to physical defects in the seals is unlikely. The mechanism for leakage through these seals is by diffusion of the material (radioactive gases in particular) through the elastomer. Based on the EVTM seal materials, dimensions, o operating temperature and the experimentally determined seal parmeation rates, ( 9) , the diffusion rate for the radioactive isotopes released to the EVTM interior was determined. Iodine isotopes were included in the list because it was assumed possible for bubbles caused by the release of fission gas to rise through the sodium and be released inside the EVTM without the , sodium totally absorbing the iodine. Since no permeation data for iodine through the elastomer seals are available, the seal permeability for iodine was taken to be the same as for xenon. However, it is expected that the permeation will actually be much < lower since iodine may react with the elastomer. This would effectively prevent its release. O Diffusion rates and isotopic concentrations were used to compute 3 leakage rates from the EVTM for each isotope; these are shown in Table 7.1-22. Leakage rates itemized in the table are initial leakage rates at 11 8 days after reactor shutdown. Actual activity leakage of the isotopes decreases subsequently with time, based on their radioactivity decay constants. The normal time required to transfer spent fuel from the reactor vessel to the EVTM and f rom the EVTM to the ex-vessel storage tank is approximately one hour. In the event of the postulated accident considered here, within three hours after the initiation of the accident the EVTM would be moved to a location where the released radioactive gases would be purged to the gas cleanup system. This purging operation could be conducted at either the 7.1-28

Amendment XI January, 1982 recctor vessel or the ex-vessel storage tank. Normally the EVTM 8 is not purged. However, following the postulated accident, a purge would be provided to achieve rapid cleanup. The purge results in an exponential removal factor in addition to the 11 leakage rates and radioactive decay. O 8 Using the leakage rates itemized in Table 7.1-22, release of ll radioactivity from the EVTM to the RCB/RSB atmosphere was determined assuming that the EVTM is connected to a purging line and the radioactivity is purged in eight hours. No credit is taken for the reduced leakage rate during purgin_. Off-site 11 exposure was conservatively computed assuming the RCB and RSB ventilation systems continue to exhaust to the atmosphere. Actually, both systems are designed to reduce the exhaust flow 8 11 rate upon detecting high activity in the exhaust. The maximum off-site whole body dose is 2.13 x 10-2 mrem. Summaries of potential doses from this event at specific downwind ' distances are provided in Tables 7.1-5 through 7.1-12. Estimates of the potential population dose are provided in Table 7.1~13. 7.1.2.6.2 ACCIDENT 6.2 - SPENT FUEL CLADDING FAILURE IN THE EVTM

             - 100 PERCENT NOBLE GAS AND IODINE RELEASE This postulated acccident is identical to ACCIDENT 6.1, except the total inventory, 100 percent, of the noble gases and iodines contained in the spent fuel assembly is assumed to be released                11 instantaneously to the interior of the EVTM.      This assumed release represents an extremely conservative upper limit.

Initial isotopic concentrations in the EVTM and the initial activity leakage rates f rom the EVTM for this assumed release are itemized in Tables 7.1-21 and 7.1-22, respectively. Again, O 7.1-29

Amendment XI January, 1982

 '()      conservatively assuming continuous ventilation exhaust to the 4 8  11 atmosphere, the maximum off-site whole body dose is 2.13 mrem.

Doses at specific downwind distances and estimates of the potential population dose are provided in Tables 7.1-5 through 7.1-13. 7.1.2.6.3 ACCIDENT 6.3 - INADVERTENT OPENING OF A FLOOR VALVE WHILE A REACTOR PORT PLUG IS REMOVED i During refueling a port plug is removed from the reactor vessel head to allow transfer of fuel and other core assemblies between the reactor vessel and refueling machines. Radiation shielding and isolation of the reactor cover gas from the containment atmosphere is provided by a Floor Valve (FV) mounted over the transfer port prior to pcrt plug removal. When the FV is in position over the transfer port, without a refueling machine mated and sealed to its upper surface, the FV is closed and sealed providing containment between the reactor cover gas and the containment atmosphere. With a refueling machine (EVTM for example) mounted and sealed to the upper surface of the FV, the valve is opened to permit transfer of core components between the reactor vessel and the refueling machine. Inadvertent opening of the FV when it is not mated and sealed to a refueling machine is prevented by proper sequencing of refueling acticns, electrical 11 interlocks, and disconnection of the electrical power cable from the EVTM to the motor that opens the floor valve. However, to , assess the radiological consequences resulting from the inadvertent opening of a FV, this event is arbitrarily postulated. I 11 The earliest time for normal port plug removal is 30 hours after shutdown (based on anticipated refueling preparation efficiency). 8 The reactor cover gas inventory, at this time, is shown in Table (() 7.1-23. 7.1-30

Amendment XI January, 1982 With the port plug removed and the FV inadvertently opened, the 11 majority of this activity would remain in the reactor vessel bacause of Argon's high density and the low cover, gas pressure. For evaluation purposes all the reactor cover gas activity was cssumed to be released instantaneously to the RCB/RSB atmosphere. (During refueling the large equipment hatch connecting the RCB l and RSB is open.) To determine off-site radiological exposure it was further assumed that the RCB and RSB exhaust systems vent this activity directly to the atmosphere. The maximum off-site whole body dose is 1.08 mrem. Summaries of 4 g it potential doses at specific downwind distances are provided in Tables 7.1-5 through 7.1-12. Estimates of the potential population dose are provided in Table 7.1-13. 7 .1. 2 . 7 ACCIDENT 7.0 - SPENT FUEL HANDLING ACCIDENTS As discussed in Section 7.1.2.6, REFUELING ACCIDENTS, the design of the CRBRP refueling system does not employ an open fuel storage pocl. Therefore, dropping a fuel assembly into a fuel storage pool or dropping a heavy object onto a fuel rack in a fuel storage pool, postulated events normally evaluated in light-water reactor environmental reports, are not realistic occurrences in the CRBRP. Inadvertent dropping of a loaded spent fuel shipping cask during 11 fuel handling is considered to be a hypothetical event. The radiological consequences of this postulated event are discussed in the following section. 7.1.2.7.1 ACCIDENT 7.1 - SPENT FUEL SHIPPING CASK DROP 11 The spent fuel shipp'ing cask is normally raised and lowered in the 72-foot-deep cask access shaf t using the Reactor Service Building bridge crane, which is a double-reeved crane with two f 7.1-31

Amendment XI January, 1982 independent hooks, each capable of supporting the entire spent fuel shipping cask load. Failure of one will not result in cask drop. With a double failure needed to 4.nitiate a drop and a low handling frequency (about 20 times a year), it is not expected that inadvertent dropping of a spent fuel shipping cask in the cask access shaft will occur. As a precaution against a release, of radioactive material in the event a drop should occur, however, the cask is designed to withstand a 30-foot drop onto an unyielding surface without leakage. This is sufficient to meet the requirement of 10 CFR 71. (A 72-foot drop onto the concrete floor is less severe than the design drop.) Nevertheless, for purposes of accident analysis, it is postulated that a cask drop occurs which results in loss of cask integrity. The radiological consequences are evaluated using the source given in Table 7.1-24, which is based on the following conditions.

l. The fission gas inventory from one fully loaded spent

{ fuel cask (80-days cooling) is assumed released into the inner containment of the cask. It leaks at the design leak rate of the inner containment seals to the RSB and then to the atmosphere via the RSB ventilation system. No credit is taken for outer containment seals. (

2. The cask holds nine assemblies (six fuel assemblies and three blanket assemblies).

The maximum off-site whole body dose resulting from this postulated failure is 2.830 x 10-4 mrem. Summaries of potential 4 8 doses from this event at specific downwind distances are provided in Tables 7.1-5 through 7.1-12. Estimates of the potential population dose are provided in Table 7.1-13. 7.1-32

Amendment XI January, 1982 7.1.2.8 ACCIDENT 8.0 - ACCIDENT INITIATION EVENTS CONSIDERED IN DESIGN BASIS EVALUATION IN THE SAFETY ANALYSIS REPORT 7.1.2.8.1 ACCIDENT 8.1 - PRIMARY SODIUM IN-CvNTAINMENT STORAGE 11 TANK FAILURE DURING MAINTENANCE The primary sodium in-containment storage tank is located below the containment operating deck in a normally inerted cel). Cell

))

volume is approximately 45,000 cubic feet and the floor area 8 beneath the tank is 850 square feet. Cell walls are concrete, nominally six feet thick. Interior surfaces of the cell are protected with Engineered Safety Feature steel liners. 8 During normal operation, the drain tank is essentially empty and the cell atmosphere is inerted.In the event that major plant maintenance requires complete. draining of one of the primary 11 loops, the storage tank will be used to store the sodium coolant. Maximum volume of sodium stored in the tank will be 35,000 lh gallons and the sodium temperature will be maintained at approximately 400 degrees F. The cell atmosphere will remain inerted. Prior to deinerting and entry into the tank cell for maintenance of cell equipment, the cell will be prepared in order to reduce radiation exposure to maintenance personnel. The preparation will include allowing the Na-24 to decay and draining the sodium in the tank to a minimum level (<500 gal). Any sodium in excess

))

of this minimum level will be transferred to an ex-containment storage tank. The off-site doses for a storage tank failure following deinerting for maintenance as stated above, are enveloped by the following evaluation which characterizes an eccident which conservatively assumes failure of the storage tank when full. For the accident evaluation it was assumed that the primary sodium stored in the tank has decayed for 10 days after reactor shutdown. It was 7.1-33

Amendment XI January, 1982 further assumed that the accident occurs near the end of plant life (30 years) when the primary sodium coolant activity has reached its peak value. Radioactivity content of the sodium for 18 these conditions is shown in Table 7.1-18. This source term would result in personnel radiation exposure in excess of CRBRP ALARA guidelines and therefore prohibits 11 personnel entry. However, the calculations of this accident have been performed based upon not draining the tank. After de-inerting the cell atmosphere, manned access to the cell is via a 21 ft 2 shielded door. The evaluation assumes that the j) cell environment connects directly with the upper containment atmosphere via a hypothetical passageway equivalent in area to the cell door. At this time the total tank capacity, 35,000

-  gallons, is accumcd inctcntanccusly drained to the cell floor.

V The radiological impact of this postulated event was determined as follows:

1. Spilled sodium burns, releasing Na 2O as aerosol;

2. Radioisotope concentrations in the aerosol are proportional by. elemental weight to the initial 11 concentrations in the sodium;

3. Radioactive decay during the accident is conservatively o

neglected; 8

4. The RCB ventilation system is automatically shut down, 8

isolating containment from the outside atmosphere.

5. Leakage from the RCB to the confinement annulus was O computed based on the design leak rate of the RCB (0.1%

vol/ day at 10 psig) and the containment overpressure due to sodium burning; and 7.1-34

Amendment XI January, 1982

6. Release from the confinement annulus to the environment would be through the annulus filtration system. 8 GESOFIRE analyses of the postulated spill and resultant fire indicate a peak containment pressure of approximately 0.8 psig.

