Text

West Valley Safety Evaluation Report (Sar), Volume 1
	ML22129A041
Person / Time
Site:	West Valley Demonstration Project
Issue date:	07/31/1962
From:	; Nuclear Fuel Services
To:	; US Atomic Energy Commission (AEC)
	Doell M
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ML22124A246	List: ML22124A252; ML22124A253; ML22129A041; ML22129A042;
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Q, SAFETY A NA L YS S SPENT FUEL PROCESSING PLANT Part B of License Application Volume I Copy No. ' 105 I '

~UCLEAR FUEL SERVICES, INC.

0) July 1962

CONTENTS Section Paragraph Number I INTRODUCTION

.,. II SITE DESCRIPTION Summary 2.1 Geography 2.4 Meteorology 2 .11 Geology 2.15 Hydrology 2.33 Seismology 2.46 Environmental Survey 2.49 III PLANT DESCRIPTION Plot Plan 3.1 Process Bui lding 3.5 IV PROCESS DESCRIPTION Fuel Receiving and Storage 4.2 Mechanical Handling 4.9 Dissolution 4.21 Feed Adjustment 4.34 Solvent Extraction--Partition Cycle 4.35 Solvent Extraction--First Uranium Cycle 4.52 Solvent Extraction--Se cond Uranium Cycle 4.57 Solvent Extraction Column--

Plutonium Cycle 4.63 Product Purification and Concentration 4.67 Solvent Re covery 4.76 Acid Recovery 4.80 Rework System 4.87 Waste Handling 4.88 V EQUIPMENT DESCRI PTION Fuel Receiving and Storage 5.3 Mechanical Handling 5.12 General Purpose Cell 5.21 Dissolvers 5.30 Pulse Columns 5.37 Evaporators 5.41 Acid Fractionator 5.47 Process Tanks 5.49 Radioactive Waste Storage Tanks 5.50 Pumps 5.57 Miscellaneous Equipment 5.61 Revision 1, October 30, 1964 0

CONTENTS Continued 0 Section Paragraph Number t- VI ENGINEERING ANALYSIS OF THE PLANT Introduction 6.1 Summary 6.2 Ventilation 6.3 Sampling and Analysis 6.22 Maintenance 6.37 Shielding 6.59

~nitoring System 6.66 Utilities 6.93 Criticality 6.103 v VII PROTECTION OF THE PUBLIC Summary 7 .1 Normal Operations 7.6 Stack 7.6 Waste Storage Tanks 7.10 Storage Lagoon 7 .11 Burial Ground 7 .14 Egress of Personnel or Material 7.18 Product Shipment 7.21 Conclusion 7.22 Abnormal Operations 7.23 0 Loss from High-Level Waste Tank Leakage from waste tank 7 .24 7.29 Criticality Incident anywhere in tfie Plant 7.30 Criticality Inc ident in Fuel Pool 7.33

/.I ., - Chemical Explos ion - 7.35

~ Failure of Iodine Removal Equipment 7.36 Conclus ion 7.37

/ VIII PROTECTION OF PLANT PERSONNEL Design Criteria 8.1 Protection from External Radiation 8.4 Inhalation 8.10 Ingestion . 8.14 Analysis of Accidents 8.20 Tank Rupture 8.21

~ Criticality Incident in Plant 8.24

~ Criticality Incident in Fuel Pool 8.29 Chemical Explosion 8.30 Failure of Ioding Removal Equipment 8.32 Minor Accidents 8.33 Summary 8.34 Revision 1, October 30, 1964

CONTENTS continued Section Paragraph Number IX PLANT OPERATION Organization 9.1 Administration 9.4 Training of Plant Personnel 9.9 Training of Outside Organizations 9.12 Health and Safety Program 9.13 Emergency Procedures 9.64 Plant Maintenance Program 9.68 Production Department 9.86 Process Maloperation 9.97 0

Revision 1, October 26, 1964 0

Figyres 0 Number 2.4 Map of Western New York State showing location of Western New York Nuclear Service Center.

2.7a Site Boundaries and Topographic Features.

2.7b Aerial Photograph of the Site.

2.7c Aerial Photograph of the Northwest Corner of the Site showing the Confluence of the Creeks.

2.8 Population Density in the Area Surrounding the Western New York Nuclear Service Center.

2.18a Boring Location Plan Western New York Nuclear Service Center.

2 .18b Seismic Point Location Plan Western New York Nuclear Service Center.

2 .19a Surface and Bedrock Profiles of Western New York Nuclear Service Center.

2.19b Stratigraphic Cross Section of the Western New York Nuclear Service Center Site.

tQ 2.22a Map of Constru ction Area showing Distribution and Lithology of Surficial Deposits.

2.22b Gene ralized Engineering Soil Map of the Western New York Nuclear Service Center.

2.23 Geologi c Cross Sections in the Constru ction Area.

2.34 Duration Curves of Daily Flow Cattaraugus Creek at Gowanda, New York.

2.35a Location of Gaging Stations on Western New York Nuclear Service Center.

2.35b Comparative Discharges of Buttermilk and Cattaraugus Creeks.

2.36a Public Wate r Supply Systems in the vicinity of the Western New York Nuclear Service Center.

2.36b Location of Wells and Springs used in the Immediate Area of Western New York Nuclear Service Center.

0 Revision 1, October 30, 1964

Figyres 0 Continued Nymber Title 2.37 Contours of Water Table on Western New York Nuclear Service Center.

2.40 Hydrographs of Wells in the Construction Area.

2.42 Map of Construction Area showinq Water Levels and Extent of the Shallow Arte si a! Aquifer.

3.la Overall Plot Plan.

3.lb Plot Plan Pro cess and Disposal Area.

3.4 Plan of Warehouse.

3.5a Perspective Sketch of Process Building.

3.5b Cutaway Perspectives at Various Levels.

3.6a General Arrangement--Fue l Receiving and Storage Area--

Plan.

General Arrangement--Fuel Receiving and Storage Area---

0 3.6b Section Sheet 1.

3.6c General Arrangement--Fuel Receiving and Storage Are a--

Section Sheet 2.

3.12a Equipme nt Arrangeme nt--General Purpos e Cell--Plans 3.12b Equipment Arrangement--General Purpose Cell--

Section She et 1.

3.12c Equipment Arrangeme nt--General Purpose Cell--

Section Sheet 2.

3.13a Equipment Arrangement--Chemical Proce ss Cell--

Elevation.

3.13b Equipment Arrangement--Chemical Proce ss Cell--

Plan 3.15a Schematic Elevation--Equipment Arrangement--

Extraction Cell.

Revi s ion 1, Oct. 29, 1962 Revision 2, Oct. 30, 1964

Figures 0 Continued Number Title 3.15b Plans--Equipment Arrangement--Extraction Cell-1 3.15c Equipment Arrangement--Extraction Cell 2--Schematic Elevation.

3.15d Equipment Arrangement--Extraction Cell 2--Plans 3.15e Equipment Arrangement--Extraction Cell ~--Schematic Elevation.

3.15f Equipment Arrangement--Extraction Cell 3--Plans.

3.16a Schematic Elevation--Equipment Arrangement--Product Purification Cell .

3.16b Plans--Equipment Arrangement--Product Pruification Cell.

3.16c Equipment Arrangement--Uranium Product Cell--Plan and Section.

3.16d Schematic Elevation--Equipment Arrangement--Product 0 Packaging and Shipping.

3.16e Plans--Equipment Arrangement--Product Packaging and Shipping.

3.19a Office Building Layout First Level.

3.19b Office Building Layout Second Level.

3.19c Office Building Layout Third Level.

4.9a Process Mechanical Cell--Equipment List.

4.9b Process Mechanical Cell--Transverse Section.

4.9c Mechanical Flow Diagram--Process Mechanical Cell.

4.2la Plant Flow Diagram of all Process Steps from Dissolution through Product Handling_.

4.2lb Schematic Flowsheet for Dissolution and Feed Pdjustment.

4.26 Treatment of Dissolver off-Gases.

Revision 1, Oct. 29, 1962 Revision 2, Oct. 30, 1964

Figures 0 Continued Number Title 4.35 Schematic of Partition Cycle.

4.52 Schematic of First U Cycle.

4.57 Schematic of Second U Cycle.

4.63 Schematic of Plutonium Cycle.

4.67a Low Enriched Uranium Product Evaporation and Final Decontamination Schematic.

4.67b High Enriched Uranium Product Final Decontamination and Evaporation Schematic.

4.73 Schematic of Pu Ionex Treatment.

4.74 Pu Product Evaporation 4.77 First Solvent Wash Cycle--Typical.

4.81 Schematic High-Level Waste Evaporation.

0 4.83 Schematic Low-Level Waste Evaporation.

4.85 Schematic of Acid Fractionator.

4.87 Schematic of Rework System.

4.89 Schematic General Purpose Evaporator.

5.3 100-ton Fuel Receiving and Storage Crane.

5.5 Fuel Pool Gate.

5.6 Fuel Pool Storage Baskets.

5.8a Fuel Pool Storage Can Crane.

5.8b Fuel Pool Service Bridge.

5.9 Fuel Storage Rack.

5.11 Underwater Transfer Conveyor.

5.12a Fuel Handling Bridge Crane.

Revision 1, Oct. 29, 1962 Revision 2, Oct. 30, 1964

/

Figures 0 Continued Number Title 5.12b Power Manipulator.

5.14 Disassembly Saw.

5.16 Bundle Shear.

5.19 Pin Shear.

5.20 Maintenance Table.

5.21 Chopped Fuel Basket Loading Station.

5.23a Gf{; 2""ton -crane.

5.23b G~ Power Manipulator.

5.25 Cf{; Crane.

5.26 Leached Hull Dumping and Sampling Station 0 5.29 Cf{; Shielding Door 5.30 Dissolvers.

5.36a Silver Reactors 5.36b Dis solver Off-Gas Scrubber.

5.36c Dis solve r Off-Gas Conde nser .

5.37 Pulse Columns 5.39a Pulse Column Instrumentation.

5.39b Decanters.

5.42a High Level Evaporator.

5.42b Low Level Wa st e Evaporator 5.42c Rework Evaporator.

5.43a Low Enriched Uranium Product Evaporator.

Revision 1, Oct. 29, 1962 Revision 2, Oct. 30, 1964

Figyres Continued Number Title 5.43b High Enriched Uranium Product Evaporator 5.45 Plutonium Product Evaporator.

5.47 Acid Fractionator.

5.50a Radioactive Waste Tanks 80-1 & 80-2.

5.50b Details--Radioactive Waste Tanks 80-1 & 80-2 .

5.50c Details--Radioactive Waste Tanks 80-1 & 80-2.

5 . 50d Plans--Vault for 80-1 & 8D-2.

5.50e Sections and Details--Vault for 80-1 & 80-2.

5 . 55 Section through Waste Storage Tank.

5.61 Plutonium Ion Exchangers 5.62 Silica Gel Columns 5.63 Solvent Wash Columns 6.3a P & ID Controlled Ventilation System to Elevation 131' .

6.3b P & ID Controlled Ve ntilation System Above Elevation 131 '.

6.3c P & ID Pro cess Off-Gas and Vent System.

6.3d Flow P & ID Waste Tank Farm.

6.17 Off-Gas Stack.

6.25 Glove Box ~ ampling Stations .

6 . 26 "C" Type Sample Cell 6.27 Process Sampling System.

6.28 Mechanical Flow Diagram--Ana l ytical and Sampling Operations .

6.31 Floor Plan and Schedules--Laboratory Area Process Building.

Revision l, Oct. 29, 1962 c Revision 2, Oct. 30, 1964

v Figures 0 Continued Number Title 6.32 Equipment Arrangement and P & ID's for Analytical cells.

6.47 >f Sketch of Jumper.

6.67a General Locations of Radiation Monitoring and Sampling Systems.

6.67b General Locations of Radiation Monitoring and Sampling Systems.

6.67c General Locations of Radiation Monitoring and Sampling Systems .

6.67d General Locations of Radiation Monitoring and Sampl ing Systems.

6.67e General Locations of Radiation Monitoring and Sampling Systems.

0 6.67f General Locations of Radiation Monitoring and Sampling Systems.

6.67g General Locations of Radiation Monitoring and Sampling Systems.

6.142 Maximum Concentration vs U-235 Enri chment.

9 .4 Plant Organization Chart 9 .100 HETS Variation With Pulse Amplitude

Tables 0 Number 2.8 Total Population and that of Towns, Villages, and Cities within successive 5-mile Radii of the Western New York Nuclear Service Center.

2.lla Mean Temperatures in Western New York.

2.llb Mean Precipitation in Western New York.

2.llc Mean Sonwfall in Western New York.

2.14 Probable Wind Roses and Diffusion Parameters for the New York Nuclear Service Center.

2.19 Estimated Rock Section Underlying the Western New York Nuclear Service Center.

2.27 Chemical Analyses of Glacial Deposits.

2.28 Ion Exchange Capacities and pH of a number of Soil Samples.

2.29a ~chanical Analysis Plus pH of Eight Selected Samples.

0 2.29b Cesium Sorption of New York Soil Samples.

2.29c Cesium Sorption on New York Soil Samples.

2.30a Strontium Sorption on New York Soil Samples.

2.30b Strontium Sorption on New York Soil Samples.

2.30c Strontium Sorption on New York Soil Samples.

2.31 Ruthenium Sorption on New York Soil Samples.

2.32 Approximate Mineralogical Content of New York Soil Samples.

2.34 Fifteen-Year Summary of Cattaraugus Creek Flow Data Gowanda, New York 2.35 Results of Discharge Measurements Buttermilk Creek Basin.

2.36a Public Water Users of Lake Erie Water in the Vicinity of Cattaraugus Creek.

2.36b Uses of Cattaraugus Creek Water Downstream from Western New York Nuclear Service Center.

Tables 0 continued Nymber 2.36c Table of Off-Site Well Records Western New York Nuclear Se rvice Center, Cattaraugus County, New York.

2.41 Summary of Hydrologic and Physical Properties of Tills from Drill Hol e 7.

3.2 Dis tances from Various NFS Facilities to Surrounding Features.

3.5 Are a Designations .

4.9 Process t.'echanical Cell--Equipment List, i'llnany oii j

,£,JoeGi14& i'~ttdhl Pl0h9 8Hft '8JL ' !!'"IUHO~r 00 J /9_ /;,47/~~

4, ZI Jtf ""'1"' ,.y ol ~rdee.r..r S T~~d~ ;::/1~..S 'f ~4n ~t"n ..S 4.77 Solvent ~aste ~eatment Schedule for Various Fuels.

5 .37 List of Pulse Columns.

5.41 Evaporator Summary.

5.42a High Level Waste Evaporator Data Sheet.

0 5.42b Low Level Waste Evaporator Data Sheet.

5.42c Rework Evaporator Data Sheet.

5 .43a Low Enriched Uranium Product Evaporator Data Sheet.

5.43b High Enriched Uranium Product Evaporator Data Sheet.

5.46 General Purpose Evaporator Data Sheet.

5.49 Proc ess Tanks 5.51 Radioactive Waste Storage Tanks Basic Design Data.

5.57 Pump Summary 6.23 Summary of Sampling Requirements.

6.36a Accountability Sample Summary.

6.36b Cold Chemical Makeup 6.36c Process Sample Summary 0 6.36d Analyti ca l Methods Revision 1, OcL. 30, 1964

Tab l es 0 Continued Number 6.60a Gamma Curies of Design Fuel.

6.60b Gamma Spectrum of Des l gn Fuel.

6.61 Gamma Spectrum of Design Fuel Assembly.

6.62a Gamma Spectrum of Fuel Basket.

6 . 62b Gamma Sp9ct.rum of Solutions in Process Vessels.

6.63 Shielding Summary.

6.67a Health-Safety Equipment.

6.67b Health-Safety Counting Equipment.

6.93 Summary of Utilities.

6.105 Reactivity Ratio of Specific Fuel s .

6.119 Characteristics of Various Fuels.

0 6.120 Safe Dissolver Canister Diameters for Various Fuels.

6.129 Safe U-235 Concentrations in Dissolver as a Function of Enrichment and of Boron Concentration where used.

6.142 Maximum TBP Concentrations for Various Fuels in 10" Columns. (I ./""! J ") J / /' ) '~ "

(,, 1?3 s,,,,,~I"' 4 t""' , "' '-" / # ;.~, /1 ~ /11)"/Jt11 c. ~;? ">'/P1.1 ~ .5

~- 7.5 Assumption~Used in Calculations--Sections VII and VIII.

7.7 Maximum Concentration of Gaseous Isotopes Under Inversion and Average Meteorological Conditions.

7.8 Iodine Deposition and Milk Concentration.

7.31 Quantities of Iodine Isotopes Formed from 1020 Fissions.

7.32a Total Dose Due to Radioiodines, Rem/Person.

7. 32b Individual and Population Doses at Several Points in Event of a Criticality Incident.

.;f- t1111- ~rd/n ;{,r :n /cJ ,, .;-/r? 0,.1,H?l'I ~

Revision 1, Oct. 29, 1962 0 Revision 2, Oct. 30, 1964

Tables Continued Number 7.34 Gaseous Activities Lost from Fuel Pool During Assumed Criticality Incident.

8.24 Thyroid Dose During Recycle Coincident with a Criticality Incident.

8.27 The Prompt Neutron and Gamma Dose at the Outside of a Normal Concrete Shield From a Nuclear Reaction of 1018 Fissions.

8.29 Gaseous Activities Lost into Fuel Receiving and Storage Area During Assumed Criticality Incident.

9.28 Rems Per Calendar Quarter.

9.32a Maximum Allowable Surface Contamination for West Valley Plant.

9.32b Maximum Permissible Concentration (microcuries per milliliter) .

9.32c Maximum Permissible Concentration (microcuries per milliliter).

0 9.35 Startup Schedule for Air Sampling.

9.47 Routine Surveys.

9.49a Environmental Monitoring Phase I 9.49b Environmental Monitoring Phase II 9.97 Instrument Functions 9.98a Ma 1opera ti on in the Fuel Receiving and Storage Area (FRS) 9.98b Maloperation in the Process Mechanical Cell Area ( PMC) 9.98c Maloperation in the General Purpose Cell Area (GPC) 9.98d Malopem tion in the Chemical Process Cell Area (CPC)

Revision 1, Oct. 29, 1962 Revision 2, Oct. 30, 1964 0

Tables Continued Number 9.99 Maloperation and Corrective Action During Dissolution-Maloperation of Feed Adjustment and Accountability Tank-Maloperation of Feed Tank to Partition Cycle.

9.100 Maloperation of HA Column, Partition Cycle Feed Pump Pots, Meter Head Pot.

9.101 Maloperation of Plutonium Cycle Feed Conditioner Tank

9. HY2 Maloperation of Feed Conditioner to First Uranium Cycle.

9.103 Mal operation of Second Uranium Cycle Feed Conditioner.

9.104 Maloperation in Plutonium Purification Cell.

9.105 Maloperation of Uranium Product Purification.

9.106 Maloperation of the Product Packaging and Shipping Area.

9.107 Maloperation Summary of Rework Evaporator System.

9.108 Maloperation of High Level Waste Evaporator Feed Tank, 0 Evaporator, Evaporator Condenser, and High Level Waste Accountability and Neutralizer Tank.

9.109 Maloperation of Low Level Waste Evaporator Feed Tank, Evaporator, Evaporator Condenser and Low Level Waste Accountability and Neutralizer Tank.

9.110 Maloperation of General Purpose Evaporator and Evaporator Condenser.

9.111 Maloperation of Acid Fractionator Feed Tank, Feed Vaporizer, Bottoms Cooler, Hot Acid Storage Tank, Hot Acid Batch Tank, Acid Fractionator, Acid Fractionator Condenser, Weak Acid Catch Tank and Recovered Acid Storage Tank.

9.112 Maloperation of Dissolver Off-Gas System.

9.113 Maloperation of Vessel Off-Gas System.

9.114 Maloperation of Off-Gas in High Level Waste Storage System.

9.115 Maloperation of Waste Tank Farm and Consolidated-Edison Storage System.

0 9.117 Solvent Treatment Systems.

0 Appendices Number Title 2.36 Public Water Systems - Supporting Data 4.1 Process Flowsheets for the Base-Line Fuels.

Commonwealth Edison Fuel Yankee Atomic Electric Fuel Consolidated-Edison Fuel Power Reactor Development, Core Zr-U Alloy Fuel Northern States Power Fuel 4.2 Cask Acceptance Criteria 5.2 Equipment List 6.121 Solid Angle Data for Dissolver Cannisters in Ajr

(,,/28 3or'"n '1 > ;.$"tJH/11~ <JI ;I)~ ../)1s.n lveY un~ye/~ .. r1.,ler P/~jl 6.129 Calculations in Support of Paragraph 6.129 6.135 Calculations for Data in Table 6.135 6.140 Calculations in Support of Paragraph 6.140 0 t , / 13 6.149

'I>J..sc~.s.s /~n ~f 74614' t, 1?3 Calculations in Support of Paragraph 6.149 6.153 Calculations in Support of Paragraph 6.153 7.7 Atmospheric Dispersion Calculation 7.8 Iodine Deposition Calculation 7.32 Iodine Dose Thyroid lo20 Fissions Calculation 7.34 Calculation of Criticality Incident in Fuel Pool 8.12 Recycled Iodine Activity Calculation 8.25 Iodine Thyroid Dose by Recycling During Criticality Incident 9.9 Curriculum for Chemical Process Operators and Senior Process Operators.

9.13 Area Radiation Alarm System 9.17 Film Badge and Dosimeter Monitor~ Protective Clothing and Safety Equipmen~ Station Monitors and 0 Hand and Foot Counters Revision 1, Oct. 29, 1962 Revision 2, Oct. 30, 1964

v Appendices 0 Continued Number 9.33 Air Sampling and Air Monitoring Eouipment 9.36 Portable Monitoring Equipment 9.37 Counting Room Equipment 9.37a Determination of Beta Emitters in In-Plant Air Samples 9.37b Determination of Long-Lived Alpha Emitters in In-Plant Air Samples 9.39a Low Background Counting System 9.39b Determination of Beta Emitters in Perimeter Samples 9.39c Determination of Alpha Emitters in Perimeter Samples 9.40 Determination of Radioiodine 9.43 Exposure Record Card 0 9.47 Routine Survey Form 9.49 Experimental Monitoring Program 9.51 Stack Monitoring System 9.53 Weather Monitoring Station 9.56 Stream Guaging and Sampling 9.64 Fire Brigade Organization 9.93 Format for Standard Operating Procedures and General Index of Standard Operating Procedures 0

I. INTRODUCTION I INTRODUCTION

1. 11 This document, which consists of nlne sections plus appendices presented in two volumes, represents a description and safety analysis of the Spent Fuel Processing Plant which Nuclear Fuel Services, Inc.

1 ..s b udl1,,fttA 1h ?I

r'fw<i Id on the Western New York Nuc 1ear Service Center near

//. //ey Rtew ti le, New York. It is the purpose of this introductory section to

~ I provide a summary of the information contained in the body of this report. Throughout the report the location of material is identified by numbering paragraphs consecutively within each section; in this introduction the numbering relates to the particular section being described.

I. 12 Sections II, III, lll, ~.and lZI describe the site plant, process, equipment, and supporting engineering systems, respectively .

These descriptive sections form the basis for the safety analysis contained in Sections lZII, Protection of the Public, and Section 2III, Protection of Plant Personnel.Section IX describes the health and safety programs and the start-up plans for the plant.

II' Site *Oescription Geography 1.21 *. The facl 1 ity wi 11 be located on the Western New York 0 Nuclear Service Center in the Town of Ashford, near Riceville, Cattaraugus County, New York, about thirty miles southwest of Buffalo and will be described as the Riceville Site. The site contains 3,331 acres and the processing plant and waste storage facilities' are located 3,000 to 4,000 feet from the nearest site boundary. The site is in the middle of a rural area of low population density - an average of 90 persons per square mile within a 25-mile radius. The population has not changed within a JO-mile radius over the past 50 years, and the character of the land and community are such that it should not change materially over the next 15 years. There is no town within 25 miles of the site with a population In excess of 10,000. The nearest village Is Springyllle, 4-l/2 miles to the north with a population of 3,852, and the nearest major population center is the city of Buffalo, the city limits of which are 26 miles north of the site. The immediate area within four miles around the site is divided between unusable rugged terrain and level fertile land used for farming. All roads through the site will be used solely for access purposes and will be controlled by the applicant . There is a spur of the Baltimore and Ohio Railroad Company railroad used solely for freight traffic running through the site at a distance of 1.800 feet at its closest point to any facility .

1.22 It is suggested that the geographical factors are favorable.

The exclusion area, as is demonstrated in Section VII, is more than adequate to assure that the health and safety of the public will not be endangered by normal operation of the facility *or by any credible accident . The population density beyond the exclusion area and population

0 within a radius of 25 miles is small, thus assuring a minimum exposure of the general public, if as a result of an unforeseen accident, radio-activity should not be contained within the area of the site.

Meteorology 1.23 The area has a mean annual temperature of 45F, an annual rainfall of 4o inches, and an annual snowfall of 80 to 100 inches. The prevailing wind directions are from the northwest in the winter and from the southwest in the summer. The area to the northeast and southeast are even more sparsely populated than the average set forth in 1.21 above and the closest major population areas in these directions are approximately 80 miles from the site. The area around the site is seldom subject to persistent stagnant high pressure areas and poor diffusion conditions.

Thus, the prevailing wind and diffusion conditions are favorable.

Geology 1.24 The plant and the waste storage facilities are located on a plateau between two of the ravines which form tributaries flowing into Buttermilk Creek . The geological structure is bedrock overlain by glacial deposits consisting of a permeable glacial till, a much less permeable silty till, with sandy tills and various shales underneath.

All layers have good ion exchange capacity for cesium and strontium.

Hydrology 1.25 The site is an elongated rolling plain cut by ravines with tributaries leading into Buttermilm Creek. All of the tributaries on the site and, therefore, all ground water on the site feed into Buttermilk Creek within the portion of that creek contained wholly within the site. Applicant thereby has control over all surface drainage for the entire site by its control over Buttermilk Creek. At the site boundary, Buttermilk Creek empties into Cattaraugus Creek, which in turn flows into Lake Erie, 39 stream miles from the site . No cities or villages downstream from the site rely on Cattaraugus Creek for their water supply, and there are no potable water sources or large water supplies in the immediate area of the site.

1.26 Buttermilk Creek supplies dilution water at an average rate of 41 cfs. Cattaraugus Creek has an average flow at the site of 358 cfs.

1.27 There are three aquifers on the site. One is in the surficial glacial till. Ground water movement In this formation is from 1 to 2 feet per day. On some parts of the site there is an aquifer located in sandy tills underneath the silty till. This does not exist on the plateau selected for the plant facilities. Finally, there is a deep bedrock artesian aquifer which Is situated well below impermeable layers at the facility location. The silty till, in which the waste tanks and the solid burial will be located, is not an aquifer

but it is water saturated. Ground wat~~ movement In this very impermeable layer is calculated to be about 5 x 10 ft/day . It is calculated that it would take about 40,000 years for the high level wastes and 5,500 years for the low level wastes to move through this silty till from the point of storage to the nearest ravine.

1.28 The good ion exchange capacity of the soil, the slow movement from the waste storage facilities to the ravines, the existence of the ravines, and the fact that alt ground water flows to a creek within the site render the site adaptable to an excellent monitoring system and allow excellent control over radioactive wastes stored on the site .

Seismology 1.29 Western New York is an area of low selsmlcity and the danger of earthquakes which might rupture any of the plant's facilities is minimal . The nearest fault to the site ls at a distance of 35 to 40 miles, and this is more properly classified as a minor earth structure rather than a fault. Thus, the site presents no seismological problems.

Sunmary l .210 In summary, the characteristics of the site are such that the health and safety of the public should not be endangered by operation at the site of the NFS chemical processing plant or by the storage of low or high level wastes. The remoteness of the site from population centers, the low population density for 25 miles beyond the site, the large exclusion area, and the meteorology, all are favorable factors to assure protection both from normal operation of the facility and from any credible accidents. The hydrology and geology are suitable to permit control of low level and high level wastes under normal conditions and in the event of *8 : credible accident . The ease of monitoring water movements and exercising necessary controls, if excessive radioactivity developed, Is assured by the special conditions existent on the plateau on which these waste facilities will be located.

TJT Plant Description

1. 31 The plant site area, located in the center of the 3,331-acre exclusion area, contains 500 acres . Both areas wilt be fenced and conspicuously posted, and access wilt be controlled. The facilities consist of a process building, a waste tank farm, a waste burial ground, a temporary waste storage lagoon, an office building, and a warehouse.

Office Building 1.32 The office building and parking for visitors and employees is located at the entrance of the plant site area 4',000 feet from the 0 process building and warehouse and 3,000 feet from tne waste disposal

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Page withheld as unreviewed potentially containing Export Controlled Information 24

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0 Pumps 1.510 A variety of pumps are used including positive displacement with and without flow adjustment, canned, centrifugal, and remote head diaphragm pumps.

Miscellaneous Equipment J. 511

a. Silica gel columns

b. Small column for the final solvent extraction product stream.

c. Ion exchange units

d. Equipment for solvent washing system.

0 0

JlI Engineering Analysis of the Plant

1. 61 In this section, the salient features of a number of the engineering aspects of th i s plant are discussed, including:

a. Ventilation

b. Sampling

c. Maintenance

d. Shielding

e. Monitoring

f. Utilities There are also sections which discuss the control of criticality and the possible effects of process maloperation.

Ventilation 1 .62 The plant has four ventilation systems which are separate from one another. These are : (1) the general building ventilation, (2) the process ventilation, (3) the process vessel system, and (4) the dissolver off-gas system. The systems are designed so that : (1) the total volume of air is kept to a minimum, (2) all air ente r ing is mechanically or chemically cleaned to remove particulate matter and fumes, (3) air pressure to limited access areas ls less than atmospheric and to process areas at an even lower pressure, (4) normal access 0 openings are vent i lated from the less active to the more active area, (5) gases from process and laboratory equipment are segregated to permit special treatment and close monitoring, (6) back-up systems are employed where desirable for reliability and continuity, (7) distribution equipment conta i ns volumetr ic control, isolation, diversion, and concentration, (8) toxic and radioactive aerosols are kept to a min imum, and (9) final exhaust to the atmosphere is accomplished at sufficient volume to insure dilution of irremovable gases and at sufficient height (202 feet above grade) to assure secondary dilution and adequate distribution to the atmosphere . The total volume of air discharged is 46,000 cfm. Fume hood and radiolaboratory exhaust, the process ventilation system, the various vessels and equipment pieces in the process area are separately vented to duplicated systems of preheaters, prefilters, absolute filters, and exhauster installations prior to release to the stack . The waste tank farm vent gas system consists of two glass fiber-packed columns and parallel exhaust discharg ing to its

<Mn stack . Each system is separately adjusted automatically and has a spare absorber train with automatic start-up and phase-in. The duplicate systems are isolated by butterfly valves . All of the exhaust fans are connected to the emergency electrical system and will come back into operation within ten seconds and automatically start up if static pressure in an area drops below a preset point or if activity increases beyond a preset point. The entire system may be operated manually if desired .

Sampling

1. 63 Sampling techniques used have been tested and proved satisfacto\y~for radiochemical work. A completely remote, multipoint sampler is ~d for most of the highly active samples. Individual shielded samplers of the Savannah River type are used for other highly_

active samples. The samplers are free draining back to the process. An air jet in the return line, controlled on the outer face of the sampling station, provides the motivating force for sample circulation. The samples from the process area are transferred remotely by conveyor to the analytical laboratory . Those from the waste tank farm are transported by truck.

1. 64 The laboratory consists of four hot cells plus one storage area. Shielding is provided to maintain 1 mrem/hour on the face of each cell. Each cell is equipped with master-slave manipulators. A transfer drawer is located in each hot cell for introduction of non-radioactive reagents and withdrawal of highly diluted samples for analysts. There are three radiochemical laboratories for use in conjunction with and in support of the hot cells. Samples diluted to less than 500 mrem/hour can be analyzed in the laboratories in hoods and behind shadow shielding.

Maintenance 1 .65 Remote maintenance Is performed in the mechanical and chemical 0 cells. In the mechanical cell most equipment can be repaired in the cell and much of it in place with the viewing and handling equipment available. Major repair and replacement can be accomplished by remotely operated equipment or the equipment can be removed for disposal or for transfer to the maintenance area for decontamination . In the chemical cell defective equipment must be removed and replaced. Equipment is designed for removal by remotely operated equipment and can be internally decontaminated in place prior to removal. All equipment except the evaporators are removed by a motorized cart to a decontamination area for external decontamination by spray. The equipment is then moved into the soaking pit for further decontamination, into the packaging area to be packaged for burial, or Into the welding bay for repairs.

1 .66 Contact maintenance is undertaken in other areas. Prior to entry by personnel, decontamination of the equipment (and In certain cases of the cell itself) is undertaken until the monitors indicate that the radiation levels are acceptable. Most of the equipment in the contact cell areas has not been subjected to more than a fraction of one per cent of the contamination levels to which the equipment in the remotely maintained cells has been subjected. Each of the contact cells has a drain to sumps and has equipment removal or access hatches for entry of personnel to make inspections, make repairs, or remove equipment to shop areas. After remote decontamination, the hatches are opened to permit a detailed survey of the cell prior to commencement of any inspection or before maintenance work is begun. Any hot spots may be further decontaminated. Pumps and other equipment which require frequent maintenance are located in shielded niches in the warm equipment aisles.

These can be isolated and separately decontaminated.

0 Shielding I .67 Shielding has been designed to assure that a level of I mr/hr will not be exceeded in normal access areas and 10 mr/hr in limited access areas. Other areas can be entered only after decontamination and careful survey. In the computation to determine the intensity of radiation to be shielded against, Consolidated Edison fuel was used as the base, since it has the highest concentration of activity of any fuel to be processed. This was multlpl ied by a factor of 1.3 for Increased activity of possible future fuel. Only 100 days cooling was assumed, allowing a further safety factor of I .6, since 150 days cooling will be adopted as a normal operating limit. The shielding material is principally ordinary concrete from 6 to 3 feet in thickness ; Lead glass shielding windows are designed to provide equivalent biological protection to that provided by the wall within which they are located . Points of penetration are protected by keeping the penetrations to a minimum size and by using multiple offsets, slopes and shadow shields to avoid a straight path.

Monitoring I .68 There is an extensive area and personnel monitoring system with both fixed and mobile units. The area system includes monitoring of plant areas for ga1T1T1a dose rate with equipment which has adjustable alarm settings, an area particulate sampl Ing system, a cell area 0 particulate sampling system, a stack gas monitoring system, . two weather monitoring systems at the base and top of the stack, an alpha radiation detection monitoring of the product packaging and handling area, three environmental monitoring stations at the site perimeter, a stream monitoring system, and a fixed in-cell area radiation measuring station system for intermittent inspection and detection of gamma background.

Alarms will be set to permit a sufficient margin of safety for taking necessary protective measures. The personnel system includes film badges and recording meters to be worn by all employees and foot and hand counters.