This peak pressure occurs about 40 hours following the postulated 11 spill. Containment pressure then decreases to ~ 0 psig approximately 75 hours after the start of the fire. The long duration of the accident results since no credit for fire fighting action was taken. Using the pressure / time history computed by GESOFIRE, HAA-3 analyses were used to determine the behavior of the aerosol generated during sodium combustion. The results of the analysis 8 indicate a total release of 3.4 kg of Na 2 O aerosol, containin9 11 2.5 kg of sodium, to the atmosphere over the 140-hour overpressure period. The maximum off-site whole body dose is 3.7 x 10-3 rem. Doses at specific downwind distances and estimates of the population dose 8 11 are provided in Tables 7.1-5 through 7.1-13. 7.1.2.8.2 ACCIDENT 3.2 - LARGE PRIMARY COOLANT SODIUM SPILL DURING OPERATION A large spill of primary sodium into an inerted Heat Transport System (HTS) cell during operation is arbitrarily postulated for purposes of this evaluation. For evaluation of cell integrity, an upper bound limit of approximately 35,000 gallons of primary g 11 O 7.1-35 ____---______J

Am2ndment XI January, 1982 l [/h

     's _    sodium at 1015 degrees F is arbitrarily assumed discharged to the HTS cell. It is further conservatively assumed that the primary 2

sodium has reached its peak activity level at the end of plant life (30 years) and that no decay of sodium activity has occurred prior to the spill. During operation the HTS cell is inerted and closed to the upper containment atmosphere. The RCB/RSB Hatch is closed, insuring containment integrity. The HTS cell walls are concrete, nominally six feet thick, and all interior surfaces of the cell are steel lined. The radiological impact of this postulated event was determined as follows:

1. Sodium reacts with the available oxygen in the inerted HTS cell (2% O2 ). The resultant fire releases Na2O as 8 an aerosol;

2. Radioisotope concentrations in the aerosol are 11 proportional by elemental weight to the initial concentrations in the sodium; l

3. Radioactive decay during the accident is conservatively neglected;

4. Twenty seven (27) percent.of the airborne aerosols are assumed to be instantaneously released to the upper 11 containment atmosphere.

O l 7.1-36

Amendment XI January, 1982

5. Leakage from the RCB to the confinement annulus was completed based on the design leak rate of the RCB (0.1%

vol/ day at 10 psig) and the containment pressure due to sodium burning.

6. Fallout (cloud depletion) of radioactive material during downwind transit is conservatively neglected.

SPRAY analysis of the postulated spill and resultant fire indicates a peak cell pressure of 14 psig. This peak pressure 8 11 occurs about five minutes after the beginning of the postulated spill. The sodium combustion rate decreases to zero within 2 hours. SPRAY and HAA-3 analyses were used to determine the time behavior of the aerosol generated during sodium burning. The analyses indicate that if no measures are taken to mitigate sodium burning, approximately 3.6 grams of Na 2 O would leak over a 30-day 8 period. The maximum off-site whole body dose is 3.26 x 10-5 rem. Doses 4 g j) at specific downwind distances and estimates of the population dose are provided in Tables 7.1-5 through 7.1-13. 7.1.2.8.3 ACCIDENT 8.3 - GROSS FAILURE OF EX-CONTAINMENT PRIMARY SODIUM STORAGE TANK The ex-containment primary sodium storage tanks are located in a l8 cell on the lowest level of the Intermediate Bay of the Steam Generator Building. The tanks will be used to store primary sodium only in the event maintenance requires drainage of a a large volume of reactor vessel sodium. The accident postulated 11 is an assumed failure which results in the complete spill of the 4 contained sodium to the cell floor. extremely unlikely. This postulated accident is g 7.1-37

fadd.Ed. XI January, 1982 ()Forconservatism, the postulated accident is assumed to occur near the end of plant life (30 years) when the radioactive content of the primary sodium has reached its peak. It is further assumed that the sodium has undergone radioactive decay for 10 days prior to charging the tank. The actual decay time is expected to be longer to allow for complete Na-24 decay. The radioactive content of the sodium for these conditions is shown 8 in Table 7.1-18. When an ex-containment sodium tank is full, access to the tank cell is prohibited and the cell is closed. The cell floor area 11 is approximately 2,400 square feet. The' floor of the cell is protected with a steel catch pan, 3/8-inch thick, which extends vertically upward to a minimum height such that the maximum potential sodium spill can be safely contained within the steel-lined volume. 11 ( ) The postulated accident results in the spill of 45,000 gallons (~ 300,000 lbs . ) of 400 degrees F sodium to the cell floor. This 3 spill represents 100 percent of the contained volume in one of the two storage vessels in the cell and is an extremely conservative upper bound. The postulated spill covers the entire 3 floor of the cell. The radiological impact of this postulated spill was determined as follows:

1. Spilled sodium reacts with the available oxygen in the cell (inerted, 2% 0 ),2 burns and releases Na20 as 4 aerosol; O

7.1-38

i 1 Am:ndm:nt XI l January, 1982

2. Radioisotope concentrations in the aerosol are jj proportional by elemental weight to the initial concentrations in the sodium;

3. Radioactive decay during the accident is conservatively neglected;

4. Leakage of aerosol from the cell to the Intermediate Bay of the Steam Generator Building (SGB) was computed based jj on a design cell leak rate of 0.6 percent vol/ day at 3.9 psig, and the cell overpressure due to sodium burning;

5. It was conservatively assumed that the SGB ventilation system continues to operate for the duration of the accident and that all aerosol leaked to the SGB vents 11 directly to the atnosphere; and

6. No credit for plateout or settling of the aerosol in the SGB ventilation system was taken.

Sodium fire analyses indicate a peak cell pressure of 4.0 psig 4 approximately 10 minutes after the postulated spill. The cell y pressure then decreases to atmospheric pressure roughly eight 8 days after the spill. SOFIRE II and HAA-3 analyses were used to determine the time behavior of the aerosol generated during sodium burning. With the conservat,ive assumption of continuous SGB venting, approximately 0.1 kg of Na 20 aerosol would be 4 8 11 released to the atmosphere over the eight-day overpressure period. The maximum off-site whole body dose is 4.2 x 10-5 rem. Doses at 11 4 8 specific downwind distances and estimates of the population dose are provided in Tables 7.1-5 through 7.1-13. O 7.1-39 L

Amendment XI Jamary,1982 7.1.2.8.4 ACCIDENT 8.4 - RUPTURE OF THE EX-VESSEL STORAGE TANK SODIUM COOLING SYSTEM DURING OPERATION There are three Ex-Vessel Storage Tank (EVST) sodium cooling circuits, two normal and a backup. The normal cooling circuits are used alternately to cool sodium circulated to and from the EVST. Each is located in a separate cell adjacent to the EVST. The pump suction line for each normal cooling circuit exits from the EVST at an elevation above the normal sodium level in the tank. There is an internal downcomer within the EVST which extends down below the sodium level. An isolation valve in the 11 pump suction line is located approximately at the tank outlet elevation. The postulated accident is a rupture of the pump suction line in the operating normal cooling circuit. In the event of this postulated accident, the other normal cooling circuit would be () brought on line to permit continued EVST cooling. The rupture assumed to occur at the low point of the pump suction line, is resulting in the siphoning of sodium down to the level of the internal downcomer within the EVST. This postulated rupture results in the maximum possible quantity of sodium discharged from the system during operation. Approximately 7,500 gallons I (~57,000 lbs.) of 475sdegree F sodium would be spilled into the cell. For conservatism, it is assumed that the accident occurs near the end of the plant life (30 years) and shortly after a refueling operation when the EvsT sodium activity has reached its peak. Radioactive content of the EVST sodium under these 4 8 conditions is shown in Table 7.1-19. The maximum spill postulated would require a simultaneous major piping f ailure plus failure of the remotely operated isolation valve. As such, the accident postulated is extremely unlikely and is not expected to occur over the life of the plant. 7.1-40

Am:ndm:nt XI January; 1982 During operation, the sodium cooling circuit cell is inerted (2% 8 0)2 and closed. Interior surfaces of the cell are protected with a steel liner approximately 3/8-inch thick. Cell walls are nominally two-foot thick concrete. The free volume of the cell is approximately 14,960 cubic feet and the cell floor area is 680 11 square feet. The radiological impact of this postulated event was determined as follows:

1. Sodium reacts with the available oxygen in the inerted cell ( 2% 0).

2 The resultant fire releases Na20 as aerosol;

2. Radioisotope concentrations in the aerosol are 11 proportional by elemental weight to the initial concentrations in the sodium;

3. Radioactive decay during the accident is conservatively O

neglected;

4. Leakage of airborne aerosol from the cell to the Reactor Service Building (RSB) was computed based on a design 11 cell leak rate of 0.36 percent vol/ day at 12 psig;

5. It was conservatively assumed that the RSB ventilation system continues to operate,for the duration of the accident and that the aerosol leaked to the RSB vents directly to the atmosphere; and

6. No credit for plateout or settling of the aerosol in the RSB ventilation system was taken.

SOFIRE II analyses of the postulated spill and resultant fire indicate a peak cell pressure of 3.78 psig. This peak pressure h occurs two hours following the postulated spill. The cell 7.1-41

Amendment XI January, 1982 pressure then decreases to approximately 1.4 psig after 96 hours. g. 'll After one day, the burning rate is less than 10-6 lb/hr-ft2, and only 56 pounds of the spilled sodium has reacted with the available oxygen in the cell. SOFIRE II and HAA-3 analyses were used to determine the time behavior of the aerosol generated during sodium burning. With the conservative assumption of continuous RSB venting, 2.0 grams 11 of Na 0 would be released to the atmosphere. Total release time 2 8 is four days. An accident in the backup cooling circuit would be less severe than the one described above, since this is a " raised" circuit which prevents a major spill involving siphoning of the EVST. The total amount of sodium that could be spilled from the backup , . cooling circuit is ~ 35,000 lbs. f D) The maximum off-site whole body dose is 4.3x10-4 mrem. Doses at I 3 11 specific downwind distances and estimates of the population dose , are provided in Tables 7.1-15 through 7.1-13. 7.1.2.8.5 ACCIDENT 8.5 - LARGE STEAM LINE BREAK The consequence of a large steam line break has been analyzed for rupture of the main steam line between the main steam line isolation valves and the manifold which joins the three main steam lines. For this case the superheater isolation valves close in each loop and reactor trip occurs on high steam-feedwater ratio. After the isolation valves close, the system is depressurized and the sensible and decay heat from the core is removed by operation of the pressure relief valves until the heat load reaches 45 MWT at which time the SGAHRS is capable of removing the heat without venting. O Main steam line rupture is a transient emergency event for which the plant is designed. Thus, no other system in the plant will 7.1-42