Utll ities I .69 Plant water is taken from Cattaraugus Creek by two pumps operated by a separate electrical system. A clarifier is Installed at the plant site to treat the water which is filtered and stored. There is a separate domestic water system. The cooling water system is provided with an open cooling tower with a two-cell Induced draft, counterflow tower. Two 40,000-lb/hr boilers are installed to meet the present 50,000-lb/hr requirement. An inert gas generator fired with propane gas and suitable for 3000 scfh is provided with a compressor to boost gas pressure to 80 pslg . Natural gas is available and a 150,000 cfh supply is contemplated. A 10,000-gallon underground tank is supplied for diesel oil. Two 300-hp compressors will be installed; each is sufficient to supply the total air requirement.

0

Control of Criticality 1 .610 Criticality is controlled throughout the plant by various methods, some of which include geometry, concentration, mass, and poisons either I iquid or sol id. Wherever possible, and particularly at the end of the process where contact between plant personnel and the product is greatest, geometry control is used. Where other methods are employed as the primary control, two or more Independent safeguards are operative at every step. The primary controls are backed up by administrative controls consisting of process instrumentation, interlocks and alarms, chemical analyses, and detailed operating procedures and supervisory checks .

1 . 611 The process is analyzed from the delivery of fuel to the ship-ment of the product, to establ lsh that sufficient criticality control is maintained throughout the operation to provide reasonable assurance that a criticality incident will not occur:

a. Fuel Receiving and Storage Fuel arrives in casks designed to prevent criticality. In J removing fuel from these casks in the unloading pool, only one fuel element can be handled at a time by the crane. Each element is placed in a storage basket and held rigidly therein with spacers to assure safe geometry during movement. The 0 baskets are put in a temporary storage rack of always safe geometry. Each basket is moved separately by a crane to the storage pool and, again, placed in geometrically safe storage racks. Each element, in its basket, is moved singly by crane to the process pool where the element is removed and placed singly in the underwater transfer conveyor for movement into the PMC.

b. Process Mechanical Cell Only one element Is permitted at one time in the area where the hardware is removed, and the scrap is inspected for fissionable material content before being placed in the scrap basket. Similarly, only one element is permitted at a time on the table of the fuel bundle shear. The canisters into which the chopped fuel is placed are of always safe diameter, and administrative controls are employed to assure that only the right canisters are present during the processing of each type of fuel . After being f i lled, the canisters are placed in geometrically safe storage racks. Similar controls are employed for the pin shear operation, which will not be operated simul-taneously with the bundle shear. The filled chopped fuel canisters are transferred one at a time into the dissolver wherein the fuel values are leached out. The empty hulls are returned to the PMC where they are monitored for fissionable 0 material content before they are discarded to waste.

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potential source of introducing radioactive contamination into the environment.

f. Product Shipment Again, tested means of preventing release during product handling and packaging will be used.

Moreover, containers used for shipment will have the necess-ary AEC, ICC, and Bureau of Explosives approvals. No unusual difficulty, therefore, is anticipated for con-tamination during product handling, packaging or shipping.

Abnormal Operations 1.73 Six abnormal events, two in the waste tanks and four in the plant, have been analyzed and they delineate accidents beyond the worst that may be deemed credible.

a. Loss from High Level Waste Tanks A major failure of the tanks ls believed to be incredible, since the tanks are of high grade material, carefully designed, with high performance characteristics, radlographed for weld defects, and with multiple means for detecing and protecting any leakage, in the unlikely event that it occurs, through liquid level measurement system in the tank and through the saucers and monitors already discussed. For a failure to occur, there 0 would have to be a combination of three unlikely events: a defect in the tank, a failure in the liquid level detection system, and a failure in the saucer or Its monitoring system.

Even assuming that JOO gallons per day are lost over 100 days and a rate of travel in the soil beyond any deemed credible, the maximum permissible concentrations would not be exceeded at the site boundary . Moreover, the rate of flow could be monitored by test wells and if it turned out to be greater than that now deemed credible, there would be more than sufficient time to Institute corrective measures either In the form of construction of a collection file field or establishment of a precipitation process similar to that in use at Oak Ridge either of which would permit reduction of the levels to permissible concentrations.

Likewise, even if it is assumed that a tank completely ruptures and its piping system becomes inoperative, a temporary piping system could be established and the wastes pumped into spare tankage within sufficient time to prevent the consequences of such an accident from befng any greater than that from the leakage accident just discussed.

b. Criticality Incident Anywhere in the Plant The conse-quences of a criticality incident involving 1020 fissions, which is in excess of any ever experienced in solution systems and represents an upper limit of any which could be 0 deemed credible, are analyzed. The controlling isotopes w wwwwc

- - :rw-=:::..

0 are the iodines, there being no hazard to persons at the site boundary from penetrating radiation. The assumption is made that all of the iodines are released from the stack instan-taneously and Iodine doses are calculated under normal and inversion conditions at the site boundary, Springville, and Buffalo. None of the values even closely approach the reference figures for reactor site location contained in 10 CFR Part TOO. The highest value Is a 5.85-rem/person dose 1...

at Springville in contrast to the 300-rem reference value in G Part 100. This value assumes inversion conditions, in which case the meteorological evidence indicates that the gases would never reach Springville but would be held in the Butter-milk-Cattaraugus Valley Systems.

c. Crltlcallty lncldent In Fuel Pool Such an incldent is deemed Incredible because of the precautions taken to prevent criticality during storage and movement of fuel Into and out of the fuel pool. However, a criticality accident is hypothe-sized which would result In the unlikely creation of the equlvalent of a 10-nMt bolling water reactor for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

There ts no risk of increased radiation levels from direct radiation. The levels of fission products released, even assuming the maximum which can be anticipated to be released through the pool water, at the site boundary would not exceed 0 maximum permissible concentrations established by 10 CFR Part 20 under the most adverse meteorological conditions.

d. Chemical Explosion It Is hypothesized that a chemical explosion somehow would release a full day's charge of fuel in solution of the highest activity level of any being processed. The calculations demonstrate that the levels at the site boundary would be within the maximum permissible concentration for mixed fission products under the most adverse meteorological conditions.

e. Failure of Iodine Removal Equipment Finally it is hy-pothesized that the iodine removal equipment fails and remains undetected for a day, which Is highly unlikely since the stack monitors and area monitors should detect the iodine increases immediately. In any event, the maximum permissible concentrations would not be exceeded at the site boundary under the worst possible circumstances.

Cone lus Ion J.74 Under all conditions, both normal and abnormal with the exception of a 1020 fission criticality incident, the release of fission products to the environment will not at the site boundary exceed the maximum permissible concentrations prescribed in the Commission's regulations contained in TO CFR Part 20. Even in the case of the 1020 0 fission criticality incident, the maximum concentration under the worst

v Paragraph 1.74, continued conceivable circumstances .wpuld be less than 2% of the guides suggested in 10 CFR Part JOO for emergency conditions. The facility as designed can be operated as proposed, therefore, at the Rlcevtlle site without endangering the health and safety of the public.

yrTT Protection of Plant .Personnel J,81 The design criteria, operating restrictions, and radiation safety program of the plant have been formulated so as to assure that the employees will be protected within the limits specified in 10 CFR Part 20 from external radiation, inhalation of radioactive contaminants, or ingestion of such contaminants. Even In the case of the worst of the abnormal events already analyzed in connection with protection of the public, the area involved could be evacuated or other* protective measures taken to eliminate any significant risk of overexposure of employees beyond levels specified in 10 CFR Part 20.

Protection from External Exposure

1. 82 All operations in the entire process are carried out remotely behind shielding after the fuel which arrives in shielded casks is placed in the storage pool. The shielding has been so designed that the maximum radiation level in normal access areas would be 1 mr/hour for the most active fuel assuming 100 days cooling. It is unlikely that anyone would be In this maximum field very Jong since the percentage of 0 time that the shielding wall ts subject to maximum activity level is small and personnel will not be standing adjacent to the wall continuously Further, since all fuel will be cooled for 150 days, a factor of safety of 1.6 is provided. It Is anticipated that during most of the working day the exposure of employees will be no more than 1/6 mr/hr.

1.83 Most sampling will be carried out behind shielding sufficient to assure a background of I mr/hour or less. If a sample is to be removed, it will be diluted prior to removal to reduce the possibility or con*

sequences of spillage or exposure to direct radiation . Maintenance work will be controlled by a work permit system and will be done under close supervision with adequate area and personnel monitoring. The procedures are such that there should be no difficulty In maintaining employee exposure within 1.25 rem/quarter.

Protection from Inhalation 1.84 The risk of inhalation hazard is kept at a m1n1mum by prov1s1on for confining most activity within the process equipment by maintaining a separate ventilation system for equipment at a pressure negative to working areas, and by having readily available masks and supply-air equipment, with frequent training sessions and drills in their use. The plant area will be monitored by fixed and mobile units with

udible and visible alarms set at least a factor of ten below tolerance levels. The only condition in which any risk of excessive inhalation is created by the stack gas release is the infrequent condition whereby

0 discharge from the stack comes directly down upon the stack . Even without allowing for dilution, which should provide a dilution factor of 10, the permissible level for iodine 131, the controlling isotope, would not be exceeded for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Ample time is provided, therefore, for corrective action or evacuation even in the unlikely event that the unusual mete' orological condition continued.

Ingestion 1.85 The requirement that protective clothing be worn In the plant and removed prior to departure, availability of other protective equip~

ment, control over eating and smoking In the plant , availability of hand and foot counters, and a mandatory cleaning and monitoring process prior to departure should protect adequately against any undue risk of ingestion.

Additional protection to employees will be provided by a medical program to assure careful pre-employment examination, foll<M up bioassays at regular i ntervals, care for on*the*job accidents, and review of exposure records .

Analysis of Accidents

1. 86 The incidents already analyzed in Section VII are evaluated in terms of their effect on employees and less serious, though more probable, accidents are also evaluated.

0 a. Loss from or Rupture of Waste Tank There is no risk of immediate exposure in excess of permissible levels to employees from the occurrence of either of these accidents .

The only risk of excessive exposure would be in providing temporary equipment to accomplish transfer to spare tankage in the event there Is simultaneously a rupture and a failure in t he pumping equipment. Even unde r these circumstances, excessive exposures can be readily avoided by temporary portable shielding for the Installation and maintenance required.

b. Criticality Incident Anywhere in the Plant A criticality incident involving 1020 fissions occurring anywhere in the plant was analyzed. Throughout most of the plant the shield-ing is sufficient that no employee could receive a dose of penetrating radiation in excess of the limits of 10 CFR Part 20. Even in those portions of the plant where the shield-ing is the least, an employee standing directly opposite the point of the event would not receive an MLD of direct radiation.

There is no risk from inhalation In excess of Part 20 limits unless the gas released from the stack comes down on the air intake or the ventilation system fails. Assuming the unusual meteorological occurrence at the time of the criticality accident, the iodine dose under the worst conditions would be 1/2 of the emergency dose suggested in 10 CFR Part 100 for 0 employees who took no protective steps within ten minutes,

Paragraph l.86(b), continued 0 despite the alarms. If the ventilation system fails, no significant doses from inhalation should result since there is a favorable pressure dlfferential between the processing cells and work areas and an evacuation alarm is activated by any failure in the ventllatlon system. Thus, the occurrence of the worst possible criticality accident, even with con-current failure of the ventilation system or direct recycle of stack gas, does not create an undue risk of exposure of employees to radiation.

c. Criticality Incident In the Fuel Pool It is shown that the highly unlikely criticality incident in the fuel pool would not destroy the integrity of the water shielding so that direct radiation is not a problem. There would be some hazard from inhalation to personnel in the room. They would have to evacuate the room within one minute in order to stay within a week's allowable inhalation of the control"I ing isotope, iodine 134. The evacuation distance is small, such an event would be extremely noticeable (there would be a visible flash and the monitors would trip an alarm), so that evacuation of the room within a minute Is quite feasible.

d. Chemlcal Explosion A chemical explosion which ruptures a tank containing a day's charge of activity has been analyzed.

So long as the ventilation system continues to operate-- and 0 it has been desighed to withstand the postulated explosion--

there would be no risk of exposure of personnel in the plant unless the stack gas discharge were to recycle directly on the air Intake. Even in this unlikely event, there would be five minutes to evacuate the buildings to avoid exposures in excess of permissible levels and this should be adequate. If the ventilation system should be knocked out by the explosion, the immediate area would have to be evacuated quickly. But in this case the spread of the airborne activity would be by diffusion and slow so that there would be ample time to evacuate, don protective equipment, and reenter to take corrective measures.

e. Failure of Iodine Removal Eguipment In the event the iodine r.emoval equipment should fail to operate, there would be no hazard at all to employees except in the unlikely case of direct recycle of the stack gas on the air intake. In that event, one hour would be available for evacuation or corrective action before permissible levels would be exceeded.

f. Minor Accidents Other minor accidents have been evaluated and it is concluded that none could credibly result In levels of exposure to plant personnel in excess of the levels speci-fied in 10 CFR Part 20. There are a number of lines of defense to protect against these accidents which include 0 minimizing the need for handling any activity, institution

0 of strict operating rules, maintenance of mobile and fixed area monitoring systems, and maintenance of personnel monitoring by meters and film badges.

Cone l us ion 1.87 The design specifications, operating limitations, protective devices, and training programs should fully protect employees under normal operations from exposures in any quarter beyond the levels permit-ted in 10 CFR Part 20. Moreover, even in the event of the highly unlikely and probably incredible series of accidents postulated, exposures should be maintained within the limits specified in Part 20 through proper ...

emergency measures. In no event would any employee be exposed in excess of the emergency doses suggested in JO CFR Part 100. Therefore, there is adequate assurance that the facility can be operated within the require-ments of the AEC's regulations, Including 10 CFR Part 20.

0 0

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IX PLANT OPERATION 1.91 Included in this section are details relating to the following subjects: Plant Organization, Plant Administration, the training of plant personnel, the Plant Health and Safety Program, the Plant Emergency Program, the Plant Maintenance Program, the operation and function of the Production Department, and a discuss i on of Process Maloperations.

1.92 Plant Organization discusses the duties of the Plant Manager, Production Manager, Health and Safety Director, Technical Service Manager and Plant Criticality committee.

1.93 Operating Procedures, Letters of Authorization, the procedures involved in initiating and changing same, and the met ~ods used to insure that these procedures and Letters of Authori-zation are being fo~lowed are discussed in the Administration Section.

1.94 The Plant Training Program at various levels throughout the plant is covered under this topic~ The Appendix to this section lists the curriculum to be employed in performing this training.

1.95 The Health and Safety section defines the responsi-bilities of the Health and Safety Department, the general regulations and procedures for performing radioactive work, the maximum allowabl e 0 levels of radiation in the plant (by zones), the monitoring sampling procedures, and the medical program.

~

1.96 Details of the fire protection organization and general procedures to be followed in the event of radiation emerge ncies are defined in this section.

1.97 The operation of the Plant Maintenaoce Department, its organization, duties and functions are defined in this section.

1!98 Production Department operations, including administrative controls within the Production Department, a break-down and a descriptidn of the operations in the plant by major area s are described in this section. ~

l.99 Process maloperations, results, the method determining the maloperation and the corrective action to be taken is presented, largely in tabular form, in this section.

Revision 1, October 26, 1964

II. SITE DESCRIPTION 1I SITE DESCRIPTION Su111nary 2.1 In this section, the salient features of the Western New York Nuclear Service Center site at which the NFS Spent Fuel Processing Plant will be built are described.

a. The site is located on a small plateau cut by Buttermilk Creek and numerous tributaries which collect all of the surface and shallow subsurface drainage from the site. This valley is surrounded by glaciated bedrock hills (2.4-2.7) .*

b. The population density in the area surrounding the site is low -

the total population density within a radius of 25 miles is 90 persons per square mile. There is no city in this area with a population greater than 10,000. The "population center 11 distance is 26 miles. The immediate area population within a ten-mile radius has not changed in 50 years and the character of the land and the corrrnunity is such that it is not expected to change materially in the next 15 years (2.8-2. 10).

c. The area has a mean annual temperature of 45F, an annual rain~

0 fall of 40 inches, and an annual snowfall of 80 to 100 inches.

The latter two are factors common to most northeastern locations.

Wind directions and velocities and meteorological parameters have been deduced from a study of the site by meteorologists from Brookhaven National Laboratory who have surveyed the site and stated that it is suitable for the uses requested (2 . 11-2 . 14).

d. Geology of the site has been investigated by a series of drillings and a seismic survey. Bedrock, which has a profile steeper than the surface, is overlain by glacial deposits. The surface layer on part of the site is relatively permeable coarse granular deposits, the thickness of which varies from O to 25 feet. This Is underlain by a much less permeable silty till varying in thickness from 25 to 35 feet. On part of the site, this silty till is at the surface. Under that there may be irregular sandy tills and various shales . These layers have been shown to have good ion exchange capacities (2 . 15-2.32).

e. All of the surface drainage for the entire site is collected by Buttermilk Creek, the average flow of which over 15 years is calculated to be 41 cfs. This creek empties Into Cattaraugus Creek which in turn flows into Lake Erie 39 stream miles away.

There are no villages or cities downstream from the site which use Cattaraugus Creek water for domestic purposes (2.33-2.36).

0

Numbers shown in parentheses refer to paragraph numbers wherein supporting data may be found .

f. There are three aquifers on the site. The surficial coarse granular deposits constitute an aquifer recharged from the rain falling onto the invnediate area. Small quantities of water can be taken from this layer. The "water table" is variable with the season and the location and is located near the interface of the granular deposits and silty tills. Velocity of flow in this aquifer is expected to be in the range of 0.1 to 1 ft/day.

In some places on the site, there is an aquifer located just below the silty till layer . This aquifer is under about 10 feet of artesian pressure. It is absent in the area selected for the spent fuel processing plant. Finally there is a deep bedrock artesian aquifer about which little is known. It is well separated from the surface layers which will be used by this plant by impermeable layers and by others which may be expected to have good ion exchange capacity. The plant site area is adaptable to an excellent monitoring system (2.37-2.45).

g. There is very little seismic activity on the site (2.46-2.48).