Am:ndm::nt XI January, 1982 experience conditions which exceed the design specifications and no other plant damage will result. The only radiological consequence of the failure will be the release of a large amount of steam-water which contains a low concentration of tritium. The level of tritium in the steam system at end of plant life (30 jj years) is 0.62 uCi/cc. The amount of water released as a result of a main steam line ~ break is approximately 312,000~ pounds. Of this amount, about jj 9,000 pounds are released from th9 pipe break before the isolation valves close and 303,000' pounds ~are vented from the Power Relief Valves to remove heat from the_ system. This 303,000 pounds of water will contain 85. Curies of $ritium which will be jj I released over a 5.7 hour period. 7 ] ~ The maximum of f-site whole body dose is 4.7 mrem. Doses at 11 l4 specific downwind distances and estimates of the potential

        . population dose are provided in Tables 7.1-5 through 7.1-13.                        8 7.1.3

SUMMARY

_OF PLANT ACCIDENT- DC:SES

     --            s.                                    _ _
                                                                ~            '

Potential dosen for each postulated a'ccident at a number of downwirid7 distances of interest are summarized in Tables 7.1-5 8 through 7'.1-12. This sumnary indicates that all potential doses fall well within the limits of 10 CFR 100. A large margin also 11 exists between the potential doses and the'10 CFR 20 limits. Th'e whole body population dose 'for each -accident .is shown in Table 7.1-13. This dose includes both the external gamma dose and the internal whole body dose due to inhalation of radioactive _ caterial. Twp wh61e-body populatlon' doses were estimated for "each acc.i dent . The maximum. prediction assumes that the wind persistG~towards the E for the' duration of the accident, while 11

                                                       ~
            ~                                        ,
                                                                   ~
                  , ~                         7.1-43
                -                                        s

II , . ] ,

                               /                                                        '  '

l, . J

                                                                                      -                                                                                       Ameldment XI
                                                                                '                                                                                             January, 1982
          .: ,;, r . r. , ;                                                      ,
                                    .)

1 the minimum estimate, assumes wind persistence towards the NNW for

         ,                                            the duration of the accident.. .These two directions correspond,
                                .# respect ve                                i     y, l to the most and leart populated azimuthal sectors,
  ]

based on the projected population' distribution for the year 2010. c

    ,/                                                                                                 ,
                                             .e=      4
                                                  .f
                              .                                                              l *
           ,     1 .! '

t' s=

1 4

l 1 ,i ?/ , n ie (< if. .e #- i i

                  ?                                     '.

t f . e, , /

               .ll                            ;)                      ,

1,

                 ,1
                                ,=                    ,1 e

t'

e l t. ,

i, t 4

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                     ,             /                           .

t

                                                               .l 4

4 1 s k t (. :c ii

i f 7.1-44 I - - . . . - - - _ . - - - - . . _ . - . - _ . . _ - - - .

Amerdment XI January, 1982 TABLE 7.1-1 ATMOSPHERIC DILUTION FACTORS 3 50 PERCENT PROBABILITY x/Q VALUES (sec/m )

Distance (miles) 2-hr 8-hr 16-hr 72-hr 624-hr_

0.42 1.01E-3 1.55E-4 1.23E-4 7.69E-5 9.06E-5 0.5 8.25E-4 1.27E-4 9.28E-5 5.78E-5 6.76E-5 0.6 7.16E-4 1.07E-4 6.91E-5 4.30E-5 5.02E-5 0.7 6.19E-4 9.29E-5 5.43E-5 3.36E-5 3.93E-5 1.0 4.29E-4 6.51E-5 2.70E-5 1.67E-5 1.93E-5 1.5 2.81E-4 4.30E-5 1.07E-5 6.69E-6 7.73E-6 2.0 2.00E-4 3.03E-5 5.61E-6 3.50E-6 4.06E-6 2.5 1.59E-4 2.30E-5 3.58E-6 2.29E-6 2.60E-6 3.0 1.26E-4 1.83E-5 2.58E-6 1.60E-6 1.85E-6 11 h 3.5 1.03E-4 1.49E-5 1.96E-6 1.19 E- 6 1.40E-6 4.0 8.69E-5 1.24E-5 1.55E-6 9.35E-7 1.llE-6 4.5 7.49E-5 1.09E-5 1.26E-6 7.66E-7 9.06E-7 5.0 6.58E-5 9.46E-6 1.06E-6 6.42E-7 7.64E-7 7.0 4.21E-5 6.04E-6 5.87E-7 3.66E-7 4.32E-7 7.5 3.90E-5 5.57E-6 5.28E-7 3.30E-7 3.88E-7 9.0 3.07E-5 4.44E-6 4 .27 E-7 2.65E-7 3.10E-7 10.0 2.73E-5 3.99E-6 3.77E-7 2.31E-7 2.72E-7 15.0 1.70E-5 2.46E-6 2.28E-7 1.36E-7 1.63E-7 20.0 1.21E-5 1.76E-6 1.56E-7 9. 4 7 E- 8 1.14E-7 21.0 1.14E-5 1.66E-6 1. 47 E-7 8.91E-8 1.07E-7 25.0 9.26E-6 1.34E-6 1.17E-7 7,22E-8 8.67E-8 35.0 6.43E-6 9.33 E-7 7.98E-8 4.89E-8 5.82E-8 45.0 4.88E-6 7.60E-7 5.89E-8 3.71E-8 4.37E-8 50.0 4.32E-6 6.25E-7 5.16E-8 3.29E-8 3.90E-8

*Soe Section 2.6                                                               h 7.1-45

  ._ .._m _ ._ . . __. _ . . . . _ . .              ._ - . . . _ . _ . _ _ . _.       .-_ .__ ____.._. .

4 f r lO !- TABLE 7.1-2 1 l i 1 } AVERAGE ENERGY.PER DISINTEGRATION . i

!                                                                 Beta               Gama

! Isotope (MeV) (MeV) i -

i. H-3 0.006 0 ,

                                     - C-14                       0.052                 0                       ,
!                                      Na-22                      0.182              2.195 Na-24                      0.463-             4.123.
                                     . Ne-23                      1.460              0.-160                     -

! Ar-39 0.188 0 Ar-41 0.406 1.280 Mn-54 '0.00021 0.835 i Co-58 0.0237 0.977 ,. i Co-60 0.105 2.51

Kr-83m 0.036 0.00248

) Kr-85m 0.277 0.158 i Kr-85 0.230 0.002 Kr-87 1.324 0.793 f Kr-88 0.376 1.950 Sr-89 0.488 -0.000082 Sr-90 0.182 0.0 Y-90 0.930 0.0 Y-91 0.515 0.0036-Zr-95 0.130 0.725 Nb-95 0.0532 0.765 Ru-103 0.077 0.474 Ru-106 0.013 0.0 , Sb-125 0.335 0.121 Te-129m 0.621 0.0414 Te-129 0.407 0.108 Te-132 0.10 0.216 (Continued) 7.1-46 i

.i

A!!ENDt1ENT VIII February 1977 O TABLE 7.1-2 (Continued) Beta Gamma Isotope (MeV) (MeV) I-1 31 0.197 0.371 I-132 0.448 2.40 8 Xe-131m 0.143 0.02 Xe-133m 0.189 0.042 Xe-133 0.135 0.045 Xe-135m 0.095 0.432 Xe-135 0.316 0.247 Xe-138 0.612 1.183 Cs-134 0.166 1.59 Cs-136 0.139 2.23 Cs-137 0.246 0.563 Ba-140 0.284 0.236 La-140 0.397 2.12 Ce-141 0. 31 5 0.0695 Ce-144 0.1 01 0.0163 Pr-143 0.31 0 0.0 Nd-147 0.335 0.122 Pm-147 0.070 0.0 0 7.1-47

Amendment XI January, 1982 i i TABLE 7.1-3 { INHALATION DOSE CONVERSION FACTORS, Fg rem /Ci Inhaled

Isotope Isotope Lung Bone Thyroid Whole Body H-3 1.58 E2 -

1.58 E2 1.58 E2 Na-22 1.30 E4 1.30 E4 1.30 E4 1.30 E4 Na-24 1.28 E3 1.28 E3 1.28 E3 1.2 8 E3 Mn-54 1.75 E5 - - 7.87 E2 Co-58 1.36 E5 - - 2.59 E2 Co-60 7.46 E5 - - 1.85 E3 Sr-89 1.75 ES 3.80 E4 - 1.0 9 E3 () Sr-90 Y-90 1.20 E6 2.12 E4 1.24 E7 2.61 E2 7.62 E5 7.01 Y-91 2.13 ES 5.78 E4 - 1.55 E3 Zr-95 2.21 E5 1.34 E4 - 2.91 E3 Nb-95 6.31 E4 1.76 E3 - 5.26 E2 Ru-103 6.31 E4 1191 E2 - 8.23 El Ru-106 1.18 E6 8.64 E3 - 1.0 9 E3 Sb-125 2.18 ES 6.67 E3 6.75 1.58 E3 Te-129m 1.45 E5 1.22 E3 4.30 E2 1.98 E2 Te-129 2.42 E2 6.22 E-3 4.87 E-3 1.55 E-3 Te-132 3.60 E4 3.25 El 2.37 El 2.02 El I-131 - 3.15 E3 1.49 E6 2.56 E3 I-132 - 1.45 E2 1.43 E4 1.45 E2 I-133 - 1.0 8 E3 2.69 ES 5.65 E2 I-134 - 8.06 El 3.73 E3 7.69 El I-135 - 3.35 E2 5.60 E4 3.21 E2 O

         *From NUREG-017 2 7.1-48

Amendment XI January, 1982 TABLE 7.1-3 (Continued) INHALATION DOSE CONVERSION FACTORS, F y i rem /Ci Inhaled

Isotope

! Isotope Luno Bone Ihyroid Whole Body 1 f Cs-134 1.22 E4 4.66 E4 - 9.10 E4 Cs-136 1.50 E3 4.88 E3 - 1.38 E4 Cs-137 9.40 E3 5.98 E4 - 5.35 E4 Ba-140 1.59 ES 4.88 E3 - 3.21 E2 La-140 1.70 E4 4.30 El - 5.73 i Ce-141 4.52 E4 2.49 E3 - 1.91 E2 11 l Co-144 9.72 E5 4.29 ES - 2.30 E4 Pr-143 3.51 E4 1.17 E3 - 5.80 El Pr-144 1.27 E2 3.76 E-3 - 1. 91 E- 4 h Nd-147 2.76 E4 6.59 E2 - 4.56 El Pm-147 6.60 E4 8.37 E4 - 3.19 E3 Pu-238 1.82 E8 2.74 E9 - 6.90 E7 Pu-23 9 1.72 E8 3.19 E9 - 7.7 5 E7 Pu-240 1.72 E8 3.18 E9 - 7.73 E7 Pu-241 1.52 E5 6.41 E7 - 1.29 E6 Pu-242 1.65 E8 2.95 E9 - 7 .46 E7

 *From NUREG-0172 l

l O l l l 7.1-49 1

Amendment XI O January, 1982 TABLE 7.1-4 POPULATION DISTRIBUTION FOR THE E AND NNW SECTORS

Population Within Radial Interval Radial Interval E NNW (miles) _

0-1 40 10 11 1-2 70 0 2-3 110 0 3-4 30 0

4-5 40 100 5-10 3400 1100 10-20 32,600 3,600 20-30 124,000 1,400 30-40 29,500 4,200 40-50 21,700 3,700

Population distribution is the projected distribution for census year 2010 i

7.1-50 O

Amsndmsnt XI Jcnuary, 1982 TABLE 7.1-5

SUMMARY

OF POTENTIAL DOSES FROM PLANT ACCIDENTS MINIMUM EXCLUSION DISTANCE - 2200 FEET

mrem / event ACCIDENT WHOLE BODY BONE LUNG THYROID 2.1 5.50 0. 5.50 5.50 3.1 1.37E-6 0. 1.37E-6 1.37E-6 3.2 5.18E-6 0. 5.18E-6 5.18E-6 3.3 7.71E-1 0. 5.92-2 0.

4.1 2.37El 3.15E2 1.77El 8.74El 4.2 8.75 2.36E2 1.16El 7.45 5.1 8.40E-5 0. 2.10E-6 0. 5.2 1.30E-2 0. 1.30E-2 1.30E-2 6.1 2.13E-2 2.06E-2 1.46E-5 9.64 6.2 2.13 2.06 1.46E-3 9.64E2 6.3 1.08 0. 1.98E-2 1.88E-4 7 .1 2.83E-4 3.llE-4 2.86E-6 1.42E-1 8.1 3.68 4.93El 2.77 1.37El 8.2 3.26E-2 2.38E-2 1.03E-2 1.89E-2 8.3 4.22E-2 5.63E-1 3.16E-2 1.56E-1 8.4 4.29E-4 1.16E-2 5.67E-4 3.65E-4 8.5 4.71 0. 4.71 4.71 10CFR20 5.00E2 1. 50 E3 l (mrem /yr) 10CFR100 2.50E4 1.50E5** 7.50E4** 3.00E5 (mrem / event)

Shortest distance from containment to the far bank of the Clinch River (Far bank is site boundary) 11

   **Not covered in 10CFR100; used as guideline values

! 7.1-51

Amendment XI January, 1982 TABLE 7.1-6

SUMMARY

OF POTENTIAL DOSES FROM PLANT ACCIDENTS DOWNWIND DISTANCE - 0.6 MILE

mrem / event ACCIDENT WHOLE BODY BONE LUNG THYROID 2.1 3.90 0. 3.90 3.90 3 .1 9.71E-7 0. 9.71E-7 9.71E-7

_ 3.2 3.67E-6 0. 3.67E-6 3.67E-6 r 3.3 5.47E-1 0. 4.19E-2 0. 4.1 1.68El 2.23E2 1.25El 6.20El 4.2 6.20 1.67E2 8.22 5.28 5.1 5.96E-5 0. 1.49E-6 0. 5.2 9.22E-3 0. 9.22E-3 9.22E-3 6.1 1.51E-2 1.46E-2 1.04E-5 6.83 6.2 1.51 1.46 1.04E-3 6.83E2 () 6.3 7.1 7.66E-1 2.01E-4 0. 2.20E-4 1.40E-2 2.03E-6 1.33E-4 1.01E-1 11 8.1 2.61 3.49El 1.96 9.69 8.2 2.31E-2 1.69E-2 7.32E-3 1.34E-2 8.3 2.99E-2 3.99E-1 2.24E-2 1.llE-1 8.4 3.04E-4 8.22E-3 4.02E-4 2.59E-4 8.5 3.34 0. 3.34 3.34 10CFR20 5.00E2 1.50E3 (mrem /yr) 10CFR100 2.50E4 1.50E5 7.50E4 3.00E5

           - (mrem / event) l l

Nearest Residence i

t I !O 7.1-52

   - . - .      -_    _ . _ _ _ - - _ - . - _ _ - - . . _ ._          _   _       __ -__    - _ _ , _ . _ _ .        _ _ . - _ _ _ ~

Am:ndm:nt XI Jcnusry, 1982 TABLE 7.1-7

SUMMARY

OF POTENTIAL DOSES FROM PLANT ACCIDENTS DOWNWIND DISTANCE - 1 MILE

mrem / event WHOLE BODY BONE LUNG THYROID ACCIDENT 2.34 0. 2.34 2.34 2.1 3 .1 5.82E-7 0. 5.82E-7 5.82E-7 3.2 2.20E-6 0. 2.20E-6 2.20E-6 3.3 3.28E-1 0. 2.51E-2 0.

4.1 1.01El 1.34E2 7.52 3.71El 4.2 3.72 1.00E2 4.93 3.17 5.1 3.57E-5 0. 8.93E-7 0. 5.2 5.53E-3 0. 5.53E-3 5.53E-3 6.1 9.05E-3 8.76E-3 6.21E-6 4.10 6.2 9.05E-1 8.76E-1 6.21E-4 4.10E2 6.3 4.59E-1 0. 8.42E-3 7.99E-5 7.1 1.20E-4 1.32E-4 1.22E-6 6.04E-2 8.1 1.56 2.09El 1.18 5.81 y 8.2 1.38E-2 1.01E-2 4.39E-3 8.04E-3 8.3 1.7 9E-2 2.39E-1 1.34E-2 6.63E-2 8.4 1.82E-4 4.93E-3 2.41E-4 1.55E-4 8.5 2.00 0. 2.00 2.00 10CFR20 5.00E2 1.50E3 (mrem /yr) 10CPR100 2.50E4 1.50E5 7.50E4 3.00E5 (mrem / event)

Nearest Recreational Area O

7.1-53

Amendment XI Janunty, 1982 TABLE 7.1-8

SUMMARY

OF POTENTIAL DOSES FROM PLANT ACCIDENTS DOWNWIND DISTANCE - 2.5 MILES

mrem / event ACCIDENT WHOLE BODY BONE LUNG THYROID

0. 8.64E-1 8,64E-1 2.1 8.64E-1 3.1 2.16E-7 0. 2.16E-7 2.15E-7 3.2 8.15E-7 0. 8.15E-7 8.15E-7 3.3 1.21E-1 0. 9.31E-3 0.

4.1 3.72 4.95El 2.78 1.37El 4.2 1.37 3.71El 1.82 1.17 5.1 1.32E-5 0. 3.30E-7 0. 5.2 2.04E-3 0. 2.04E-3 2.04E-3 6.1 3.34E-3 3.23E-3 2.29E-6 1.51 6.2 3.34E-1 3.23E-1 2.29E-4 1.51E-2 () 6.3 7 .1 1.70E-1 4.44E-5 0, 4.88E-5 3.llE-3 4.49E-7 2.95E-5 2.23E-2 11 8.1 5.80E-1 7.76 4.36E-1 2.15 8.2 5.13E-3 3.75E-3 1.63E-3 2.98E-3 8.3 6.63E-3 8.84E-2 4.96E-3 2.45E-2 8.4 6.74E-5 1.82E-3 8.90E-5 5.73E-5 8.5 7.39E-1 0. 7.39E-1 7.39E-1 10CPR20 5.00E2 1.50E3 (mrem /yr) 10CFR100 2.50E4 1.50E5 7.50E 3.00E5 (mrem / event

Low Population Zone (LPZ)

O 7.1-54

Amendment XI January, 1982 TABLE 7.1-9

SUMMARY

OF POTENTIAL DOSES FROM PLANT ACCIDENTS DOWNWIND DISTANCE - 4 MILES

mrem / event ACCIDENT WHOLE BODY BONE LUNG THYROIO 2.1 4.73E-1 0. 4.73E-1 4.73E-1 3 .1 1.18E-7 0. 1.18E-7 1.18E-7 3.2 4.46E-7 0. 4.46E-7 4.46E-7 3.3 6.63E-2 0. 5.09E-3 0.

4.1 2.04 2 .'/ l El 1.52 7.52 4.2 7.53E-1 2.03El 9.98E-1 6.41E-1 5.1 7.22E-6 0. 1.81E-7 0. 5.2 1.12E-3 0. 1.12E-3 1.12E-3 6.1 1.83E-3 1.77E-3 1.26E-6 8.29E-1 g 6.2 1.83E-1 1.77E-1 1.26E-4 8.29El 6.3 9.29E-2 0. 1.70E-3 1.62E-5 . 7 .1 2.43E-5 2.67E-5 2.46E-7 1.22E-2 8.1 3.17E-1 4.24 2.38E-1 1.18 8.2 2.80E-3 2.05E-3 8.88E-4 1.63E-3 8.3 3.63E-3 4.84E-2 2.72E-3 1.34E-2 8.4 3.69E-5 9.98E-4 4.88E-5 3.14E-5 8.5 4.05E-1 0. 4.05E-1 4.05E-1 l l 10CFR20 5.00E2 1.50E3 (mrem /yr) I 10CFR100 2.50E4 1.50E5 7.50E4 3.00E5 l (mrem / event)

          ---. _=

Nearest Dairy l

l l O 7.1-55 l

Amendment XI January, 1982 () TABLE 7.1-10

SUMMARY

OF POTENTIAL DOSES FROM PLANT ACCIDENTS DOWNWIND DISTANCE - 7 MILES

9 mrem / event ACCIDENT WHOLE BODY BONE LUNG THYROID 2.1 2.31E-1 0. 2.31E-1 2.31E-1 3 .1 5.71E-8 0. 5.71E-8 5.71E-8 3.2 2.16E-7 0. 2.16E-7 2.16E-7 3.3 3.21E-2 0. 2.47E-3 0.

4.1 9.95E-1 1.32El 7.43E-1 3.67 4.2 3.68E-1 9.91 4.87E-1 3.13E-1 5.1 3.53E-6 0. 8.82E-8 0. 5.2 5.46E-4 0. 5.46E-4 5.46E-4 6.1 8.95E-4 8.65E-4 6 .13 E-7 4.05E-1 6.2 8.95E-2 8.65E-2 6 .13 E- 5 4.05El () 6.3 7 .1 4.54E-2 1.19E-5 0. 1.31E-5 8.32E-4 1.20E-7 7.90E-6 5.96E-3 l 8.1 1.53E-1 2.05 1.15E-1 5.70E-1 11 l 8.2 1.36E-3 9.92E-4 4.30E-4 7.89E-4 r 8.3 1.77E-3 2.36E-2 1.33E-3 6.55E-3 8.4 1.80E-5 4.87E-4 2.38E-5 1.53E-5 8.5 1.98E-1 0. 1.98E-1 1.98E-1 10CFR20 5.00E2 1.50E3 l ! (mrem /yr) 10CFR100 2.50E4 1.50E5 7.50E4 3.00E5 (mrem / event)

Nearest Population Center > 2500 (Kingston)

O 7.1-56 l .

Amendment XI Jcnunry, 1982 TABLE 7.1-11

SUMMARY

OF POTENTIAL DOSES FROM PLANT ACCIDENTS DOWNWIND DISTANCE - 21 MILES

mrem / event ACCIDENT WHOLE BODY BONE LUNG THYROID 2.1 6.05E-2 0. 6.05E-2 6.05E-2 3 .1 1.55E-8 0. 1.55E-8 1.55E-8 3.2 5.85E-8 0. 5.85E-8 5.85E-8 3.3 8.70E-3 0. 6.68E-4 0.