2 . 2 We believe the site to be an excellent one from the standpoint of population. Meteorology is more favorable than at most sites.

Climatology is acceptable although less rain and snQ.o.I would be desirable.

Rainfall at any site in the northeast would not be significantly different . The hydrological picture is excellent from the standpoint of 0 predictability, monitoring, and lack of domestic use. It is our opinion that we can design the plant to accommodate existing water table conditions.

The site is easily accessible despite its relative isolation and is desirably located economically.

2.3 The assistance of the following men in supplying some of the data and conclusions of this section is gratefully acknowledged:

Maynard E. Smith Brookhaven National Laboratory Irving A. Singer Brookhaven National Laboratory John Broughton New York State Geologist Herbert G. Stewart, Jr. United States Geological Survey -

Albany T. Tamura Oak Ridge National Laboratory Jon Anderson New York State Off ice of Atomic Development Geography 2.4 The NFS Spent Fuel Processing Plant will be built at the Western New York Nuclear Service Center, a 3331-acre site located in the town of Ashford in the north center section of Cattaraugus County. It is centered approximately 4-1/2 miles south of the village of Springville, New York . Its relation to surrounding communities in New York, Pennsylvania, and Ontario is shown in Figure 2.4.

0

Figure 2.4 Map of Western New York State Showing Location of Western New York Nuclear Service Center 0

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0 2.5 All surface drainage on the Service Center is discharged into Buttermilk Creek within the boundaries of the Center . Hence, all surface drainage leaving the site can be monitored. The Service Center includes all of the Buttermilk Creek valley for five miles above its mouth. At the northwest end of the property, Buttermilk Creek joins Cattaraugus Creek which flows in a westerly direction into Lake Erie 39 stream miles away.

2.6 The eastern, western, and southern boundaries of the Service Center are along the slopes of glaciated bedrock hills, some of which reach altitudes in excess of 1900 feet above sea level. Land surface slopes from these hillsides onto the elongate rolling plain that con-stitutes the central part of the Service Center. The surface of the plain is approximately 1380 feet above sea level . Buttermilk Creek flows through the central part of the plain in a valley cut about 100 feet below the surface of the plain. Tributaries of Buttermilk Creek have further dissected the topography of the Service Center . The valley walls of Buttermilk Creek and its tributaries are generally quite steep, but are badly slumped in some areas. Although surface drainage channels are deeply incised, the system is not wel I integrated and there are small isolated marshes on the Service Center.

2 . 7 The boundaries of the site superimposed on a topographic map of the area are shown in Figure 2.]a. This exhibit shows the location of 0 tributary creeks, existing roads , a power transmission line, two oil transmission lines, and a railroad which cross the property . Figure 2.7b is an aerial photograph of all but the extreme northwest corner of the site and Figure 2.]c is an aerial photograph at a somewhat larger scale of the northwest corner Sha.Ying the confluence of Buttermilk Creek and Cattaraugus Creek.

2 . 8 The site is located in an area where the population density is low . Figure 2.8 sho.Ys the site, the 5-, 10-, 15-, 20-, and 25-mile radii from the center of the site, the location of all villages and cities within the 25-mile radius, and by means of color coding shows the population density of the countryside less the villages and cities indicated. Table 2.8 gives the populations for each of the villages and cities and the total population within each of the radii shown. It can be seen from these exhibits that:

a. Three-quarters of the land within the 25-mile radius has a population density of less than 60 per square mile.

b. Only the area around Gowanda, between 10 and 15 miles west of the site, and the areas to the north and west approaching Buffalo exceed this.

c. There is no city or village within 25 miles with a population greater than 10,000 .

0 Figure 2.?a Site Boundaries and Topographic Features

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Qtf*C:t 0' ~MIC D!Yf.u>Jl'ilENt WESTERN NEW YOftK HUOl..EAR SERVICE CENTER lQWM Of A$IFOllO CQlljy'f Ole *~

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Figure 2.7b Aerial Photograph of the Site a

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0 Figure 2.7c Aerial Photograph of the Northwest Corner of the Site Showing the Confluence of the Creeks 0

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0 Figure 2.8 Population Density in the Area Surrounding the Western New York Nuclear Service Center

0 NEW YORK STATE CHEEK*

TOWAGA L ANCASTER ALDEN o*

Aldeo DARIEN ALEX

ANDER 0

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I BETHANY J

~y' WEST Attica* . WYOMING CO.

c::::i 0-60 PER SQUARE MILE SENECA I ELMA W yu ming

~ 60-llO PER SQUARE MILE BENNINGTON ATTICA MIDDLE*

llIIllIJ llO AND OVER PER SQUARE MIL BURY

~ VILLAGES AND CITY IN T~NS i ORANGE*

1 VILLE

\l WARSAW GAINESVILLE S i lvt>r "'z Ill

-co. "

UME 0 (

Fredonia

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Filh

~AFT dagn CH A IU.on a TON S i nclain i lle FR IEND.

ELLING* SHIP RY GERRY TON

.0 Friends hip POLAND CLARKS- WIRT Fa l coner VI LLE Richuu1 RED 0Boli\'llr BUSTI GENESEE' HOUSE OLEAN BOLIVAR ville

Table 2.8 Total Population and That of Towns, Villages, and Cities Within Successive 5-Mile Radii of the Western New York Nuclear Service Center

SUMMARY

Radius Total Population Population Density Miles Persons Persons/Square Mlle 5 5,765* 73

'. 5 2,685** 36 10 15,644 49.6 15 39,297 55.5 20 62,~32 49,5 25 170,573 87 0

0 *With SPRINGVILLE

- Without SPRINGVILLE

Table 2.8 ('Conti nued 1)

SPECIFIC ANALYSIS Towns and VILLAGESa Popul at i onb 0-5 Miles from Site Ashford 1,288 Concord 932 SPRINGVILLE (Part) 3,080 East Otto 83 El I icottvi 1 le 34 Machias 162 Yorkshire 186 5,765 0-10 Miles from Site Ashford 1,490 Collins 2,014 Concord 1, 796 SPRINGVILLE 3,852 East Otto 701 E11 i cot tv i 11 e 456 Frankl i nvi 11 e 135 Machias 1'314 Mansfield 127 0 North Col I ins 60 Otto 248 Sardinia 1 .575 Yorkshire 1,099 DELEVAN 777 15,644 0-15 Miles from Site Arcade 356 ARCADE 1 ,930 Ashford 1,490 Boston 1. 979 Colden 1,427 Co 11 ins 5,640 GCMANDA (Part) 1,079 Concord 2,600 SPRINGVILLE 3,852 East Otto 701 Eden 66 E11 i cot tv i 11 e 818 ELLICOTTVILLE 1. 150 Farmersville 500 Frankl invi 11 e 867 FRANKLINVILLE 2, 124 Freedom 624 0 Great Valley Hol 1and 334 860

0 Table 2.8 T<Mns and VILLAGESa Po2ulation b 0-15 Miles from Site Humphrey 64 (continued) Java 5 Little Valley 118 Lyndon 35 Machias 1;390 New Albion 152 CATTARAUGUS I ,258 North Col I ins 395 Otto 715 Persia 338 GOWANDA (Part) 2;273 Sardinia 2' 145 Yorkshire I , 235 DELEVAN 777 39,297 0-20 Miles from Site Colden 2,384 Col I ins 5,905 a GOWANDA (Part)

Concord SPRINGVILLE 1,079 2,600 3,852 Dayton I ,046 Eagle 132 East Hamburg 2,914 East Otto 701 Eden I ,041 EDEN 2,366 El 1icottvi1 le 818 ELLICOTTVILLE I , 150 Evans 200 Farmersv i 11 e 721 Frankl invi I le 906 FRANKLINVILLE 2' 124 Freedom I ,059 Great Valley I ,408 Hamburg I ,000 Hinsdale 6 Holl and 2,304 Humphrey 402 Ischua 287 Java 969 Leon 135 Little Valley 493 LITTLE VALLEY I ,244 Q, Lyndon Machias 381 I ,390 Mansfield 632

0 Table 2.8 TCMns and Vl'LLAGESa Population b 0-20 Miles from Site Napoli 237 (continued) New Albion 723 CATTARAUGUS 1 ,258 New Hudson 61 North Collins 2,231 NORTH COLLINS 1,574 Otto 715 Perrysburg 1 ,393 PERRYSBURG 434 Persia 483 GOWANDA (Part) 2 ,273 Rushford 311 Salamanca, incl. approx.

1/2 of SALAMANCA CITY 4,376 Sardinia 2, 145 Sheldon 17 Wales 540 Yorkshire 1 ,235 DELEVAN 777 0 62,432 0-25 Miles from Site b

Towns and VILLAGESa County Population A11 egany Cattaraugus 4,419 Arcade Wyoming 931 ARCADE Wyoming 1,930 Ashford Cattaraugus 1 ,490 Aurora Erie 6,097 EAST AURORA Erie 6,791 Boston Erie 5, 106 Brant Erie 1 ,989 Caneadea Allegany 378 Cattaraugus Indian Reservationl 1, 140 Allegany Indian Reservation )

Carro 11 ton Cattaraugus 441 Centervi 1le A1 legany 491 Cherry Creek Chatauqua 251 Cold Spring Cattaraugus 394 Col den Erie 2,384 con ins Erie 5,905 GOWANDA (Part) Erie 1 ,079 Concord Erie 2,600 0 SPRINGVILLE Conewango Erie Cattaraugus 3,852 693

Table 2.8 0-2~ Hi 1es from Site (continued)

T<Mns and VILLAGESa County Population b Cuba A1legany 759 CUBA A1legany 1,949 Dayton Cattaraugus 1,235 DAYTON Cattaraugus 696 Eagle Wyoming 896 East Hamburg Erie 6,974 East Otto Chatauqua 701 Eden Erie 4,264 EDEN Erie 2,366 El 1 icottvi I le Cattaraugus 818 ELLICOTTVILLE Cattaraugus I, 150 Evans Erie 9,540 Farmersville Cattaraugus 721 Frankl* i nvi 11 e Cattaraugus 906 FRANKL INV I LLE Cattaraugus 2' 124 Freedom Cattaraugus 1 ,059 Great Valley Cattaraugus 1,408 Hamburg Erie 16, 707 HAMBURG Erie 9, 145 Hanover Chatauqua 2,797 Hinsdale Cattaraugus 1 ,206 Holland Erie 2,304 Hume Allegany 396 Humphrey Cattaraugus 415 Ischua Cattaraugus 562 Java Wyoming 1'757 Leon Cattaraugus 808 Little Valley Cattaraugus 493 LITTLE VALLEY Cattaraugus 1,244 Lyndon Cattaraugus 406 Machias Cattaraugus 1,390 Mansfield Cattaraugus 632 Marilla Erie 469 Napoli Cattaraugus 670 New Albion Cattaraugus 723 CATTARAUGUS Cattaraugus 1,258 New Hudson Allegany 483 North Col I ins Erie 2,231 NORTH COLLI NS Erie l ,574 Orchard Park Erle 10,283 ORCHARD PARK Erie 3,278 Otto Cattaraugus 715 0 Perrysburg PERRYSBURG Cattaraugus Cattaraugus 1 ,423 434

0 Table 2.8 0-25 Miles from Site (continued)

Towns and VILLAGESa County Population b Persia Cattaraugus 483 GOWANDA (Part) Cattaraugus 2 ,273 Red House Cattaraugus 235 Rushford Allegany 995 Salamanca Cattaraugus 432 SALAMANCA CITY Cattaraugus 8,480 Sardinia Erie 2, 145 Sheldon Wyoming l, 108 Villenova Chatauqua 511 Wales Erie 1 ,910 Weathersfield Wyoming 260 Yorkshire Cattaraugus 1 ,235 DELEVAN Cattaraugus 777 170,573 0

a The term Town in New York State is equivalent to Township Is many 0 states; Cities and Vi 11 ages are shown in capita 1 Ietters.

b Populations of Towns and Villages taken from Advance Reports, Final Population Counts, 1960 Census of Population, November 30, 1960.

PC(Al)-34 issued by Bureau of Census, Department of Commerce.

0

d. The total population within the 20-mile radius results in a population density just under 50 per square mile; the entire 25-mile area contains less than 90 per square mile.

e. The nearest village, Springville 1/2 miles to the north, has a population of 3t852.

2.9 The city limits of Buffalo (population 532t759) are at an air distance of 26 miles north from the center of the site. This distance is the "population center distance" within the meaning of the definitions in 10 CFR Part 100. The center of Buffalo is 32 air miles away. Other nearby cities are Rochester (318,611} 72 miles to the northeast; Jamestown (41,818) 38 miles to the southwest; and Olean (21,868) 28 miles to the southeast. Except for these cities, the low population density representative of most of the area as shown in Figure 2.8 extends for long distances particularly to the east - the general direction into which the prevailing winds will flow.

2.10 The population in the area of the site has not increased appreciably in the past 50 years. Predictions of future population trends are always difficult to make. It would seem certain that, in company with the rest of the country, this area can be expected to experience some population growth particularly in the area bordering the City of Buffalo. In the immediate areat this plant can be expected to bring in 0 immediately perhaps 200 people (exclusive of the transient construction personnel) and eventually 1000 additional persons might be brought into the area from other parts of the country by associated activities. The large portion of the immediate area is either of sufficiently rugged terrain as not to lend itself to general use or it is of a relatively fertile and level character now being used for dairying and farming and it is likely to remain largely that way. To the west, Zoar Valley from about 4 to 10 miles from the site is being developed as a state conservation area with the possibility of some camping and picnicking facilities.

About 15 miles to the south a ski area has been set up. Farther to the south, there is a large area of land in Allegany State Park which will remain unpopulated and farther to the west is the Cattaraugus Indian Reservation which may be expected to remain largely as it is now. This site appears to have a good prospect of remaining roughly as it is nQI/

for the next 15 years.

Meteorology 2.11 It is not expected that the climatology of this site will differ markedly from that determined from existing nearby reporting stations. Data from these reporting stations which encircle the site have been obtained. The annual mean temperature computed over a 13-year period at the nearest reporting stationt Franklinville, is 45F. These data together with monthly averages are given in Table 2. lla. The mean precipitation at five nearby reporting stations is given in Table 2. llb.

0 The annual snowfall at four surrounding stations is shown in Table 2.llc.

0 Table 2. 1la Mean Temperatures in Western New Yorka,b Mean Temperature Over 13-Year d Month Minimum Maximum Period, F* Highestc Lowest January 15.9 32.8 24.3 71 -28 February 12.0 31.6 21.8 65 -45 March 20.5 39. l 29.6 77 -16 April 30.7 52.6 41. 7 82 3 May 41.6 66.9 54.2 89 20 June 51. l 76.8 63,9 97 30 July 54. l 80.4 67.3 99 36 August 52.3 78,8 65.6 94 26 September 45.8 71.9 58.9 93 21 October 36.9 60.7 48.8 86 10 November 28.7 45.7 37.2 Bo -24 December 18.8 34.8 26.8 63 -27 0 Annual 34 56 45.0 a At Franklinville - 12.3 miles S, 25° E, elevation 1590 feet.

b From New York Climatic Summary No. 26, Supplement for 1931 through 0 1952, Weather Bureau, U. S. Department of Commerce.

c 13-Year Period .

d 14-Year Period .

0 Tab 1e 2. 11 b Mean Precipitation in Western New Yorka Litt led ' Derbyf Month Arcade b Frankl invi 11ec Va 11ey GONanda e

2 NW January 3.05 2. 71 3.74 2.89 3.06 February 2.37 2.68 3.86 2.34 2.77 March 3,25 2.89 4.87 2.63 2.99 Apri I 3.21 3. 17 4.53 3. 10 3.21 May 3,96 3,55 4.77 3.62 3.86 June 4.05 3,93 4.32 3.50 3.20 July 3. 19 3. 70 4.95 4.oo 3,05 August 3,09 3. 12 3.48 2.47 2.65 September 3.89 3.26 4.13 3,37 4. 10 October 3.26 3.04 3.45 2.49 3.03 November 3 .61 3.00 4.70 3. 77 4.47 December 2.86 2.83 4.25 2.36 2.90 Annual 39,79 37.88 51.05 36.54 39,35 0

a From New York Climatic Summary No. 26 of the United States, Supplement for 1931 through 1952. Weather Bureau, U. S. Department of Commerce.

b 8 to 10 years record. 13.2 miles N,60° E, elevation 1480 feet.

c 13 to 17 years record. 12.3 miles S, 25° E, elevation 1590 feet.

d 0 11 to 12 years record.

e 7 to 8 years record.

15.7 miles S, 30° W.

15 miles N, 88° W, elevation 865 feet.

f 7 to 8 years record. 23.8 miles N, 45° W, elevation 640 feet.

0 0 Table 2.1 lc a b Hean Snowfall in Western New York '

Arcade Fr an k I i nv i 11 e Litt 1e Va I 1el'. Derb:t 2 NW A B c A B c B c B c Month Years c -- _!L _ 7_ _ 9_ 14 12 9 10 9 _7_ _9_

January 23 .3 16.2 24 .2 20.6 15 .7 29.2 27 .6 39 .4 14.o 17 . 1 February 15.5 15.9 19.2 15.0 21.4 32 .2 30 .6 35 .4 12 . 9 9. 1 March 1l.8 14. 1 15.9 8.9 17 .6 29 .9 25 .5 28 .0 8 .5 11. 8 Apr i 1 5.6 2.6 4. 1 5 .8 4 .4 10 .9 3.0 8.4 1. 1 I. 3 May 0.03 0.06 0.06 0.01 June July August September October 2.4 0.3 0.5 1. 5 0.9 1.4 o.6 1. 0 0, I I .1 November 8. 3 16 .4 13 .4 7.0 11. 9 19. 2 17 .5 20 .4 13.6 14. 3 December 18 .8 21.2 18.2 17.2 17. 1 30.6 39 .6 36.6 I 9. 3 16 .3 Annual 86 .0 87 .3 95 .5 76 .6 89 .0 153 .4 144.s 169.2 69 .5 71.0 a Climatic Sunmary, New York State Bulletin No. 26, reported by U. S. Department of Commerce.

b Climatological data, New York State Bulletin No. 6, for each year 1953 through 1961 reported by U. S.

Department of Conmerce.

c A= Data taken prior to 1931.

B = Data taken between 1931 and 1953.

C =Data taken from 1953 to 1961 inclusive.

0 2.12 The meteorology of the site has been investigated by Brookhaven National Laboratory meteorologists Maynard E. Smith and Irving A. Singer.

In their opinion. the Springville site is considerably more favorable than most from the point of view of meteorology. topography. and the location and orientation of major population centers. This section of New York State is generally characterized by relatively vigorous wind flow with two prevailing directions. northwest in the winter and southwest in the summer. Neither of these is unfavorable. since major population areas to the southeast and northeast are of the order of 80 miles distant. It is also true that this portion of the country is not often frequented by persistent stagnant high-pressure areas and poor diffusion conditions. Such phenomena are much more commonly found south of this region in Pennsylvania. West Virginia. Maryland and Virginia.

2. 13 The local wind flow patterns are difficult to define.

even though the general circulation above the hilltop level can be estimated fairly accurately. The terrain surrounding the site is rolling, with maximum differences in elevation of a few hundred feet. The immediate site 0 area will probably show local wind circulations associated with Buttermilk Creek, which runs northwest-southeast through the site and possibly to some extent by the smaller creek running northeast-southwest and joining Buttermilk in the southern part of the area. In regard to this, the probable drainage flow during stable conditions is of interest, since a low-level release under such circumstances would be likely to remain concentrated for significant distances. It seems quite reasonable to expect that such flow will be quite consistently northwestward down the Buttermilk Creek Valley. possibly reaching the Cattaraugus Creek Valley about 3 to 4 miles to the northwest. It seems quite doubtful that a release would reach the village of Springville under such conditions. but rather would either become stagnant in the Buttermilk or Cattaraugus Valleys or follON the Cattaraugus Valley away from Springville.

2.14 Wind data from the available nearby sites have been obtained and studied. These include airport observations from Olean, 30 miles south-southeast; Jamestown. 35 miles south-southwest; and Danville, nearly 50 miles to the east. But study of these wind records indicates that each is primarily affected by the local terrain In 0 that particular locality. Therefore. the wind rose and diffusion parameter data presented in Table 2.14 have

Table2.14 Probable Wind Roses and Diffusion Parameters for the Western New York Nuclear Service Centera WIND ROSES Wind Per Cent of Time From Summer Winter N 4 6 NE 3 3 E 5 3 SE 10 15 s 30 15 SW 25 15 w 8 8 NW 15 35 DIFFUSION PARAMETERS For use when conditions b ~ ~ng ~ t udie d ~r~ expected to persist for:

3 Hours to Day Instantaneous 0 100 Days Inversion Lapse Inversion Lapse n 0.25 0.5 0.25 0.5 0.25 Cy o.4 0.4 0.5 0.2 0.25 Cz 0.4 0.07 0.2 0.07 0.2.

Cx 0.2 0.25 u, m/sec 4 4 4 0 a Memo, M. E. Smith to W. A. Rodger, 5/23/62, estimated from general meteorological conditions as modified by the local terrain.

been deduced from a knowledge of the general conditions aloft in this area and from assessing the probable impact of the local terrain . Du ri ng the course of construction and operation local meteorological data will be obtained and the presented data will be refined for operating purposes . t n the absence of specific data for the s i te, the diffusion parameters have been chosen on an exceedingly conservative basis. Determination of the on-site data will undoubtedly justify the use of more 1 iberal values .

Geology 2.15 The following discussion of the geology of western New York State was prepared by Dr. John Broughton, New York State Geologist. The discussion of the pa r ticular site was prepared from material supplied by Dr . Broughton and by Herbert G. Stewart, Jr .,. Geologist in the Albany off ice of United States Geological Survey .

Western New York, from a l i ttle south of the latitude of Buffalo, 1 ies in the Allegheny Plateau physiographic province . Along the merid ian of the Western New York Nuclear Service Center site, the land surface rises from an elevation of approximately 250 feet at the Lake 0 Ontario shor eline southwa r d to about 2250 feet at the Pennsylvania I ine . The preglacial erosion surface in this area was a maturely dissected upland with deeply incised valleys . Many of these valleys have been deeply buried by glac ial deposits with the result that much of the present drainage is post-glac i al and bedrock valleys, wh ich have a depth and direct ion varying from the present ones, may be del imi ted by well data. The regional topo-graphic slope is underlain by a th ick series of flatlying sedimentary rocks (shales, sandstones and limestones) up to as much as 9000 feet in th i ckness . The rocks actually dip gently to the south at 20 to 40 feet per mi le . The result is that, as one goes from north to south, the sedimentary rock section progressively increases in thickness and younger formations appear at the surface.

The depth to crystalline 11 basement11 rocks at the site is esti mated at about 7000 feet . In the upper 2000 feet of rock section a lateral change of rock type also takes place in which the relative percentage of shale increases westward away from the Genesee River Valley .

2. 16 Much of central and western New York is underlain by a salt basin which is thickest beneath the central Finger Lakes and trends both east and west . Approximately 10,000 squa re miles of New York State is underlain by 0 this salt . The salt bed beneath the New York Service Center site, based on gas well records, should range from 11 feet to 30 feet in th i ckness .

0

2. 17 All of western New York, with the exception of the area generally encompassed by Allegany State Park, is over-lain by a veneer of glacial deposits left by the last glacier . Most of this consists of till (ground up clay-rich rock fragments containing cobbles and pebbles) and thick deposits of sand, gravel and clay.

2.18 In the specific area of the Western New York Nuclear Service Center, the overlying sections of unconsolidated materials have been explored by 108 power auger holes, 14 deep wells, and a seismic survey.

Approximately 38 of the test holes were drilled in the construction area with a power auger equipped with continuous flights, 6 inches in diameter. Screened observation wells, 1-1/4 inches In dlamete~ were installed in or adjacent to most of these auger holes . Such test holes and wells are designated 11 PAH- 11

These holes range from 6 to 40 feet in depth . Samples were collected at 5-foot intervals by driven split-tube samplers or, in a few instances, from the auger. Seven deeper holes were drilled by other methods, but were also sampled with the split-tube sampler. These deeper holes are referred to as 11 drill holes", and are designated 11 DH- 11 or 11 UDH- 11

The 1ocat ions of the power auger and dr i 11 !

holes are shown in Figure 2. 18a. The locations of the seismic points I I

are shown in Figure 2. 18b.

2.19 Surface and bedrock profiles taken along two of the seismic 0 lines shown in Figure 2 . 18b are given in Figure 2.19a. Both can also be seen in the geologic cross sections sh<Mn later in Figure 2 . 23. The shale and siltstone bedrock Is exposed in the upper valley walls of Buttermilk Creek Valley. These belong to the Machias formation of the Upper Devonian Canadaway Group. They are exposed in deep rock cuts of the lONer portion of Buttermilk Creek not far from its confluence with Cattaraugus Creek. These are the only rocks exposed in the area .

Information concerning the bedrock at depth is summarized from geological investigations of the rock sections In neighboring areas and from incomplete logs of old wells drilled for gas. Within and just outside the perimeter of the site, the rock section is estimated from these observations to be as shown in Table 2. 19. It will be noted that the site is underlain by a thick series of flatlying gray and black shales down to the top of the Onondaga limestone at an estimated depth of 2000 feet. Included in this section are 6 black shale layers having an estimated thickness respectively of 120, 20, 185, 20, 20 and 30 feet.

In addition, there are two dark gray shales having a thickness of 80 and 95 feet. The black and dark gray shales are uniformly impervious, but fissile. An additional thickness of limey shales and I imestones would be penetrated beneath the Onondaga limestone with the Syracuse salt member of the Salina formation at a depth of approximately 2700 feet. The succeeding stratigraphic section also includes shales, sandstones and limestones, but particular attention should be drawn to the existence of two deep saline aquifers which have been identified in well logged gas wells 20 miles west and 13 miles northeast . These are 0 the Oswego sandstone, 90 feet thick at an estimated depth of 4500 feet and the Theresa formation, 300-650 feet thick at an estimated depth of 6775 feet. This discussion is summarized schematically in Figure 2. 19b.

Figure 2. 1Ba Boring Location Plan Western New York Nuclear Service Center 0

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Table 2.19 Estimated Rock Section Underlying the Western New York Nuclear Service Center Depth Formation Feet Canadaway Group Caneadea-Machias gray shale and siltstone 425 Hume very dark gray shale so South Wales gray shale 160 Dunkirk black shale 120 Java-West Falls Group Hanover gray shale 120 Pipe Creek black shale 20 Angola gray shale 370 Rhinestreet black shale 185 Sonyea Group Cashaqua gray shale 85 Middlesex black shale 20 O* Genesee Group West River gray shale 25 Genesee black shale 20 Haml 1ton Group Centerfield-Leicester gray shale and limestone 235 Levanna very dark gray shale 95 Stafford limestone 10 Oatka Creek black shale 30 Onondaga limestone Total thickness to top of Onondaga 2,000 0

Figure 2.19b Stratigraphic Cross Section of the Western New York Nuclear Service Center Site 0

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2.20 Data obtained so far Indicate that the present stream of Buttermilk Creek Valley flows mainly on glacial deposits and recent alluvium and is underlain at depth by a deep pre-glacial bedrock gorge which trends approximately N 250 Wand probably initially drained north-ward past Springville and Boston across the present course of Cattaraugus Creek. This gorge apparently has an average depth of 550 feet and slopes northward. Its configuration is more rugged than the present land surface. The present valley of Buttermilk Creek was eroded in uncon-solidated glacial materials during the 10,000 to 15,000 years since the disappearance of the last glacier. The much larger valley cut into the bedrock beneath the glacial deposits was eroded by stream action over a period of at least 60 million years and was probably deepened further by glacial scour as the ice moved down this bedrock valley . The difference in the power of the erosive agents and the length of time over which the erosion was accomplished adequately accounts for the discrepancy in size of the valleys.

2.21 The glacial deposits in the Buttermilk Creek valley range from 5 to 560 feet or more In thickness . This thickness is neither uniform and consistent in lithology, nor the result of a single deposition . Glacial ice advanced over, and melted back from, this area several times. During each such oscillation, a series of deposits, quite diverse in character, were laid down. The glacial deposits are thinnest on the higher hills around the perimeter of the site where they 0 constitute a thin veneer over the bedrock surface. These deposits thicken toward the central part of the Service Center where they partly fill the pre-glacial bedrock valley. There are two principal types of material at the surface in the central part of the site:

1. Till, a very fine-grained heterogeneous mixture of clay and silt which contains minor amounts of sand and stones; it is generally dense, compact and moist, and is dark blue-gray in color. In the upper few feet, however, the color is a yellow-brown due to oxidation of contained iron during soil development.

2. Coarse granular deposits, consisting largely of sand and pebbles up to several inches in diameter, but also containing minor amounts of silt and clay . The color of the granular deposit ls yellow-brown to depths of about 15 feet, and a dark greenish-gray below this depth . These deposits are stratified or well sorted as to grain size in some places, but not in others. These deposits were laid down at different times and under different conditions, but their history of origin is not important to our present discussion.

Drilling and field mapping have disclosed the existence of two additional types of deposits in the subsurface . These are:

0

3. Outwash; coarse granular deposits of stratified, well sorted .

sands (S) and gravels (G). Some deposits appear to be thin-bedded units of both sands and gravels (SG, GS). Such deposits are dark greenish-gray in the drill holes, but are oxidized yellow-brown where exposed in valley walls . These deposits were laid down by melt-water streams from the ice sheets .

4. Lake deposits; fine-grained, thin-bedded, fine sands, silts, and clays (V) with minor amounts of fine pebbles. Individual beds are usually well sorted . These deposits are dark blue-gray, compact, dense, and moist. Such materials were deposited in melt-water lakes impounded between the ice front and higher ground in the valley south of the Service Center. In their gross aspects, they strongly resemble the till previously described, differing chiefly in their laminated lithology and lower pebble content.

2 .22 The surface distribution of the principal deposits described in the previous paragraph is shCMn in Figure 2.22a . The coarse granular deposits overlie till in a broad belt along the lower slopes of the high hills to the west and in an area extending out onto the northern part of the area east of Erdman Brook. The thickness of these deposits ranges from 0 to 25 feet. The tops and upper slopes of the hills west of the construction area are covered with 3 to 10 feet of till overlying bedrock . The till in these areas is oxidized and leached of calcium carbonate to nearly its full thickness. Locally, the surface is 1 ittered with stones ranging from pebbles to boulders due to erosion of the finer materials from the till . The till beneath coarse granular deposits on the lCMer slopes, and that which is at the surface in the central part of the construction area, is a fairly uniform sheet from 20 to 30 feet thick. In much of the area between Buttermilk Creek and Erdman Brook the till sheet is almost entirely clayey and silty. However, in much of the area from Erdman Brook west to the lower hill slopes, the lONer parts of the till sheet contain a considerable amount of very fine sand, possibly as much as 20 per cent. The sandy zones appear to be related to the underlying materials . More detail on the surficial deposits is given in a generalized engineering soil map, Figure 2.22b.

2.23 Figure 2.23 gives three geological cross sections drawn along the section lines indicated in Figure 2 . 22a in the areas in which construction will take place . All three cross sections show the relationships of the surficial deposits just discussed. Sections A-A' and B-8 1 also show the lower sandy zones in the uppermost till sheet as "SBT11

All three sections show a thin layer of sand (S) at an altitude of about 1350 feet . It is apparent from the relationships of the upper till sheet, the sandy till zones, and the thin sand unit that they are related . The sand unit has been destroyed in some areas by incorporation into the overlying till sheet as the till sheet was being deposited.

Geologically, this is to be expected in till sheets and is not significant in itself. However, in this instance it relates directly to ground-water conditions on the site, and will be discussed later in this regard.

Figure 2 . 22a Map of Construction Area Showing Distribution and Lithology of Surficial Deposits 0

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AT 1 I AT Coaro1-9rolned depollls. sondy ond stone)..

" Fine-gra lned 1111, cla7e7 and silly.

~ '"° HT c

EI AT

..::+/----~~~""""~ --------

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s Sand Grave t

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.. IT La111lnaled sand*, sills, and cla71.

v ~Sl~mped

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~ SIT

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____ __ y SCALI.

... - .... MOL'U'I' ll~-----..1..--------------------~---------------------------'

Geolo9lc cross-sections through tlle construction area.

=-r-0 2.24 The sequence of deposits encountered In DH-6 (Sections A-A' and C-C', Figure 2.23) may be considered as generally representative of those in the central valley area. The generalized section is as follows:

Depth Below Land Symbol Unit Surface (Feet)

BT Till, dark blue-gray silt and clay '*

small pebbles; dense, compact, moist O to 21 s Sand, coarse, some. f lrie sand* * ~nd .

s i.1_t*, ;w~ t~r :* :bea*r Ing: 21 to 25t BT Ti 11 , as before 251- to 76 AT Gravel, coarse, and sand; silty, compact, permeable but apparently not water-bearing 76 to 80 s Sand, coarse, some silt and fine gravel So to 88 0 BT Till, as before, abundant fine pebbles 88 to 115 s Sand, some silt and fine gravel, compact 115 to 117 BT Till, as before 117 to 1251 G Gravel, coarse, sparse fine material 125! to 126i-BT Ti 11, as before 126i to 135 G Gravel, coarse to fine, sparse fine material 135 to 141 BT Till, as before 141 to 178 S Sand, some fine gravel and silt 178 to 185 SBT Till, as before, plus 2<>°~+/- very fine sand 185 to 240 In DH-4 (Section B-B', Figure 2.23), which is In the specific plant site location, the following sequence of deposits were encountered:

0

Paragraph 2.24 (continued) 0 Depth Below Land Symbol Unit Surface (Feet)

AT Gravel, coarse, and sand ; scattered cobbles, very silty; brown, friable, unstratified, damp O to 15 v Silt and fine sand; brown, stratified, sand laminae up to~

inch thick 15 to 16-l BT Till , brown silt, coarse stoney and sandy; unstratified, moist 16t to 25!

BT Till, silt, clayey, gray-brown; occasional pebbles, less than t inch diameter; unstratified, damp 25! to 29!

s Gravel and sand, approximately 200/o silt and clay ; ~ray, tough~

unstratified (?}, damp 29! to 31-l BT Till, dark blue-gray silt and clay, contains abundant pebbles up to 0 1! inches in diameter; tough, dense, damp 31! to 40 BT Silt, clayey, gray, very sparse coarse material; laminated (?) .

tough, dense, moist (possibly till) 40 to 41!

BT Till, as at 31! to 40 feet 41! to 61 SBT Till, very stoney with flat cobbles; hard, compact; poor recovery, losing drilling water 61 to 62 SBT Till, greenish-gray, silt, clayey, abundant smal 1 pebbles; very tough, damp 62 to 62t SBT Till, as at 61 to 62 feet; sandy 62! to 64-!

SBT Till, gray-green, sandy; abundant pebbles up to 1 inch diameter; very little material smaller than fine sand; pebbles are approximately 50% of sample (hard boulder at 70 to 70! feet). Unstratified, very compact, damp . Unit drains drilling mud and water from hole overnight and during drilling 64! to 81!