4.1 2.61E-1 3.47 1.95E-1 9.61E-1 4.2 9.63E-2 2.60 1.28E-1 8.20E-2 5.1 9.24E-7 0. 2.31E-8 0. 5.2 1.43E-4 0. 1.43E-4 1.43E-4 6.1 2.34E-4 2.27E-4 1.61E-7 1.06E-1 6.2 2.34E-2 2.27E-2 1.61E-5 1.06El 11 6.3 1.19E-2 0. 2.18E-4 2.07E-6 7 .1 3.llE-6 3.42E-6 3.15E-8 1.56E-3 8.1 4.16E-2 5.56E-1 3.13E-2 1.54E-1 8.2 3.68E-4 2.69E-4 1.17E-4 2.14E-4 8.3 4.64E-4 6.19E-3 3.48E-4 1.72E-3 8.4 4.72E-6 1.28E-4 6.24E-6 4.02E-6 8.5 5.18E-2 0, 5.18E-2 5.18E-2 10CFR20 5.00E2 1.50E3 (mrem /yr) 10CFR100 2.50E4 1.60E5 7.50E4 3.00E5 (mrem / year)

Nearest Population Center > 100,000 (Knoxville)

O 7.1-57

Amendment XI January, 1982 t TABLE 7.1-12

SUMMARY

OF POTENTIAL DOSES FROM PLANT ACCIDENTS DOWNWIND DISTANCE - 50 MILES mrem / event ACCIDENT WHOLE BODY BONE LUNG THYROID 2.1 2.20E-2 0. 2.20E-2 2.20E-2 3.1 5.86E-9 0. 5.86E-9 5.86E-9 3.2 2.22E-8 0. 2.22E-8 2.22E-8 3.3 3.30E-3 0. 2.53E-4 0. 4.1 9.48E-2 1.26 7.08E-2 3.50E-1 4.2 3.50E-2 9.44E-1 4.64E-2 2.98E-2 5.1 3.36E-7 0. 8.40E-9 0. , 5.2 5.20E-5 0. 5.20E-5 5.20E-5 6.1 8.52E-5 8.24E-5 5.84E-8 3.86E-2 6.2 8.52E-3 8.24E-3 5.84E-6 3.86 () 6.3 7 .1 4.32E-3 1.13E-6 0. 1.24E-6 7.92E-5 1.14E-8 7.52E-7 5.68E-4 11 8.1 1.57E-2 2.llE-1 1.18E-2 5.85E-2 8.2 1.39E-4 1.02E-4 1.42E-5 8.10E-5 8.3 1.69E-4 2.25E-3 1.26E-4 6.24E-4 8.4 1.72E-6 4.64E-5 2.27E-6 1.46E-6 8.5 1.88E-2 0. 1.88E-2 1.88E-2 10CFR20 5.00E2 1.50E3 (mrem /yr) 10CFR100 2.50E4 1.50E5 7.50E4 3.00E5 (mrem / event) O 7.1-58

Araendment XI Janunty, 1982 TABLE 7.1-13

SUMMARY

OF POTENTIAL WHOLE BODY POPULATION DOSES FROM PLANT ACCIDENTS Whole Body Population Dose Minimum Estimate Maximum Estimate Accident Number (Man-rem) (Man-rem) 2 .1 1.41E-1 1.75E+0 3.1 3.52E-8 4.35E-7 3.2 1.33E-7 1.65E-6 3.3 1.98E-2 2.45E-1 3.4 1.67E-2 2.06E-1 4.1 6.09E-3 7.53E-2 4.2 2.25E-1 2.78 5.1 2.16E-6 2.67E-5 5.2 3.34E-4 4.13E-3 6.1 5.47E-4 6.77E-3 6.2 5.47E-2 6.77E-1 11 6.3 2.77E-2 3.43E-1 7 .1 7.27E-6 8.99E-5 8.1 9.46E-2 1.17 8.2 8.38E-4 1.04E-2 8.3 1.08E-3 1.34E-2 l l 8.4 1.10E-5 1.36E-4 l 8.5 1.21E-1 1.50 i O 7.1-59

l@ TABLE 7.1-14 HAS BEEN DELETED 4 lO G 7.1-60 t i ' - - _ NWWe_

4FQ, _ _

Amnndmant XI January, 1982 TABLE 7.1-15 RUPTURE OF THE NOBLE GAS STORAGE VESSEL Cell Leak Tightness Assumed Initial Total Inventory Radioactivity in the Released From NGSV the Plant IEQtgpg ( Cil_._, (Cit. 11 Xe-133 2.34E5 1.07E2 Xe-135 4.40E4 0.19 Kr-88 L1DIl 3.4E-4 Total 2.79ES 1.07E2 O No Cell Leak Tightness Assumed i Initial Total Inventory Radioactivity in the Released From l NGSV the Plant Isnt99g (Ci) {Cil l j Xe-133 2.34E5 5.6E2 Xe-135 4.40E4 7.7 Kr-88 L1DE2 LE-2 Total 2.79E5 5.7E2 O 7.1-61

l i i i

3 !O 4 I a 4 4 i a 4 ;

?

i ' 4 J I r 4 I q t 1 l t I 1 I k ! TABLE 7.1-16 i i HAS BEEN DELETED 1 I f i i 1 i i t i G ; 7.1-62 i e f

l 1 Amendmnt XI 1 January, 1982 TABLE 7.1-17 TOTAL EXCESS COVER GAS LEAKAGE FOR ACCIDENT 5.1 Leakage Isotope (Curies) Xel31m 1.3E-6 Xel33m 1.lE-5 Xel33 3.8E-4 Xe135m 2.lE-5 Xel35 3.7E-4 Xe138 5.4E-5 Kr83m 1.5E-5 Kr85m 4.3E-4 Kr85 8.6E-7 Kr87 4 .3 E- 5 Kr88 7.0E-5 Total 1.4E-3 i l l i 4 0 7.1-63

h nt XI January, 1982 TABLE 7.1-18 RADIOACTIVE CONTENT OF PRIMARY SODIUM COOLANT

A Ci/gm Days _After Shutdown ISOTOPE A la Na-24 2.94 4.32E-1 Na-22 3.49 3.46 Cs-137 42.1 4.21El Cs-136 8.7 5.25 Cs-134 5.35 5.30 Sb-125 .241 2.40E-1 I-131 24.8 1.05El Te-132 1.76 2.08E-1 I-132 16.7 1.98 Te-129M .359 2.93E-1 11 Te-129 .359 2.93E-1 Sr-89 .055 4.80E-2 Sr-90 .034 3.40E-2 Y-90 .034 3.40E-2 Y-91 .0156 1.40E-2 Zr-95 .0292 2.60E-2 Nb-95 .0292 2.60E-2 Ru-103 .0415 3.50E-2 Ru-106 .0287 2.80E-2 Rh-106 .0287 2.80E-2 Sb-127 1.82 2.93E-1 Te-127M .104 9.80E-2 Te-127 .124 9.80E-2 Ba-140 .0327 1.90E-2 O

7.1 64

h nt XI January, 1982 TABLE 7.1-18 (Continued) RADIOACTIVE CONTENT OF PRIMARY SODIUM COOLANT

4 A Ci/gm Days After_ Shutdown ISOTOPE A 1A La-140 .0327 1.90E-2 Ce-141 .0387 3.10E-2 Ce-144 .0229 2.20E-2

Pr-144 .0229 2.20E-2 Pr-143 .0274 1.70E-2 Ed-147 .0128 7.00E-3 Pm-147 .0128 1.30E-2 Pu-238 8.0E-3 8.00E-3 11 Pu-239 2.12E-3 2.10E-3 Pu-240 2.77E-3 2.80E-3 2.30E-1 t Pu-241 .23 Pu-242 5.9E-6 5.90E-6 Np-238 2.45E-6 9.00E-8 Np-239 7.9E-3 4.12E-4 Am-241 8.2E-4 8.20E-4 Am-242m 3.23E-5 3.23E-5 Am-242 3.69E-5 3.23E-5 Am 243 1.32E-5 1.32E-5 cm-242 6.0E-4 5.75E-4 Cm-243 7.95E-6 7.95E-6 Cm-244 1.66E-4 1.66E-4 i l H-3 2.34 2.34 Rb-86 1.00 .69 l l *30 years of plant operation, 0.5 percent failed fuel O 7.1-65

                                                                  . amen &nent XI January, 1982 O                              TABLE 7.1-19 RADIOACTIVE CONTENT OF EVST SODIUM

Sodium Isotope CuCi/g)

H-3 1.40E-2 Na-22 5.8E-1 Na-24 1.47E-1 I-131 4.45E-1 Cs-134 3.5E-1 II Cs-136 2.2E-1 Cs-137 3.55 Pu-238 3.5E-3 Pu-239 9.3E-4 Pu-240 1.21E-3 () Pu-241 Pu-242 8.lE-2 2.59E-6

       *30 years plant operation, 0.5 percent failed fuel, maximum value during refueling.

O 7.1-66

Amendment XI January, 1982 TABLE 7.1-20 FUEL ASSEMBLY NOBLE GAS AND IODINE INVENTORIES 8 DAYS AFTER SHUTDOWN Inventory Isotope (Curies) Half-Life Kr-85m 2.07E-9 4.4 hr. Kr-85 6.07E2 10.76 yr. I-130 7.42E-1 12.6 hr. 11 I-131 9.10E4 8.1 d. I-132 4.39E4 2.4 hr. I-133 5.03E2 20.3 hr. I-135 6.61E-4 6.68 hr. Xe-131m 1.06E3 11.8 d. Xe-133m 2.16E3 2.26 d. Xe-133 1.29E5 5.27 d. Xe-135m 2.24E-4 15.7 min. Xe-135 5.33 E-1 9.14 hr. O 7.1-67

Amerdnent XI January, 1982 O TABLE 7.1-21 EVTM GAS ACTIVITY 8 DAYS AFTER SHUTDOWN 1% Release 100% Release From From Fuel Assembly Fuel Assembly Isotope b4ci/cc) ,f24Ci/cc) H-3 2.6E-4 2.6E-4 Ar-39 7.8E-1 7.8E-1 Kr-85m 1.24E-ll 1.24E-9 Kr-85 3.64 3.64E2 I-130 4.44E-4 4.44E-2 I-131 5.45E2 5.45E4 I-132 2.63E2 2.63E4 11 1-133 3.01 3.01E2 I-135 3.96E-6 3.96E-4 Xe-131m 6.33 6.33E2 Xe-133m 1.29El 1.29E3 Xe-133 7.71E2 7.71E4 Xe-135m 1.34E-6 1.34E-4 Xe-135 3.19E-3 3.19E-1 Total 1.60E3 1.60E5 O 7.1-68

Amendmtnt XI January, 1982 TABLE 7.1-22 INITIAL LEAKAGE RATE THROUGH EVTM SEALS TO RCB/RSB ATMOSPHERE IL. DAYS _AETEB_SHUTRQWH 11 1% Release 100% Release From From Fuel Assembly Fuel Assembly IE9tgpg _f Ci/segl_ _JHCi/cagl__ H-3 1.82E-6 1.82E-6 Ar-39 1.13E-3 1.13E-3 Kr-85m 2.36E-14 2.36E-12 Kr-85 6.92E-3 6.92E-1 11 I-130 1.04E-6 1.04E-4 I-131 1.28 1.28E2 I-132 6.18E-1 6.18E] I-133 7.07E-3 7.07E-1 I-135 9.31E-9 9.31E-7 Xe-131m 1.49E-2 1.49 Xe-133m 3.04E-2 3.04 Xe-133 1.81 1.81E2 Xe-135m 3.15E-9 3.15E-7 Xe-135 7.50E-6 7.50E-4 Total 3.77 3.77E2 O 7.1-69

t i 1 Amendment XI

 -                                                                         January, 1982 TABLE 7.1-23                              .-

REACTOR COVER GAS INVENTORY 30 HOURS AFTER SHUTDOWN w .