0 Depth Below Land Symbol Unit Surf ace (Feet)

seT Til I, as at 64! to Sit, but less moisture and smaller pebbles 81! to 90 SBT Till, as at Bit to 90, but very sandy and with profuse fine to medium pebbles; silty, tough, damp 90 to 103 SBT Till, dark gray silt and clay, abundant fine pebbles, sparsely fine sandy; dense, tough, damp.

Becomes more sandy below 110 feet 103 to 115!

Shale, gray-green, thin-bedded, I moderately hard 11st to 120-5/6 Field study of drill samples and exposed sections indicates that the several till sheets shown in the cross sections are nearly Identical in texture, color, and composition. The cross sections Indicate that some of the outwash units (S, G) and lake deposits (V) are discontinuous.

This may be due to local non-deposition or to local destruction during the deposition of the subsequent till sheets as previously described .

0 Local discontinuity is typical of glacial deposits.

2 . ZS Test drillings have gone to a maximum depth of 240 feet in one test hole (DH-6). The other drill holes were terminated at 200 feet or at bedrock, whichever was reached first. It may reasonably be anticipated that the deeper-lying glacial deposits will be similar in character to those described above.

2.26 During the exploratory program, 50 samples of the glacial deposits and bedrock were collected for various laboratory analyses.

These analyses, and the number of samples selected for each, are as follows:

Ion exchange capacity 50 pH 50 Clay mineralogy 9 Semi-quantitative spectrographic analysis 20 (from the 50)

Rapid rock determination of rock chemistry 15 The analytical work was done by the Geochemistry and Petrology Branch, United States Geological Survey. In addition to this work, the Atomic Energy Commision at Oak Ridge National Laboratory analyzed 8 of the 50 samples for ion exchange capacity in the presence of radionucl Ides .

0 2.27 The chemical compositions (as oxides) of 8 representative samples, as determined by rapid rock analytical methods, are I isted in Table 2.27. The most notable differences in the composition of the materials is in the amount of Si02 and Al203 in three of the samples (Nos. 159220, 159221, and 159429). These three analyses reflect the sandy nature of the deposits from which they were obtained. Position of the samples may be determined from the cross sections In Figure 2.23.

The relatively uniform composition of the till sheets is also indicated by the analyses.

2.28 Ion exchange capacity and pH are reported in Table 2.28. The pH was determined on 1:10 soil-water mixtures of each sample . One-gram samples, crushed to pass a 60-mesh sieve, were leached overnight (16 hrs) in IN neutral NH4Cl. The sample was separated from the leachate by centrifugation, and washed free of excess NH4Cl with ethyl alcohol. The exchange capacity was then determined by ammonia distillation . It can be seen that most of the samples were slightly alkaline and that the ion exchange capacity is quite high, ranging from 3.5 to 18.8 meq/100 grams and averaging about 10.

2.29 Eight samples were submitted to Oak Ridge where ion exchange studies using cesium, strontium, and ruthenium as radiotracers were done by T. Tamura of the Health Physics Division. The samples are identified and the pH and particle size shown in Table 2 . 29a. The data on cesium sorption using 25 ml of Oak Ridge tap water and 0 . 5 gram of sample (see Table 2.29b) shON that the material has a high affinity for this element. If 150 ppm of potassium is added, the sorption is reduced to roughly 1/6 of the original tap water value (see Table 2.29c) . These results suggest that movement of cesium will be limited under ground-water conditions.

2.30 Movement of strontium is of prime concern, since soils do not normally exhibit high selectivity for this element. Tests were made using Oak Ridge tap water, demineral lzed water with 15 ppm calcium, and demineral ized water with 150 ppm calcium, and on four selected samples New York well water was used . The New York well water was not used on all samples, since it did not arrive until tests were well under way.

The tests were conducted with 0.5 gram of sample in contact with 25 ml of appropriate solution; the suspension was shaken continuously on a mechanical shaker, and periodic samples were taken to measure the amount of sorption. Table 2.30a shows the results of all samples tested with Oak Ridge tap water . Note that the stront ium l<d is much ICMer than those reported for cesium, but that there is a significant amount of sorption nonetheless . In Table 2.30b are shCMn the results of experiments carried out using demineral ized water to which 15 ppm calcium was added .

Finally, in Table 2.30c, there are shown the results of the four tests run using New York well water as the vehicle. The similarity of these three sets of data suggests that all three waters contained about 15 ppm calcium. When a series 'of tests was run using 150 ppm calcium in 0 demineralized water, the Kd was reduced to about 1/4 the tap water value.

This suggests that the control I Ing feature of strontium Kd is the calcareous nature of the sediment.

I 0 0 0 Table 2.27 Chemical Anal:t:ses of Glacial De~os1ts

. a Lab Number - 159429 159430 159219 159220 159221 159431 159432 159433 Field Number - DH-4 OH-4 DH-6 OH-6 DH-6 DH-7 DH-7 DH-7 15-16-i feet 25-26-!' feet 36-i-38 feet 87-89 feet 170-171 feet 8-37 feet 37-52 feet 52-75 feet Coarse Si I ty s 11ty Si I ty Si I ty Sandy Si I ty Materials Granular Clay Clay Si lty Clay Clay Clay Clay (see Figure 2.23) Deposits Ti 11 Ti 11 Sand Ti l 1 Ti 11 Ti 11 Ti 11

{AT) {BT} {BT} {S) {BT} {BT} {SBT) {BT)

Si02 70 . 7 56 . l 58 . 2 68 .o 67.0 56.6 58 . J 56 . 5 Al203 10 . 9 14. 5 14. 4 11.0 12 .4 14. 7 13.5 15.9 Fe203 2.7 2.9 2.2 2 .0 2. 3 2. 4 I. 9 2.0 FeO 1.6 2. I 2 .8 2.2 2. 9 2. 8 2. 7 3 ,3 MgO 1.6 2.8 2.6 1. 9 1.8 2 .6 2. 3 2 .8 cao 2.9 5 .8 5,5 3.9 2.8 5.8 5.8 4 .4 Na20 0.94 o.64 0.76 1.0 0.77 0. 71 0 . 73 0.65 KzO 2.2 3. I 3. 1 2.3 2.4 3.2 3. 0 3.5 H20- 0 . 60 1.4 0.57 0.36 0.30 0.75 0 . 56 0 . 77 H20+ 2.6 3,7 3 .6 2. 8 3.2 3,7 3. 9 4 .2 Ti02 0 . 77 0 . 76 0 . 78 0 . 76 0 . 92 0 . 79 0. 72 0 . 79 P205 0 . 13 0 . 13 0 . 10 0 . 10 0 . 10 o. 13 0. 12 0 . 13 MnO 0 .06 0.07 0.07 0.07 0 .07 0 . 06 0 . 06 0 . 06 C02 2.3 5 .6 s.o 3.6 2.6 5,3 5.6 4.o Sum 100 . 00 100.00 100 .00 100.00 100 . 00 99 . 00 99 . 00 99 .00 a Analyses by Geochemistry and Petrology Branch, United States Geological Survey, using rapid rock methods.

0 Table 2.28 Ion Exchange Ca~acities and eH of a Number of Soil Sameles Boring Depth of Sample Exchange Capacity Location (Feet} _.£!!.._ meg/100 grams DH-6 36-! - 38 8.57 10 . 2 DH-6 87 - 89 8.59 7.0 DH-6 170 - 171 8.49 6. 9 PAH-2 26t - 28 8.46 16 .8 PAH-3 25 - 26!

(A - Fine) 8 .58 11.6 PAH-3 25 - 26t (B - Coarse) 8 . 75 3.8 PAH-7 5 - 15 7.18 6.o PAH-7 20 - 21 8.49 13.5 PAH-29 5 16! 8.20 12. 1 PAH-39 0 6 5.70 7.4 PAH-39 6 - 32 8.47 8.1 PAH-42 0 - 6 8.00 12 .6 PAH-42 6 -- 32 8.30 17.4 0 PAH-50 PAH-50 12 0

12 21 8.34 8.48 6.9 6.9 PAH-51 0 - 6 7.35 17 .0 PAH-51 6 - 14 8.25 12 .6 PAH-52 0 - 12 8.48 15 .4 PAH-52 PAH-59 12 10

- 23

- 40 8.54 8.33

11. 3 9 .8 PAH-66 0 - 9 8.84 6. 7 PAH-66 DH-13 9

st

- 20

- 10 8.65 8.56 9,5 9 .6 DH-4 5 !- 5.43 6. 1 DH-4 20 - 21! 8.70 1.2 DH-7 0 - 8 8.45 17.7 DH-7 8 - 37 8.33 10 . 1 DH-7 52 - 75 8.33 17 . 9 DH-7 75 - 115 8.40 4 .3 PAH-35 5 - 6! 8.76 6.0 PAH-35 ti - 26! 8.45 9 .8 PAH-58 10 - 35 8.47 10 .0 PAH-62 7 20 8.33 12.3 PAH-87 0 45 8 .45 9 .0 PAH-95 0 10 7 .41 18.8 PAH-95 15 7.58 12.8 PAH-92 0 - 15 6.25 5. 1 PAH-92 15 - 40 8 .20 10.7 0 - 20 0 PAH-94 PAH-94 20 - 40 8.46 8.54 18.5 11.8 DH-3 8.86 5.4 DH-4 8.99 3,5 DH-5 8.95 5.6

0 0 Table 2. 29a Mechanical Analysis Plus pH of Eight Selected Samples Field Number Particle Size DH-3 OH-4 DH-4 DH-7 PAH-1 PAH-4 PAH-4 PAH-10 and pH 10-1 li Feet 15-16i Feet 25}-26} Feet 37-52 Feet lot-12 Feet 11%-13 Feet 21-23 Feet 5-15 Feet

% >2 ITITI 6 .53 32.68 65 . 53 22.42 6 . 41 4.46 36.62 65 .48

% 50 J.J - 2 mm 53.51 22 .09 1.80 18.78 12.67 11 .98 33.01 15 .84

% 2 ).J - 50 )J 30 . 17 32.55 13 . 74 33.88 43.81 49. 72 21.46 12.45

%<2).J 8 .93 12 . 19 18 .28 24 .92 35 . ~3 32 . 25 8.63 6.04 Total 99 . 14 99 ,51 99 .35 100 .00 98 .82 98 .41 99. 72 99.81 pH 8 .45 8.25 8 . 15 7.73 7.74 7. 90 8. 05 7.81

0 Table 2.29b Cesium Sorption on New York Soil Samples Clay: 0.5 g of< 2 mm fraction.

Solution: 25 ml of Oak Ridge tap water plus 10,500 cpm per ml cs137.

1-Hour Contact 4-Hour Contact 24-Hour Contact Field Number % Sorpt ion Kd* % Sorpt ion Kd°ir % Sorption Kd*

DH-3 10-1 lf Feet 96.57 1410 97.44 1910 98. 72 3860 DH-4 15-16! Feet 98.02 2480 98.71 3830 99.38 8020 DH-4 25t-26t Feet 98.51 3310 98.51 3310 98.99 4900 DH-7 37-52 Feet 98.18 2700 98.45 318() 98.90 4500 PAH-1 0 1ot-12 Feet 98.92 4580 99.08 5380 99.27 6800 PAH-4 11 t-13 Feet 97.51 1960 98.30 2890 98.53 3350 PAH-4 21-23 Feet 95.73 1120 97. 15 1700 98.56 3420 PAH-10 5-15 Feet 96.91 1570 97. 79 2210 98.65 3650 0

_ Per Cent Radionuclide Sorbed/Weight of Material Kd - Per Cent Radionuclide in Solution/Volume of Solution

0 Table 2.29c Cesium Sor~tion on New York Soil Same I es Clay: 0.5 g of< 2 mm fraction.

Solution: 25 ml of 150 ppm potassium plus 19,000 cpm per ml csl37.

I-Hour Contact 4-Hour Contact 24-Hour Contact Field Number % Sorption Kd* % Sorption Kd* % Sorpt ion Kd*

DH-3 10-1 I! feet 92.22 595 94.72 900 94 . 14 805 DH-4 15-16-! Feet 92 . 73 640 95.58 1080 93 . 34 700 DH-4 25!-26-! Feet 95 . 23 1000 97,71 2130 97.36 1840 DH-7 37-52 Feet 86,57 320 88.08 370 86.86 300 PAH-1 0 10t-12 Feet 93,54 725 95.60 1080 94. 03 790 PAH-4 11t-13 Feet 88 . 99 405 91 . 36 530 89 . 15 410 PAH-4 21-23 Feet 83 . 22 250 87 .44 350 89 . 59 430 PAH-10 5-15 Feet 91 .62 545 93,53 725 91 . 93 570 0

_ Per Cent Radionuclide Sorbed/Weight of Material Kd - Per Cent Radionuclide in Solution/Volume of Solution

0 Table 2.30a Strontium Sorption on New York Soil Samples Clay: 0.5 g of .(2 mm fraction.

Solution: 25 ml of Oak Ridge tap water plus 12,000 cpm per ml sr85, 1-Hour Contact 4-Hour Contact 24-Hour Contact Field Number % Sorpt ion Kd* % Sorption Kd* % Sorption Kd*

DH-3 10-l li Feet 38 . 86 32 40 . 99 35 42.87 38 OH-4 15-16i Feet 51.67 53 54.12 59 55 .05 61 DH-4 25t-26! Feet 58 . 12 69 57.75 68 59 . 51 74 DH-7 37-52 Feet 30. 15 22 29.64 21 29 . 99 21 PAH-1 0 1ot-12 Feet 40 . 62 34 37. 78 30 38.96 32 PAH-4 11 t-13 Feet 38.80 32 37 . 79 30 37.82 30 PAH-4 21-23 Feet 25.62 17 26 . 98 18 27 .97 19 PAH-10 5-15 Feet 49. 78 50 48.57 47 50.74 52 0

_ Per Cent Radionuclide Sorbed/Weight of Material Kd - Per Cent Radionuclide in Solution/Volume of Solution

0 Table 2.30b Strontium Sor2tion on New York Soi 1 Samples Clay: 0.5 g of <2 nvn fraction.

Solution: 25 ml of 15 ppm calcium plus 12,000 cpm/ml sr85 .

I-Hour Contact 4-Hour Contact 24-Hour Contact Field Number % Sorption ~ % Sorption ~ % Sorption ~

DH-3 I0-11 t Feet 40.96 35 46.67 44 42. 10 36 DH-4 15-16-l Feet 54. 15 59 56.oo 64 57,56 68 DH-4 25f-26t Feet 61.94 81 62.63 84 60.78 77 DH-7 37-52 Feet 32.78 24 32.87 24 31.40 23 PAH-1 1ot-12 Feet 42. 12 36 40. 14 34 39,38 33 0 PAH-4 11 t-13 Feet 40.70 34 39,86 33 39.26 32 PAH-4 21-23 Feet 28.78 20 29.90 21 30. 11 22 PAH-10 5-15 Feet 49. 77 so 49.99 50 51. 52 53 0 = Per Cent Radionuclide Sorbed/Weight of Material Per Cent Radionuclide in Solution/Volume of Solution

0 Table 2.30c Strontium Sorption on New York Soil Samples Clay: 0.5 g of <:2 mm fraction.

Solution: 25 ml of New York well water plus 11,000 cpm per ml sr85.

1-Hour Contact 4-Hour Contact 24-Hour Contact Field Number % Sorption !d!.... % Sor(!tion !d!.... % Sorption ~

DH-4 15-16! Feet 58 . 68 71 57.62 68 59. 77 74 DH-4 25t-26! Feet 62.12 82 59 ,97 75 60.65 77 PAH-1 1ot-12 Feet 43.98 39 4o.54 34 41.97 36 PAH-10 5-15 Feet 50.80 52 49.25 49 50.62 51 0

0

Kd _ Per Cent Radionuclide Sorbed/Weight of Material

- Per Cent Radionuclide in Solution/Volume of Solution

2.31 A few tests were run using ruthenium tracer, but the results are not too meaningful since they were conducted using seep ruth~nium (ruthenium which had percolated through the Oak Ridge soil), and thus the sorb,ble and filterable portions have been removed. Since

tests conducted at Oak Ridge using waste ruthenium {not seep ruthenJ um) have shown this element to precede strontium, one can also expect t~is situation to hold at New York. The data obtained are . shown in Table 2.31.

2.32 Clay mineralogy determinations were carried out on three samples as follows:

Field Number Description PAH-35, 5-6t feet Sandy ti 11 PAH-94. 0-20 feet Outwash OH-4 Shale core The samples were wet sieved to remove the sand. The clay and silt were separated by centrifugation, utilizing Stoke's law. The fractions were then dried and weighed . The percentages of the various fractions are as follows:

Sam~le % Sand {>62JJ} % s i 1t {62-2~} % C1a~ {< 2!:!}

0 PAH-35 5-6! feet 39 . 6 47.6 11.0 PAH-94 0-20 feet 46 .4 30.4 22 . 4 DH-4 83.5 12.3 5.6 The fractions separated during size analysis were used to determine the mineralogical content of each sample. The mineral constituents were determined by X-ray diffraction. Inasmuch as many factors , in addition to the quantity of a mineral, affect diffraction intensity, these estimates are not intended to give more than a very general indication of the relative amounts of the mineral present which amounts are shown in Table 2.32.

Hydrology 2.33 All of the surface drainage from the entire site, as well as the drainage from the upper layers of ti 11, Is collected in Buttermilk Creek through a series of small tributaries on either side of the creek.

At the northwest corner of the site, Buttermilk Creek joins a larger stream, Cattaraugus Creek. The conf Juence of these two streams and both sides of Buttermilk Creek from its entry into the property at the south to the confluence (a distance of approximately 5 miles) are included within the site boundaries.