                                                                                              '~--

Inventory - - , Isotoog (Curies) H-3 3.4E-3 N.. Ar-39 10.0 Xe-131m 0.11 , v , i Xe-133m 0.23 Xe-133 4.2 11 Xe-135m 8.0 Xe-135 2.5 . t, y

. yCa Total 25.0 .p s

jr I

e-s - N :.+% 3 t l i s> . l 7.1-70 ~

_. ~ s x ,

                              -'                                  j                                         %                                  ,
                                                                                                                                       ~.
               ~

i s '. . Amendment XI

                                                                   ~
                                                                                                                   .                                              January, 1982 s                                                                                             ,

s TABLE 7 '.1-24 . FUEL ASSEMBLY. INVEN'IORY AND RELEASE RATES OF LO!,?G-LIVED

'~

VOLATILE FISSION-GAS ISOTOPES WITH SIGNIFICANT ACTIVITIES

                                              -          FOR SFSC DROPLFROM MAXIMU,M POSSIBLE HEIGHT ~'
                      --                                                                                                                         ...                                                       tj
                                                                                                                                               ~

Total Activity in One. Specific Activity in-Cask Leak Rate F/A at 80-Day Decay' Gas at 80-Dity Decay Time From Dropped Isotope Time (C1) (C1/sec)(1) s , Cask (Ci/sec: l'. 23 E-7 Kr-85~ 599 ' l.076E-3 ~-- Xe--131m 29.7 .

                                                                                                                             ' 5 .~3 3 E--5 '                                              6 . 0 b E'- 9 1.81E-3 Xe-133                                         10.1                ,

s 2.06E-9

                                                                                                        ~                                                                      '

3.77E-8 LI I-131 ~ -18'4 -

                                                                                                             ,                   3.31Ed4-               '

Cs-134 3600 .fl .'89 E-7J 2[ 2.15E-ll

              .Cs-136                                    219                                                                     1.38E-1012b                                               1.57E-14 1 '5.24E-7 ( 2)'

Cs-137 9950 - 5.97E-ll Rb-86 ' 41.5 1.050-9(2) 1.20E-13 Nu(1) Specific activity for six fuel assemblies. - !. (2) Based on vapor pressure of Cs and Eb At the maximum.SFGC' seal temperature of'3500P. - f ,.

1 - - _ _, , y

es \

g 9' y % L px ~

s., . T

'~

s a w

                                                                                                                                                                                                      -y l                                           s l                  '
                                                                                 -                   7 1-71                                                          -
                                                                                     '   ^
                                                                                                                        ~                                                                                '

Amendment XI January, 1982 77 . 2 OTHER ACCIDENTS Accidents of a non-radioactive nature have been postulated for all areas where potentially hazardous chemicals are stored. In

          '            almost all cases, the chemicals are concentrated acids and bases although some other materials prenent special problems. It shculd be noted that chlorine gas will not be present on-site 11 because sodium hypochlorite will be utilized for cleaning
                   ~

purposes in place of chlorine. 7.2.1 FIRES AND EXPLOSIONS Minimum environmental impact is expected from fires and explosions. The only significant explosion hazard exists in the

     '                   hydrogen gas storage area, located outside cpposite the southeast                                                                                                                   it corner of the Maintenance Shop Warehouse. The total volume of

( ) hydrogen stored on site will be 28,000 scf. An explosion will 4 not produce any hazardous gases or any significant damage to

                      -   nearby buildings; thus, such an explosion will have no effect on the environment.

The largest potential source of fire is from the two emergency 4 diesel fuel storage tanks, located below grade adjacent to the Diesel Generator Building. Elevation of the tanks is 796 feet 11 i 3 feet base, with plant grade at 815 feet MSL. As this fuel is stored below grade, the chance of an accident is reduced. There is also a concrete mat positioned below the tank. Any leakage is collected in a sump and periodically pumped to the surface through a pipe. The leakage will then be collected and transported off-site by a licensed contractor. There is no 11 environmeatal impact anticipated as a result of leakage from this tank. o 7.2-1

Amendment XI January, 1982 o 11 A list of chemical storage tanks is provided in Table 7.2-1. Two h of the chemicals, hydrazine and liquid ammonia, require special consideration. Hydrazine, in pure form, presents an inhalation hazard and is potentially explosive. The hydrazine on the site will be stored as a 35 percent solution; in this form it is not volatile, so both problems are eliminated. Liquid ammonia vcporizes upon release and therefore, presents an inhalation hazard. It will be stored in a separate room with its own ventilation system; any leakage will be released to the exhaust of the Turbine Generator Building and diluted there. Ammonia fires are not possible belcw a temperature of 1,500 degrees F(l) so further protection is not necessary. Neither hydrazine nor ammonie will have an impact on the Site and the surrounding area. In the Nuclear Island, the postulated accidents could involve cryogenic materials or DOWTHERM. There are two cryogenic mcterials, liquid nitrogen and liquid argon, located in the Reactor Service Building (RSB). Any leakage will quickly evaporate and the ventilation system will be designed such that concern over such releases is eliminated. oil The Nuclear Island of the CRBRP will utilize a limited amount of 6 DOWTHERM in several secondary cooling loops for cooling the Fuel Hcndling Cells and Primary Sodium Cold Traps. In this cpplication, Dowtherm serves as an intermediate cooling medium for separating the sodium associated with the Fuel Handling Cells cnd Primary Cold traps from the chilled water used as primary hcat exchanging medium. The entira Dowtherm inventory will be contained in closed piping systems; no Dowtherm will be stored in the Nuclear Island. Ecch cooling line containing Dowtherm will utilize remote shutoff volves positioned on the lines to isolate and limit any leakages O 7.2-2

Amendment XI Jmitary,1982 that might be postulated to occur. In addition, the cooling lines will be sloped to assure collection into small pools and reduction in surface area of any leakages. Fire prevention measures will provide additional guarantees that postulated leakage of Dowtherm will be limited and accommodated. 7.2.1.1 SCDIUM FIRES - NON-RADIOLOGICAL EFFECTS Sodium fires may occur at the CRBRP Plant. The main combustion products of sodium are Na 0,2 Na2 2,0NaOH, NaH and Na2CO3 Such compounds as Na 2 O and NaOH could be released into the atmosphere 8 as a smoke plume originating from a sodium fire. 8 Several sources (1-5) have identified the currently acceptable guideline for human exposure to NaOH as the threshold limit value () (TLV) of two milligrams per cubic meter of air recommended by the American Congress of Governmental Industrial Hygienists (ACGIH). 8 A threshold limit value is defined as an eight-hour time-weighted average concentration level under which continuous exposure will 3 not adversely affect an average human for an integrated exposure i over a working lifetime, f Because of the high affinity of sodium oxide (Na 2 0) for water, it g is reasonable to assume that sufficient contact with atmospheric moisture would have occurred when the airborne plume reaches the Site boundary to allow the sodium oxide to convert to other chemical forms such as sodium hydroxide or carbonate. The assessment presented assumes the hydroxide form is present at the site boundary. Laboratory experiments have suggested a value of 80 mg/m3 as a limit for unprotected short-term exposure to sodium hydroxide (5), O 7.2-3

Amendment XI January, 1982 Evaluation of the three most limiting potential sodium fire cccidents occurring at the CRBRP in terms of expected sodium hydroxide releases and associated concentration levels at the closest Site boundary are presented in Table 7.2-2. Ccses considered in the overall evaluation include both rcdioactive and non-radioactive sodium releases. Site boundary NaOH concentrations calculated for the non-limiting postulated cccidents are quite low, ranging in magnitude from about 10-3 mg/m3 to about 10-8 mg/m3 . These levels are well below the suggested TLV of 2.0 mg/m 3. The higher NaOH concentration values estimated for the shorter time duration accidents given in Table 7.2-2 are also at tolerable levels, as is seen by comparison to the short term exposure suggested limit ranges for short duration events. Specifically, potential Accidents 4.1 and 8.1 both have expected sodium hydroxide levels of about 1.7 mg/m3 for durations of two minutes each, and Accident 5.2 has an expected concentration level of 8.0 mg/m3 for a 15-second duration. The chemical form of the sodium combustion product before reaching the Site boundary can be expected to be in a less toxic, carbonate form due to reaction with carbon dioxide in the atmosphere. A method has been developed for predicting this conversion . ( 6) For the time scale involved before a postulated release would reach the site boundary, essentially complete g conversion to the carbonate form would be expected. In addition, the travel from release to arrival at the Site boundary is expected to involve some fallout of the cloud. A depletion factor of 100 has been applied for sodium hydroxide in its transit from release to arrival at the Site boundary. This factor will conservatively account for the expected chemical conversion and fallout effects and has been applied to the non-radiological impacts of sodium releases. O 7.2-4

t Amendment XI January, 1982 O Expected off-site sodium hydroxide concentrations resulting from g the potential accidents, such as those evaluated in Table 7.2-2, are considered to be compatible with the suggested long term and

 !        short term exposure limit guidelines.                        There is expected to be no l          long-term adverse impacts to off-site public based upon the assumed releases of sodium combustion products at CRBRP.

I 7.2.2 OIL AND HAZARDOUS MATERIAL SPILLS I Minimal environmental impact is expected from spills of oil and : 11 i hazardous materials. In the Balance of Plant (BOP), consequences of accidents such as tank rupture or leakage are controlled by secondary containment systems. Secondary containment, sufficient to contain the capacity of the largest single tank in the l drainage system shall be provided for all on-site tanks containing potentially hazardous materials. When the tank i storage is outside, the capacity of the secondary containment a will be increased to allow for the additional accumulation of liquid from rainfall. In the Nuclear Island, acid and caustic will be stored in the l j Radwaste Area of the RSB. The cells storing these tanks are designed to handle the leakage and are equipped with drains to lf the collection tank in the Radwaste System. No environmental effects are anticipated due to any accidental release from these tanks. A list of chemical storage tanks is provided in Table l 7.2-1. As was discussed in Section 7.2.1, the largest potential source

of an oil spill is from the two emergency diesel fuel storage l tanks. These tanks are located below grade and anchored to a reinforced concrete mat which is founded on and surrounded by l

O 4 ( 7.2-5

Amendment XI January, 1982 compacted Class A backfill. This mat will serve as a catchment in ll the event that an oil leak occurs in either of the two tanks. Any p:rcolated rainfall runoff or tank leakage will be collected in a sump and periodically pumped to the surface through a pipe. Any leakage will be collected and transported offsite by a licensed contractor. There is no environmental impact anticipated as a result of leakage of these tanks. Lube oil is stored in a single tank in the Turbine Generator Building. This tank is comprised of 2 compartments; 10,000 gallons each. Secondary containment, sufficient to contain the capacity of the entire tank is provided U within the building. Switchyard and transformer yard equipment containing oil, i.e., transformers, circuit breakers, and the neutral ground reactor, will have secondary containment systems capable of handling and containing any oil spills associated with this equipment without adverse environmental impact. A list of oil storage facilities is provided in Table 7.2-3. All outside fill stations are provided with secondary containment in h the form of a sloped concrete pad, capable of holding the largest tank truck served at that station. If a spill should occur, the material will be contained at the fill station until it can be disposed of offsite by a licensed contractor. O 7.2-Sa

Amendment XI January, 1982 TABLE 7.2-1 CRBRP Chemical Storage Tanks MAX. STORAGE STORAGE VESSEL LOCATION Turbine Generator Buildina Sulfuric Acid 5,500 gal. I tank Sodium Hydroxide 5,500 gal. 1 tank Ammonium Hydroxide 3,300 gal. 1 tank TBD 55 gal, drum Hydrazine Circulatina Water Pumphouse sulfuric Acid 12,000 gal. I tank Sodium Hypochlorite 15,000 gal. ea. 2 tanks Radwaste Area of Reacfar Service Buildina Sulfuric Acid 150 gal. 1 tank Sodium Hydroxide 2,500 gal, 2 tanks 150 gal. Waste Disposal Bldg. Sulfuric Acid 4,000 gal. I tank Sodium Hydroxide 4,000 gal. 1 tank Aluminum Sulfate TBD Paper Bag (Alum) lO l l l 7.2-6 l

TABLE 7.2-2 ESTIMATED

S0DIUM HYDR 0XIDE RELEASES FOR REPRESENTATIVE POTENTIAL FIRE ACCIDENTS Average Peak Concentration Concentration Accident No.** Description Duration (mn/m3) (mg/m3) 4.1 Failura of ex-containment 2 minutes 1.73 2.54 primary sod;um drain pipe during maintenance 4 8 5.2 Steam generator tube rupture 15 seconds 7.95 --

8.1 Primary sodium in-containment 145 hours 3 x 10- 7.3 x 10 -5 drain tank failure during . maintenance L 8

Estimated sodium hydroxide levels at the closest Site boundary

 ** Refer to accident numbering in Section 7.1                ,

IE T9 55! QB e-. O O e

Amendment XI January, 1982 Ow TABLE 7.2-3 CRBRP Oil Storage Facilities LOCATION MAX. STORAGE Turbine Generator Building Lube Oil Storage Tank 20,000 gallons Outside Diesel Generator Buildina 11 2 Diesel Fuel Storage Tanks 68,000 gallons /each () Main Transformer Yard 1 Main Transformer 12,000 gallons 1 USS Transformer 6,000 gallons l 1 Ground Reactor 2,500 gallons Reserve Switchyard and Transformer Area 2 Reserve Transformers 8,000 gallons /each 2 Oil Circuit Breakers 5,000 gallons /each Generating Switchyard 5 circuit Breakers 5,000 gallons /each 7.2-8

Amendment XI January, 1982

25. Norwine, J.R., Heat Island Properties of an Enclosed Multi-Level Suburban Shooging Center, Bulletin of the American Meteorological Society, Vol. 54, No. 7, July 1973, 11 pp. 637-641.

26. Van der Hoven, ISAAC; "A Survey of Field Measurements of Atmospheric Diffusion Under Low-Wind-Speed inversion Conditions", Nuclear-_Safetv. Vol. 17, No. 2, March - April 1976, pp. 223-230,

27. Hinds, W. T., Diffusion Oyar_Cnastal Monnialns.of SouthRrn lil California. Atmosaharic Environment. Vol. 4, No. 2, March 1970, pp. 107-124

28. U.S., Atomic Energy Commission, Regulatorv Guide _1.1. l9 $1 Assumotions Used for Evaluating the Potential Radiological Cnnsgguences of a loss of Coolant Angldent for Pressurized Water Rgaciars, June 1974.

29. Letter, Kornasiewitcz, R., Meteorologist, USAEC to Van jg g)

Vleck, L. D., XESD, September 1973.

2.7 REFERENCES

1. Letter confirming July 6 telephone conversation, Myers, D.

()T (_ W., XESD to Sutton, K., County Agent, Roane County, Tennessee, 11 July 1973.

2. Bradburn, D. M., Forest ManassmRnt Plant. ERDA Oak Ridge Reservation: 1976-1980. Oak Ridge National Laboratory, Environmental Sciences Division Publication no. 1056 (ORNL/TM-5833), June 1977, 58 pp.

3. Energy impact Associates, Agnatic and Terrssirjal Ecology.

Reconnaissance Surveys. August 1980. Clinch _Blver BreedRE Emactor Site, November 1980, 50 pp.

4. U.S., Department of Agriculture, Burecu of Plant industry, Soll Survev. Roane__Cnunty. Tennessee. May 1942.

( V 13.0-12

5. Peters, L. N. , Grigal, D. F. , Curlin, J. W. and Selvidge, W. J. ,

Walker Branch Watershed Project: Chemical, Physical and Morphologi-cal Properties of the Soils of Walker Branch Watershed, ORNL-TM-2968, Oak Ridge National Laboratory, Oak Ridge, Tennessee, 1971. O O 13.0-12a

Amendment XI January, 1982 w/

    )                                      1.                U.S. Atomic Energy Commission, Toxicity of Power Plant chemicals to Acuatic Life, Prepared by Battelle Pacific Northwest Laboratories, Richland, Washington, WASH-1249, June 1973.

2. Arthur, J. W. and Eaton, J. G., Chloramine Toxicity to the Amohicod (Gammarus Dseudolimnaeus) and the Fathead Minnow (Pimephales promelas), Journal Fisheries Research Board of Canada, Vol 28, No.12,1971, pp 1841-1845.

2a. Christman, R. F., Johnson, J. D., Hass, J. R., Pfaender, F. K., Liao, W. T., Norwood, D. L. and Alexander, H. J., Naturaland Model Acuatic Humics: Reactions with Chlorine, in Water Chlorination: Environmental Impact and Health Effects, Volume 2, edited by Jolley, R. L., Gorcher, H., and Hamilton, D. H. , Ann Arbor Science, New York,197 8, pp. 9 15-28. 2b. Hoehn, R. C., Randall, C. W., Goode, R. P. and Shaffer, P. T. B., Chlorination and Water Treatment for Minimizino l Tribalomethanes in Drinkina Water, in Water Chlorination: Environmental Impact and Health Effects, Vol. 2, edited by Jolley, R. L. Gorcher, H. and Hamilton, D. H., Ann Arbor Science, New York , 197 8, pp. 519-53 5, 2c. Morris, J. C. and Baum, B., Precursors and Mechanisms of Halsform Formation in the chlorination of Water Supplies, in I Water Chlorination: Environmental Impact and Health Effects, Vol. 2, edited by Jolley, R. L., Gorcher, H. and Hamilton, D. H. , Ann Arbor Science, New York,197 8, pp 29-48.

3. U.S. Environmental Protection Agency, Rules and Regulations, 9 Title 40. Part 112 Oil Pollution Prevention, December 1973, August 1974, and March 1976.

3a. U.S. Environmental Protection Agency Proposed Rules, Title 11 AD, Part 151. Hazardous Substance Pollution Prevention, September 197 8.

4. Roffman, A. and Roffman, H., Effects of Salt Water Coolino Tower Drift on Water Bodies and Soils, Reprint from Water, Air and Soil Pollution, Vol 2,1973, pp 457-471.

13 .0-3 2a

t l O O INTENTIONALLY BLANK l l l l l l l O

Amendment XI January, 1982 (Oj 2. Pathfinder cecommissioning Plan, Amendment No. 50 to Provisional Operating License DRP-ll (Docket No. 50-13 0-7 and 50-13 0-8) , February 1971.

3. Boiling Nuclear Superheater Power Station Decommissioning Final Report, WRA-B-70-500, September 1970.

4. Retirement of the Piqua Nuclear Facility, AI-AEC-12832, April 1970.

5. Report on Retirement of Hallam Nuclear Power Facility, AI-AEC-12709, May 1970.

6. Elk River Reactor Dismantling Plan, Operating Authorization DPRA-3 (SS-83 6) , August 27, 1971, Revised October 18, 1971.

7. SEFOR Decommissioning Plan, Docket 50-231, License No. DR-15, March 10,1972. State of Arkansas Byproduct License, ARK-396 BP-9-74.

8. Permi I Request for Possession Only License, August 14, 1973, Docket No. 50-16, License No. DPR-9. Possession license issued September 5,1973.

s 9. A Preliminary Report on Light Water Reactor Decommissioning Costs, GU-5295.

6.1 REFERENCES

1. U.S., Environmental Protection Agency, Water Quality Office, Analytical Quality Control Laboratory, Methodr for Chemic;l Analysis of Water and Wastes, Cincinnati, Ohio , 1971.

l,

2. Standard Methods for the Examination of Water and Wastewater, 13 th ed. , American Public Health Association, Washington, D.C. ,

1971, pp 660-662 and 734-737.

3. Millipore Corporation, Bioloaical Analysis of Water and Wastewater, AM302, Bedford, Massachusetts, 1972.

4. U.S., Department of the Interior, Federal Water Pollution Control Administraton, Water Ouality Criteria, U.S. Government Printing Office, Washington, D. C., April 1968.

5. Taylor, C.B., Bacterioloay of Fresh Water: II. The Distribution and Types of Coliform Bacteria in Lakes and Streams, Journal of Hygiene, Cambridge, Vol 41, pp 17-3 8.

l 13.0-35

Amendment XI January, 1982

6. U.S., Environmental Protection Agency, National Environmental Research Center, Analytical Quality Control Laboratory, BiQlogical_Eleld_and_LaboIat9Iy_BetbQds_fnI_ Measuring _the_ Quality Of_SUIface_ Waters _and_Efflugnts, EPA-670/4-73-001, July 1973.

7. Pennak, R.W., Collegiate _DictiQnary_Qf_ZQQlQgy, Ronald Press Company, New York, 1964, p 386.

8. Weber, C. I. and Raschke, R. L., Use._QL_a_ElQating_EeIlphyton SampleI_f9I_WateI_EQllutlQn_SurYRillance, Federal Water Pollution Control Administration, Analytical Quality Control Laboratory, Cincinnati, Ohio, Reprint, February 1970.