0

~======'11='="'-========"'="====-=--~~==-~=====================-=-==-===*============---=-=~============-=='="'-===iF 0

Table 2.31 Ruthenium Sorption on New York Soil Samples Clay: 0.5 g of <::2 nm fraction.

Solution: 25 ml of ruthenium from seepage pits at ORNL diluted 1:1 with demineral ized water.

1-Hour Contact 4-Hour Contact 24-Hour Contact Field Number % Sorption ~ % Sorption .!Sd!:.... % Sorption ~

DH-4

.1S-t6t Feet 1.82 0.9 1.68 0.9 1.42 0.7 DH-4 25f-26-l Feet 0.79 o.4 0 . 17 o. 1 0 . 54 0.3 PAH-1 lot-12 Feet 1.25 o.6 1. 51 o.8 0.87 o.4 PAH-10 5-15 Feet 1.68 0.9 0.55 0.3 0.00 0.0

Per Cent Radionuclide Sorbed/Weight of Material Kd = Per Cent Radionuclide in Solution/Volume of Solution

===-=====Jb.,==""""'====-~===============-=-=***~=====-==-==-==================~========-=-=-=-==-=-~-======i<

0 Table 2 . 32 Approximate Mineralogical Content of New York Soil Samples Estimated Amount Sample Mineral Content {Parts in Ten)

PAH-35 s i 1t Q.uartz 6 5-6! Feet Feldspar 2 Ool omi te 1 Mica 1 Calcite ? tr Chlorite ? tr Clay Mica 3 Q.uartz 2 Chlorite 2 Mixed Layered Chlorite-Mica 1 Vermiculite 1 Kaolinite 1 Feldspar tr PAH-34 Si It Q.uartz 5 0-20 Feet Calcite 2 0 Dolomite Feldspar 1

1 Mica 1 Kaolinite tr Chlorite ? tr Clay Q.uartz 3 Mica 3 Mixed Layered Chlorite-Hontmor i l l on i te 2 Chlorite l Mixed Layered Chlorite-Mica l Kaolinite tr Feldspar tr Calcite tr DH-4 Sand Q.uartz 5 Feldspar 2 Calc i te 2 Mica l Chlorite tr Kao Ii n i te tr silt Quartz 6 Feldspar 2 Chlorite 1 0 Kao Ii n I te Mica 1

tr Ca le I te tr

~=-=-=-== ....======================-=====w=-==*===============================-==:===========-====~

===t 11 I

0 Tab 1e 2. 32 (;Continued}

Estimated Amount Sample Mineral Content (Parts in Ten)

DH-4 Clay Mica 4 (continued) Chlorite 3 Quartz 2 Kaolinite 1 Feldspar tr 0

0

==:===-=-=-=If.=========-=-==-:=..-====-==-=======================-=-=-=-=-.=-=-~======================~

0 2.34 Cattaraugus Creek flows in a generally westerly direction through Zoar Valley, Gowanda, and the Cattaraugus Indian Reservation and empties into Lake Erie 27 miles west of Buffalo. It is 20 stream miles from the confluence of Buttermilk and Cattaraugus Creeks to Gowanda and another 19 miles to the mouth of Cattaraugus Creek. The nearest gaging station to the site on Cattaraugus Creek is at Gowanda, where one is maintained by the United States Geological Survey. The total Cattaraugus drainage area above Gowanda is 428 square miles; above the confluence of Buttermilk Creek with Cattaraugus Creek, it is 218 square miles; the drainage area for Buttermilk Creek itself is 25 square miles. A 15-year sunvnary of data taken at the Gowanda station is given in Taple 2.34 . Figure 2.34 gives flow duration developed for this station by the Surface Water Branch of the Survey. These curves indicate average conditions for the period of record as compared with a single year. That fl<M conditions in a given year may depart widely from the average is obvious. Based on these data and the drainage areas given above, the following can be calculated :

Average Daily FlOfl Over a 15-Year Period Cattaraugus Creek as measured at GOflanda 704 cfs Cattaraugus Creek at 0 Buttermilk Creek Buttermilk Creek 358 cfs 41 cfs 2.35 A network of gaging sites was established on the Service Center in October, 1961. The network consists of a continuous-stage recording station and 10 other sites on Buttermilk Creek and its tributaries at which discharge is gaged periodically . The locations of these stations are shCYWn on Figure 2.35a. The measurements made through January, 1962, are tabulated In Table 2.35. A comparison of available discharge data for Cattaraugus Creek and Buttermilk Creek is shown in Figure 2.35b. The ratio of flows in the two creeks shown therein is not significantly different from that calculated from the ratio of drainage areas.

2.36 There are no villages or cities downstream from the site which rely on Cattaraugus Creek for their water supply and there are no potable water sources or large water supplies used in the immediate area. Lake Erie is used as a source of public water, but there is no such use closer than 7 miles from the mouth of the Cattaraugus . The closest Lake Erie water uses are shown in Table 2 .36a. Cattaraugus water is used dONnstream from the site for industrial and recreational purposes as shOfln in Table 2.36b. A map showing the public water supply systems of the communities in the general area of the Western New York Nuclear Service Center is shown in Figure 2. 36a. Detailed supporting data for this figure are given in Appendix 2.36. There is no commercial or 0 industrial use of water on or within 4 miles of the Service Center. All existing water supplies in the area are for domestic and livestock uses.

Most of these supplies are obtained from shallow, large-diameter dug

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I Table 2.34 Fifteen-Year Summar:t: of Cattaraugus Creek FICM Data Gowanda, New Yorka I

I ..

Water Minimum Average Flow For Average Daily Flow Year Seven ~onsecutive Da~s Fo.r' Period.*of Record Ii Ending Oa i l:t: F lcm - cfs Flow Period of Number Flow

~ Sept 30 Maximum Minimum Mean cfs Occurrence of Years cf s

~:1 1941 9 ,860 53 591 59 Sept 24-Sept 30 591

~

1942 22,900 66 642 94 Oct I-Oct 7 2 617 1943 13, I00 112 988 117 Sept 24-Sept 30 3 740 i

1944 9,310 81 618 98 Oct 7-0ct 13 4 710 11 i1!

1945 1946 1947 9,230 14,200 15 , 500 52 82 92 832 680 1027 56 91 96 Sept Sept Oct

] -Sept 13 23-Sept 29 5-0ct 11 5

6 7

734 72.5 768

,,11 I; 1948 10 ,800,(1 103 '1 673 112 Sept 13-Sept 19 8 756 1949 4,720 56 536 76 Aug 22-Aug 28 9 732 0 1950 1951 13 , 300 9 , 600 87 75 655 842 94 85 Oct Aug 16-0ct 22 25-Aug 31 to 11 724 735 1952 9,000 62 724 70 Sept 8-Sept 14 12 734 1953 4, 170 71 587 77 Aug 29-Sept 4 13 723 1954b 6,090 56 588 86 July 23-July 29 14 713 1955b 12 , 100 52 582 60 July 20-July 26 15 704 0 a Cattaraugus Creek Drainage Basin, Lake Erie-Niagara River Drainage Basin Series, Report No . 4, New York State Department of Health, April 1957 .

b Provisional data .

II

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0 Figure 2.34 Duration Curves of Daily Flo.-1 Cattaraugus Creek at Go.-1anda, New York 0

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Figure 2.35a Location of Gaging Stations on Western New York Nuclear Service Center

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................................................, .......... 1..e4111i . . . . . . . . . . . ie.etl*.t ... ..,,............ _..,. . . ......

0 Table 2.35 Results of Discharge Measurements Buttermilk Creek Basin Drainage Area Site Latitude Square Measured Discharge No. Name and Location Longitude Mile Date cfs 8 Buttermilk Creek at 42026 02 1 11 10-31-60 1.45 Riceville Station 78037 48 1 11

9. 12 12-20-60 2. 14 6-29-61 3.08 10-19-61 l.80 11-20-61 8.91 12-6-61 15.7 1-8-62 26.3 9 Buttermilk Creek Tributary 42°25 05 I 11 at Fox 78°38 33 1 11 2.08 10-19-61 0.32 7 Buttermilk Creek Tributary 42°26 13 I 11 11 ... 20-61 3 . 61 near mouth near Fox 78°38' 03 11 3 .02 12-6-61 s.41 0 10 Gooseneck Creek at Ri cev i 11 e 42°26 31 78°36 54 1

1 11 11 7.26 10-31-60 12-20-60 1.62 2.20 6-29-61 4.84 10-19-61 2.20 1-8-62 17 .4 6 Gooseneck Creek at mouth 42°16 18 1 11 11-20-61 7.52 near Riceville 78°37' 59 11 7.76 12-6-61 13. 1 5 Buttermilk Creek Tributary 42°26 -, 38 11 10-19-61 0. 14 No. 2 near Springville 78°38 22 1 11 l.69 11-20-61 2.43 12-6-61 2.66 4 Buttermilk Creek Tributary 42°27 *06 11 10-19-61 0. 17 No. 3 near Springville 78°38 31 1 11 1.38 11-20-61 0.74 12-6-61 1. 79 I ll Buttermilk Creek at RR 42°27 26 1 11 12-20-60 4. 18 11 I

Bridge near Riceville 78°38 1 40 11 23.8 6-29-61 10.7 3 Buttermilk Creek Tributary 42°27 45 1 11 10-19-61 0. 11 I No. 4 near Springville 78°39 11 1 11 2.61 l l 61 2.47 11 12-6-61 3.98 II 2 Buttermilk Creek Tributary 42°28 1 02 11 10-19-61 0. 13 0 I I

No. 5 near Springville 78°39 32 1 11 2.07 11-20-61 12-6-61 0.54 0.82 1\

~~*~~~~~~*~~*~~~~~* - *- *-** -*:r-.-=-.*:-=:':"."":.":.::=---*~--:.:...-:=-::-=:-:-.---::"=:--=-":":"~-::.":.":.":":"'==:.-..::-:=:==--=-:=-::._

I

0 Table 2.35 (Conti nued9 Drainage Area site Latitude Square Measured Discharge No. Name and Location Longitude Mi 1e Date cf s Buttermilk Creek near 42°28 1 21 11 10-19-61 5.54 Spr i ngv i 11 e 78°39 1 5411 29.4 10-26-61 19. l 11-13-61 57.0 Gaging Station 11-20-61 29.5 12-6-61 43.8 1-8-62 77.6 2-5-62 310.0 3-5-62 18.8 Buttermilk Creek at Thomas 42°28 1 4911 11-20-61 30. 1 Corners Road near 78°40 '29 30.0 12-6-61 46.0 Sp r i ngv i 11 e 0

0

0 Figure 2.35b Comparative Discharges of Buttermilk and Cattaraugus Creeks 0

0

10 IO *o 0

Table 2.36a Public Water Users of Lake Erie Water in the Vicinity of Cattaraugus Creek Miles from Mouth of User Cattaraugus Creek Angola (northeast} 7 Erie County Water Authority (Sturgeon Point} 12 Wanakah 19 Erie County Water Authority 21 Buffalo 27 0

0 Table 2.36b Uses of Cattaraugus Creek Water DCMnstream From Western New York Nuclear Service Center I ndustr:.ial Use:' ...

Mi 1es From Location Site Use Si 1ver Creek Boi 1er feed and Preservative Company Irving 38 cooling canal purposes Peter Cooper Corp. GCManda 21 Glue processing and condenser waters BrCMn Shoe Company GCManda 20.5 Other Use Area Use 0 Mouth of Cattaraugus Creek to south boundary of Cattaraugus Recreation, fishing, sewage, agriculture and industrial waste Indian Reservation disposal South boundary of Indian Fishing, industr ial, water supply,

..Reservation to south boundary agriculture, sewage and industrial of GCManda Village waste disposal From south boundary of GCManda Recreation, fishing, agriculture Village extended to Buttermilk and industry Creek

0 Figure 2.36a Public Water Supply Systems in the Vicinity of the Western New York Nuclear Service Center 0

LEGEND PUBLIC

WATER

SUPPLY* SYSTEMS ~ WATE!ISHEI> AREA WESTERN

NEW

YORK

NUCLEAR

SERVICE* CENTER OPEN DISTRlllUllON 4 5 6 ~ lll'FOtHlNI RESERWfl v HTAKE 0 WELL ALIXANOIR

... SPRING

@ STAl'CI Pff:

D 'rnEATMENT PLANT

~ WITH FIJ'RATION rJ WITH ~

E8XI WITH 80TH 7

I wells or springs. It appears that in recent years a significant number of drilled wells in bedrock have been constructed on and adjacent to the Service Center to furnish such supplies. One reason for this ls to maintain an available supply in dry periods when springs and dug wells have failed. Reportedly, this occurred during the fall and winter of 1960-61. On Figure 2.36b there are shown the locations of the nearer surrounding wells with the depth and elevation of the well head noted.

Detailed data for each of these are given in Table 2.36c.

2.37 Usable quantities of ground water occur in three aquifers on the site. The term "usable" may here be construed as a yield of l to 10 gallons per minute from a well or spring. The coarse granular deposits at the surface (see Figure 2.22a) constitute the uppermost aquifer in the construction area . This aquifer is referred to as the nonartesian aquifer. The level below which all pore spaces in the aquifer are filled with water is called the water table, and its position is shown by the water levels i n wells screened in this aquifer. A map showing the shape and altitude of the water table by means of contour lines is shown in Figure 2.37 . Comparison of this map, and the topographic base map of the Service Center, indicates that the water table generally follows the configuration of the land surface.

2.38 Water is added to the aquifer by the infiltration of precipi-tation from the land surface down to the water table. However, not all 0 of the precipitation reaches the water table; a considerable part of it is returned to the atmosphere by evaporation and through transpiration of plants, and some flows directly over the land surface to streams.

Because of the permeable nature of this aquifer, however, direct runoff is doubtless considerably lower than in the area underlain by till.

After reaching the water table, ground water moves through the aquifer by gravity-flow and it follows paths that are at right angles to the contours shown on Figure 2.37. This map shows that the ground water is being discharged from the aquifer into the surface drainage system.

2 .39 In much of the site the stream valleys cut completely through the aquifer. An important result of this segmentation is the relatively short distance of travel by the ground water from points of recharge to points of discharge into surface streams. The rate of ground-water movement is determined by the hydraulic gradient and the permeability and porosity of the aquifer. The permeability of the aquifer can be estimated from present data. It may be expressed as a coefficient of permeability, which is defined as the quantity of water in gallons per day (at field temperatures) that will pass through one square foot of the aquifer under a hydraulic gradient of one foot per foot. The coefficient of permeability for this aquifer is approximately 100 gallons per (day)(square foot). Porosity may be described as a ratio of the total volume of pore space to the total volume of rock, and expressed as a percentage. The porosity of the coarse granular deposits is estimated to be about 25°k. An approximate rate of ground-water movement in this aquifer may be determined by using the estimated permeabll ity and porosity, and the distances and hydraulic gradients shown on Figure 2.37. In the area between PAH-38 and PAH-41, the hydraulic gradient is

Figure 2.36b Location of Wells and Springs Used in the Immediate Area of Western New York Nuclear Service Center 0 Legend Well location; number is consecutive number assigned to wells inventoried in Cattaraugus County. County symbol (Ct) omitted.

Q Spring, used for domestic and/or livestock.

A Indicated house abandoned or destroyed; no water supply observed.

N Well observed at homesite; no data available.

0 Table 2.36c Table of Off-Site Well :-Records Western New York Nuclear Service Center Cattaraugus County, New York 0

0

TABLE 2. 36C Table of Off*Sf te Well Records Western New York Nuclear Service Center, Cattaraugus County, N. Y.

Water Level Casing below Depth Depth I Yield Altitude of Diam. Type Water-Bear Ing Land Surface Date of (Gal Ions Wel I Number Type of Wei I (Feet) 11 (Feet) (Inches) Land Surface l/

Formation Y (Feet) Measurement Per Minute) (Feet)

Ct 273 Dug H 11.0 A 11.0 48 Metal and Concrete I un H 8.99 10/21/61 -- 1,330 Ct 274 Ct 275 Dug Drilled H 16.2 H 40.8 A 16.2

-- 20 4

Fieldstone Steel

,1 un br H 10.62 H 19. l 9 10/21/61 10/21/61

1,410 Ct 276 Drilled R130 R 80 6 e. It

-- 1,525 I* br R 70+/- R5 1,360 Ct 277 Ct 278 Drl 1led Drf lled M83.1 H 41.5 6

8 e.

e.

I*

II I

br br M 26.24 H 9.54 10/23/61 10/23/61 I

.... 1,465 1,560 Ct 279 Ct 280 Ori 1led Driven H 78.0 H 12.36 H 12.4 6 B. I* br H 30.07 10/23/61 l

I ,48o Ct 281 Ct 282 Drll 1ed DriJ 1ed H 61.7 H 73.0 D 65

-- '* 5 6

G. I.

Steel B. I.