9. Patrick, R., The_Use_Qf_ Algae _in_the_ Assessment _Qf_WateI_Qu.ality, Presentation at Environmental Monitoring Symposium of American Society for Testing and Materials, Los Angeles, California, 27 June 1972.

10. Taylor, M. P., Thermal _Elfggts_Qn_the_Peliphyton_CQEmunity_in_the Greed _Eiyer.11661_lEEH_and_111Q, TVA, Division of Environmental Planning, Muscle Shoals, Alabama, February 1973.

11. Weber, C. I., Ec ce nt _D evelo pmen tJ _.in_the_Me a sur e ment _Qf _th e Besponse_of_ElanktoD_and_Eeriphyton_to_ Changes _in_Their EnyiIQDment, Bicassay Techniques and Environment Chemistry, Ann Arbor Science Publishers, Inc., 1973.

12. Weber, C. I. and McFarland, B. H., Egriphyton_ Biomass ChlOIQphyll Batic_as_an_Index_of_WateI_ Quality, Presented at the 17th Annual F2eting, Midwest Benthological Society, Gilbertsville, Kentucky, April 1969.

13. Hester, F. E. and Dendy, J. S., A_Myltiple: Elate _ Sampler _fDI Aquatic _MasIQinvertebrates, Trans. Amer. Fish. Soc., Vol 91 (4),

196 2, pp 4 20 and 421.

14. Sinclair, R. M. and Isom, B. G., Eurther_ Studies _QD_the IntIQduced_6siatic_ Clam _iCQIbiculal_in_ Tennessee, Tennessee l Department of Public Health, Tennessee Stream Pollution Control Board, November 1963.

15. Jaco, B. D. and Sheddan, T. L., TVA Fish Population Monitoring -

l LMFBR Demonstration Project, TVA Fisheries Resources, Unpublished Report, 11 January 1974, mimeographed.

16. Carlander, K. D., HandbQQk_of FresbyatgI_Eishgry_Hiolggy, Vol 1, Iowa State University Press, Ames, Iowa, 1969.

17. Wilhm, J. L. and Dorris, T. C., Biological _Earameters_f0I_ Water Quality _CriteIla, Bioscience, Vol 18, 1968, pp 477-480.

l 13.0-36

Amendment XI January, 1982

18. Krebs, C. J., Egglegy: The_ExpfIlmental_ADalygig=of DiStIlDMtinD and Abundance, Harper & Row, New York, 1972.

19. Patrick, R., The Use of Alcae in the Assessment of Water Ouality, Presented at Environmental Monitoring Symposium of American Society for Testing and Materials, Los Angeles, California, 27 June 1972.

20. Patten, B. C., The Information Concept in Ecology: Some Aspects of_ Information-Gathering Behavior in Plankton, Reprinted from:

Information Storage and Neutral Control (W. Fields and W. Abbott, eds.), Charles C. Thomas, Publisher, Springfield, Illinois, 1963.

21. Wilhm, J. L. and Dorris, T. C., Species Diversity of Benthic Macroinvertebrates in a Stream Receiving Domestic and Oil Refinery Effluents, American Midland Naturalist, Vol 76 (2),

1966, pp 427-449.

22. Poole, R. W., An Introduction to Ouantitative Ecology, McGraw-Hill, Inc., New York, 1974.

23. Pielou, E. C., An Introduction to Mathematical Ecology, Wiley-Interscience, New York, 1969.

   ) 23a. Woosley, L. H., Jr., Taylor, M. P., Toole, T. W. and Wells, S.

R., Status of the Nonradiologocial Water Ouality and Nonfisheries 9 Biological Communities in the Clinch River. Prior to Construction of the Clinch River Breeder Reactor Plant. 1975-1978, Tennessee Valley Authority, Chattanooga, Tennessee and Muscle Shoals, Alabama, February 1979, 143 pp and appendices. 23b. Tennessee Valley Authority, " Quality Assurance Procedure No. WQEB-SS-2," Revision 0, 1978. 1R. " Handbook of Standard Procedures for the Collection of Water Samples," Water Quality Section, Water Quality and Ecology Branch, Division of Environmental Planning, February 1974, Report No. I-WQ-74-1.

24. " Laboratory Operating Procedures," Laboratory Branch, Division of Environmental Planning, February 1974, Report No. I-WQ-74-2.

2R. Federal Water Pollution Control Act Amendment of 1972, Section 402. 3R. " Standard Operating Procedures for Routing Aquatic Biological Studies," Aquatic Biology Section, Water Quality and Ecology aranch, Division of Environmental Planning, May 5, 1975, Report f-w No. I-EB-75-2.

25. Hotler, C. R., Low-Level Inversion Frecuency in the Contiguous United States, Monthly Weather Review, Vol. 89, No. 9, September 1961, pp 319-337.

13.0-37

Amendment XI January, 1982

26. Holzworth, G. C., Estimates of Mean Maximum Mixing Depths in the Conticqpus United States, Monthly Weather Review, Vol 92, No. 5, may 196 4, pp 23 5-242.

27. Holzworth, G. C., Mixing Heights. Wind Speed and Potential for Urban Air Pollution Throughout the Contigucas United States, Environmental Protection Agency, January 1972, pp 75-75, 79-80 and 83-84.

28. Vaiksnoras, J. V., Tornado Occurrences in Tennessee, 1916-1970, National Weather Service Office, Nashville, Tennessee, 15 April 1971, mimeographed data.

29. Vaiksnoras, J. V., Tornadoes in Tennessee (1916-1970) with Reference to Nqtable Tornado Disasters in the United States (1880-1970), University of Tennessee, Institute for Public Service, Knoxville, Tennessee, revised October 1972.

30. Thom, H. C. S., Tornado Probabilities, Monthly Weather Review, Vol 91, Nos. 10-12, October-December 1963, pp 730-736.

31. Changnon, S. A., Jr., Examples of Economic Losses from Hail in the United States, Journal of Applied Meterology, Vol 11, No. 7, 1972, pp 1128-1137.

32. U.S., Department of Commerce, Weather Bureau, Hazimum Recorded United States Point Rainfall for 5 Minutes to 24 Hours at 296 First Order Stations, Technical Paper No. 2, Revised 1963, p 28.

33. U.S. Army, Quartermaster Research and Engineering Command, Glaze

     - Its Meteorology and Climatology Geographical Distribution and Economic Effects, Technical Report EP-105, Natick, Massachusetts, March 1959, pp 60, 62 and 63.

34. U.S., Department of Commerce, NOAA, Some Devasting North Atlantic Hurricanes of the 20th Century, NOAA/PA70024, 1971.

34a. U.S. Bureau of the Census. 1980 Census of Population and Housing, Tennessee, Preliminary Population and Housing Unit Counts, PHC80-P-44. U.S. Department of Commerce, January 1981. 34b. Telecon, Maranuchi, J., U.S. Bureau of the Census to White, W.' 10 Dames and Moore, March 24, 1981. 34c. Greenberg, Michael R., Donald A. Krueckeberg, and Richard Mautner. Long Range Population Projections for Minor Civil Divisions: Computer Programs and User's Manual, New Brunswick, New Jersey: Center for Urban Policy Research, Rutgers University, 1973. 34d. U.S. Bureau of the Census. Current Population Reports, Series P-25, No. 704. Projections of the Population of the United States: 1977 to 2050, Washington, D.C.: U.S. Government Printing Office, 1977. 13.0-38

Amendment XI January, 1982 34e. U.S. Bureau of the Census Current Population Reports, Series P-25, Projections of State Populations by Age, Race, and Sex: 1975 to 2000, Washington, D.C.: U.S. Government Printing Office, 1979. 0 34f. State of Tennessee. Tennessee State Planning Office, Population Projections for Tennessee. Counties, and Civil Divisions, Nashville, Tennessee, 1977.

35. Stone & Webster Engineering Corporation, Clinch River Breeder Reactor Plant Project, Construction Environmental Monitoring Program, J.O. No. 12720, May 31, 1977, 7 pp plus appendices.

9

36. Tennessee Valley Authority, Division of Environmental Planning, Preconstruction Radioactivity Levels in the Vicinity of the Proposed Clinch River Breeder Reactor Project, Report No.

RH-77-3-CR-1, April 1977, 23 + iv pp.

6.2 REFERENCES

1. Harvey, J.H., (ed.), HASL-300, HASL Procedures Manual, 9 Revised August 1974.

2. Federal Water Pollution Control Act Amendments of 1972, (j~g

( Public Law 92-500, Section 402.

3. Tennessee Water Quality Control Board, General Water Ouality Criteria for the Definition and Control of Pollution in the Waters of Tennessam, adopted on 26 May 1967, amended 1967, 1970 and 1971.

4. Peters, L. N., Grigal, D. F., Curlin, J. W. and Selvidge, W.

J., Walker Branch Watershed Project: Chemical Physical and Morpholooical Properties of the Soils of Walker Branch Hatershed, Oak Ridge National Laboratory, ORNL-TM-2968, 1971.

5. U.S. Department of Agriculture, Soil Conservation Service, Soil Survey Manual, 1962. (Also called Agriculture Handbook, No .18. )

O V 13.0-38a

9' INTENTIONALLY BLANK 1 1 l O l l l

 --_- . . . . , _ . _ -_. _ _ - . _____. _ _ _ _ _ . . _ _ - - ______ _ _ . . _ _ _ _ _ . . _ _ - . _ _ _ . _ _ _ . - - _ _ _ _ _ _ _ _ _ _ _ - - . _ ~ _ - -                     - _ . - _ . .

O AMENDMENT XI Additional Information for Detailed Environmental Assessment of the Clinch River 3reeder Reactor Plant (CR RP) Site

O Amendment XI Revisions Resulting from Design Changes and Additional or Updated Infonnation and Minor Corrections Section Major Reason for Revision 2.6 - Editorial changes to make Environment Report description more concise

             - Deletes listing of off-site meteorological data (X-10,1971-1972) from the local meteorological description placing emphasis on on-sitedata(1977-1978) 3.5      Editorial Corrections O

5.4 - Revised to update the discussion of the effects from oil and stored chemicals on surface waters 6.1 - Editorial cnanges to reflect appropriate references 7.1 - Rewritten in its entirety to incorporate the latest plant design parameters into the descriptions of the assumed accidents. The dose calculations include the most recent meteorological and population distribution data. 7.2 - Rewritten to incorporate the latest plant design parameters into the descriptions of the assumed accidents and to add Section 7.2.2 "011 and Hazardous Material Spills." 13.0 - Revised to incorporate references to Chapter 6 inadvertently deleted by Amendment X. O AXI-1

                                             . _ . _}}

ML20039G438

Text

Dear Mr. Check:

Enclosure:

=. 8 O O O O O O O O O O O O O O O O *

REFERENCE:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

2.7 REFERENCES

6.1 REFERENCES

6.2 REFERENCES

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