II un br br H 10.02 H 9.47 M50.54 10/24/61 10/24/61 11/ 7/61 010

.... I ,280 I ,410 1,490 Ct 284 Orf I led 0166 0164 6 br H 9.15 i> e. '* 11/ 8/61 0 2 1,500

~

Ct 288 Drll led D 70 D 20 6 B. I. br R 30 R5 Ct 289 Ori I led R 4o R 15

.... 6 B. 1. br H 4.54 4/20/62 .... 1,555 Ct 290 Ct 291 Orf lled Ori 11 ed H 53.1 H 54.4 D 32 6

6 Steel Steel br br H I 2.43 H 3.92 4/20/62 4/20/62 0 3

-- 1,555 1,367 1,370 Ct 292 Dug H 17.8 A 17.8 36 '"leldstone un*br a Ct 293 Ct 294 Drilled Drilled H 51.3 M48.5

.... 6 6

Steel Steel br br H 10.23 H 15.94 H 6.52 4/20/62 4/21/62 4/21/62 1,780 1,525 1,525 Ct 295 Dug H 15.3 A 15.3 36 ~1 el dstone un*br H 2.20 Ct 296 Dug 4/21/62 1,540 H 10. l A 10.1 24 ~ieldstone &. un-br H 4.14 4/21/62 Concrete 1,730 Ct 297 Dug M 5.3 A 5.3 24 .. feldstone Concrete

&. un

" 2.82-- 4/21/62 -- 1,800 Ct 298 Ct 299 Drilled Dug RJOO M 11.9 A 11.9

-- 48 6 R Steel

~ieldstone br un 3.86 4/21/62

1,820

"" 6.14 1,845 Ct 300 Ct 301 Dug Dug " 6.4 H 12.0 A 6.4 A 12.0 24 36 Tile "f el ds tone un un*br 0.97 4/26/62 ---- 1,560 H 4/27/62 1,580 Ct 306 Ct 307 Drfl led Ori lied H 92.4 R250 6

5 B. I.

R Steel br br

" ss.36 R 15 4/28/62 Rio+

1,570 1,450 Ct 309 Dug " 14.7 A 14.7 36 "iel dstone un H 7.65 Ct 310 Dug 4/30/62 1,420 H 10.S A 10.5 40 "lel dstone un 5.30 Ct 311 Ct 312 Dug Drfl led H 11.9 RIOO IA 11.9 R 90 36 63/8 Fieldstone Steel un*br br M 4.13 5.83 4/30/62 4/30/62 1,420 1,450 Ct 313 Ct 314 Drilled Dug M161.3

" 16.4 ~ 16+4

-- 36 6 B. I.

ieldstone br un H 24.26 M 11+82 51 l/62 51 1/62 51 1/62 R14

1 ,510 1,450 1,475 1

Ct 315 Ori fled Rl30 R 90 .. 6 B. I. br Ct 316 Drfl Jed RIOO .... 4 R Steel br R 25- 1,450 Ct 317 Dri I led R 90 -- 6 B. I. br R flowing flowing ---- 1,515 Ct 318 Orf I led R 90 ~ 60!

6 RB. I. br

4/30/62

1,515 1,570 Ct 319 Drilled R 80 6 R B. I. br Ct 320 Orf I led R 37 6 R B. I. br -- -- 1,580 1,560 11 R - reported 'J,/ un - unconsolidated deposits 'JI Altitude of land surface, fn feet above mean sea level, is estimated from topo nMllp.

H - measured br - bedrock 0 - driller's records A - assumed.

0 Figure 2.37 Contours of Water Table on Western New York Nuclear Service Center 0

0

0 IXNMo\TI*

.. im

--*-er... *-**

...!Li.-tl* .. *lh

m,::ri:;*..!::*:.:-r.*:..t Xl507Altl- ef

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r9~.

UZI~ i:-=.:::-:.r:.**,.* II

....... , .....1.u. ........, .. '"" ** ,. **

Ceo-* l*te,..I

It r.ot.

N 1,0 *to IOO tfO ICALI IM,.,,

j

- ., -*-ti* *- ................. "" .... -*** _,, "* 11161.

0 approximately 30 feet in 1200 feet. The velocity (in feet per day) equals the hydraulic gradient (in feet per foot) times the permeability /Tn gallons per (day)(square feetl7 divided by (7.48 x porosity) which converts gallons per day to feet per day. Thus:

30 x 100 Velocity= 1200 + (7.48 x 0.25)

= 1.3 feet per day This indicates that, under natural conditions, the velocity of ground water in the coarse granular deposits is in the range of l to 2 feet per day.

2.40 The water table fluctuates in response to recharge and discharge.

The fluctuations observed in two wells in this aquifer (PAH-9 and PAH-22) are shown in Figure 2.40. The period of record is too short to show details of the annual pattern or range of fluctuations on the Service Center. Other aquifers of this type in New York normally reach their highest water levels in the spring, decline slowly to a low point late in the fall, and rise during the winter and early spring. Normally, water levels in such aquifers fluctuate about 5 to 10 feet during the course of ..

a year.

2.41 The silty clay till in the construction area is not an aquifer.

0 However, the till is largely water-saturated. Pore spaces in these deposits are very small, and poorly interconnected. The movement of ground water through the till is very slow and almost entirely capillary in nature.

Three undisturbed samples from DH-7 were submitted to the Hydrologic Laboratory of the Survey for determination of porosity, permeability, and grain-size analysis. The results of these examinations are given in Table 2.41. The points at which the samples were taken may be located on Section C-C', Figure 2.23. The permeabilities reported in Table 2.41 are in a vertical direction. Undisturbed horizontal samples were collected from exposed valley walls near PAH-18, -19, and -34. The horizontal permeabil-ities were found to be 0.005, 0.004, and 0.004 gal/(day)(square foot),

respectively.

2.42 The thin sand unit beneath the uppermost till sheet (see Figure 2.23) constitutes a second aquifer in the valley area. This aquifer is referred to as the shallow artesian aquifer on Figure 2.40. It is found in most of the area between Buttermilk Creek and Erdman Brook. The altitude of water levels in this aquifer, and the extent of the aquifer known at this time, is shown on Figure 2.42. The aquifer Is confined above and below by till sheets and the contained water is under artesian conditions. Water levels in the aquifer stand 5 to 17 feet above the top of the aquifer and 8 to 22 feet below land surface. Certain of the data suggest that this sand unit may be completely enclosed by the till sheets and that the contained water may be controlled by capillary phenomena.

Conversely, the water-level fluctuations observed in PAH-1 (Figure 2.40),

which is equipped with a continuous recorder, seem to indicate a normal response to recharge and discharge and appear to follow the expected seasona 1 trend.

0 Figure 2.40 Hydrographs of Wells in the Construction Area 0

0

PAH-22 NonartHlan aquifer PAH-9 NonartHlan aquifer

- g

I on Ii-.~~~~....&.~~~~~"-~~~~-""~~~~~......~~~~--

""c Cl PAH-1 Shallow ortealon aquifer

--Cl)

Cl)

.E 7 II Cl

- 0

.I:.

Q.

II 0

w*u development and tlug V teat to tlll* point Ct272 Bedrock artesian aquifer 90'i--~~O~C~T~~+-~-N-O-V~~+-~-D~EC~~-+~~~~~-+-~~~~-t IHI

-Hydrographa of wella in construction area.

Table 2.41 Summary of Hydrologic and Physical Properties of Tills from Drill Hole 7 Depth of Sample 3-5 Feet 13-14.8 Feet 45-47 Feet Porosity 35.5% 35.4% 36.7%

Coefficient of permeabilitya

.l9a11ons per (day)(square footl7 0.002 0.002 0.001 Grain-size distribution:

Clay - less than 0.004 mm 50.4 50.2 55.4 Silt - 0.004-0.0625 mm 34.2 32. 1 32.2 Very fine sand - 0.0625-0. 125 mm 3.8 3.0 2.7 Fine sand - 0.125-0.25 i;nm .... 3,3 2.8 2.3 Medium sand - 0.25-0.5 . mm ... 2.3 2.2 2.3 0 Coarse sand - 0.5-l.O mm 1. 1 1. 1 1.0 Very coarse sand - 1.0-2.0 mm 1.0 1. l 0.2 Very fine gravel - 2.0-4.o mm 2.0 1.8 1.6 Fine gravel - 4.0-8.o mm 1. 9 1.9 2.3 Medium gravel - 8.0-16.0. mm 3.8 0 a Vertical permeability.

Figure 2.42 Map of Construction Area Showing Water levels I and Extent of the Shallow Artesian Aguifer 11 I

I 0

0

-~**-

.u.

~**

C..Utl* . , *It ., ........

,,.,. :::,-::;.::,:*!,=**=*

Cl tft Pr1..1 a 1 , - *II lo -.-;....

N

.,o 4f0 ° 190

/

0

T 7S

~*.

0 ne "a. T

~* ..., ...

~

Hiii flood

.ll..

-¥- * * .!!.

loH tOffl lt*fe Off Ct o At*dl c Ot'f'lf OPfftlrtt

2.43 The shale bedrock comprises the third aquifer in the area.

This aquifer is referred to as the bedrock artesian aquifer on Figure 2.40. The rate and direction of movement of water in this aquifer are essentially unknown because of the few wells available for observation.

Most of the existing wells in bedrock are in the marginal . parts of the site and adjacent areas. It appears that the rock itself has a very low permeability, possibly in the same order of magnitude as that indicated for the till. However, the rock contains many fractures that will transmit small but usable quantities of water to a well. The existence of fractures ma~ effectively increase the permeability of the aquifer to several gpd/ft . Studies in other parts of New York indicate that most fractures are restricted to the upper 100-300 feet of the bedrock surface. In sedimentary rocks, such as the bedrock of the Service Center, fractures are developed in regular patterns which cut across the bedding at high angles. In these rocks, another set of fractures usually develops approximately parallel to the bedding, and the several sets of fractures intersect one another.

2.44 Water probably enters the bedrock on the tops and upper slopes of the higher hills, where the till cover is thin. Thereafter the water moves through the shale along the fractures to points of discharge.

Because of the extremely small openings developed along the fractures, the movement of water is accomplished by considerable loss of head (pressure). This is indicated by the difference in water levels in DH-3, finished in the upper 7 feet of bedrock; and in Ct-272, drilled 53 feet into bedrock (see Figure 2.42). The altitude of bedrock surface is approximately equal in the two wells. The altitude of the water level in DH-3 was 1358 feet on January 24, 1962, or 54 feet above that in Ct-272. Figure 2.42 shows the location of well Ct-272, a recently-drilled, unused, private well, in the construction area. This well is now in use as an observation well, and is equipped with a continuous water-level recorder. The record of water-level fluctuations in this well Is shown In Figure 2.40. The general decline indicated by the record may be most 1y due to continuing use of a nearby we 11.

2.45 The particular area chosen for the plant facilities (see Figures 2.7a and 3. 1) is one in which the artesian aquifer is missing (see Figure 2.42). This area is a 11 peninsula 11 bordered on the east by Erdman Brook and on the west by an unnamed stream. The incision of the valley floor by these two defiles is deep enough and the water table contours are such (see Figure 2.37) that it can be definitely stated that any activity getting Into the ground water in the plant site area will show up eventually in one of these two streams and nowhere else except, of course, for that which is sorbed upon the soils and held therein. This situation will allow us to have an excellent monitoring system with a minimum of expense and a maximum of reliability.

0

0 Seismology 2.46 The following discussion of the seismology of the site was prepared by Dr. John Broughton, New York State Geologist. Western New York is an area of lCM seismiclty. Although northern New York and New England are subject to frequent minor earth shocks, this frequency does not extend into southwestern New York. Earthquakes in the Northeast are of two major types: fl} those resulting from shearing stresses along lines of structural weakness and (2) those caused by regional uplift because of rebound of the crust after melting of the glacial ice which left this area no more than 10,000 years ago.

2.47 According to the records of the United States Coast and Geodetic Survey, in more than 100 years there has been only one earth-quake classified as 11 destructive or near destructive11 within a radius of 200 miles of the site. Detailed records since 1928 list only six earthquakes with epicenters within 75 miles of the site. Of these, only the Attica earthquake of August 12, 1929, exceeded Intensity~.

This shock was originally classified as Intensity II on the Rossi-Forel scale and would now probably be classified as Intensity llllI on the Modified Mercalli scale.

2.48 The nearest fault to the site is at a distance of 35 to 40 miles. Even this formation, the so-called Clarendon-Linden fault, is a 0 minor earth structure and cannot be completely proved as a fault.

Environmental Survey 2.49 An environmental survey to determine the natural radioactive background at and near the site is planned. The survey will include samples of water from Cattaraugus Creek above and below the site going as far below as GCManda; Buttermilk Creek water at several points; ground water from the surficial till, the shallow artesian aquifer, and the bedrock aquifer with samples being taken at several points in the construction area; silt samples from Cattaraugus and Buttermilk Creeks at the same points that water samples are obtained; vegetation on and near the site with particular attention being given to pasturage plants; a limited number of indigenous fauna will be selected for continuing study and a number of the selected species will be collected and thoroughly analyzed to give base-I ine data.

2.50 As a part of this program, the eventual plant monitoring stations will be set up on the ~reeks and brooks in the area and data will be taken at these points to arrive at a statistically acceptable base-line upon which to base future operational decisions. For instance, both the plant and the waste tanks wil 1 lie just to the west of Erdman Brook. A major monitoring station will be required at the confluence of Erdman Brook with the small stream just to the west of it. This will be established and analyses will be run on water obtained at this point.

0

0 2.51 During the preoperational survey period, the plant air monitoring stations wll l be selected and set up. These should be in operation for at least a year prior to any operation with activity to get background data for use in meteorological determinations.

0 0-

Ill. PLANT DESCRIPTION Ill PLANT DESCRIPTION Plot Plan 3,1 The exclusion area, some 3300 acres in extent, has been described in detail in Section II. This entire area is fenced with barbed wire farm fence and is conspicuously posted. The plant site area is shown in Figure 3.la and in more detail in Figure 3.lb. The plant is located near the center of this exclusion area which contains about 190 acres. This area is separately fenced with 7-foot chain link fence with three strands of barbed wire at the top. It, too, is con-spicuously posted. The plant is about 1500 meters from the nearest site boundary. The distance from the plant to Springville is four miles.

3.2 Figures 3.la and 3.lb show the relationship to one another of the various facilities included in this complex: the process building, waste tank farm, burial ground, lagoon, and warehouse. Distances from each of these facilities to the exclusion area boundary, uncontrolled streams, and railroad are shown in Table 3.2.

3.3 Figure 3.la shows the relocation of Rock Springs Road and Figure 3.lb shows the location of the gatehouse and parking area. All 0 access of personnel into the plant will be controlled from the gate-house and parking will be adjacent thereto.

3.4 The warehouse is located near the process building. This building provides storage space not only for bulk chemicals and other supplies for the plant, but also for bird cages, shipping containers, and equipment spare parts. A floor plan of the warehouse is given in Figure 3.4.

Process Building 3.5 An external perspective view of the process building is shown in Figure 3.Sa. A series of cutaway perspectives of the plant at various levels is shown in Figure 3.5b.* The building contains about 80,000 square feet of gross floor area. The process areas have been grouped together as much as possible to minimize piping runs and to provide a reasonable flow of material from the introduction of fuel into the plant to the removal of purified products.

Revision l, October 29, 1962 0 Revision 2, November 10, 1963 *.,.........

Figure 3.la Overall Plot Plan Drawing 4413-15A-A-101 0

Revision 1, October 29, 1962 Revision 2, November 10, 1963 0

10

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Process and Disposal Area i Drawing 4413 15A-A-102 Revision 1, October 29, 1962 Revision 2, November 10, 1963 0

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Table 3.2 Distances from Various NFS Facilities To Surrounding Features Distances in Feet From Process Waste Buri a 1 Seepage Building Tank F51rm Ground Basin Warehouse To: Exclusion Area Boundary 3,500 3,700 3,500 3, 300 3,500 Buttermilk Creek 2,700 2,soo 2,000 2' 100 2,800 Cattaraugus Creek 12,500 11 ,800 11 , 200 12,800 l 3,000

u. s. 219 12,700 12,400 11 , 700 13,500 l 3, 100 Rai 1 road 3, 100 3,250 2,000 2,400 3, l 00 Process Building 400 l ,000 700 170

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SPENT FUEL PROCESSING PLANT ENGINEERS ~ CONSTRUCTOR~

Figure 3.5b Cutaway Perspectives at Various Levels Drawing l5R-M-I Revision 1, October 29, 196:

c Revision 2, November 10, 1963

Page withheld as containing Export Controlled Information 153

0 Around the central core of process facilities are located offices, change facilities, and a utility room. Maintenance shops are provided in a separate building adjacent to the utility room. The result is a compact arrangement which makes use of common shielding walls wherever possible.

A minimum of space is lost In corridors. Mechanical handling between cells has been stmpl ifted. The design ts such as to permit a high degree of process control. Operations are segregated by type, degree of mainte-nance required, and activity levels encountered. Repair and replacement of each individual equipment piece has been made an integral part of the process and building design. The abbreviations used throughout this document for the various processing areas are shown in Table 3.5.

3.6 The fuel receiving and storage area Is shown in more detail In Figures 3.6a, 3.6b, and 3.6c. It contains an area Into which a truck or railroad car may be brought to wash down the cask and prepare It for unloading, a cask decontamination pit, cask unloading pool, fuel storage pool, and equipment for maintaining the purity of the water.

The Initial washdown area ts serviced with water, steam, and decontamina-tion solutions all of which are collected in a sump for possible processing.

There ts a second decontamination area located in a pit just to the ~ ~~- f of this area. These areas and the cask unloading pool are serviced by a 100-ton crane. (IV*I) Space Is provided for storing and doing mainte-0 nance work on casks.

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Figure 3.6a General Arrangement - Fuel Receiving and Storage Area - Plan Drawing 4413 lA-A-6 Revision 1, October 29, 1962 Revision 2, November 10, 1963 0

Page withheld as containing Export Controlled Information 157

0 Figure 3.6b General Arrangement - Fuel Receiving and Storage Area - Section Sheet I Drawing 4413 lA-A-7 0

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Page withheld as containing Export Controlled Information 161

Page withheld as containing Export Controlled Information 162

Page withheld as containing Export Controlled Information 163

0 F i gu re 3. 12a Equipment Arrangement - General Purpose Cell - Plans Drawing 4413 2A-A-9 0

Revision 1, October 29, 1962 Revision 2, November 10, 1963 0

Page withheld as containing Export Controlled Information 165

0 Figure 3.12b Equipment Arrangement - General Purpose Cell - Section Sheet 1 Drawing 4413 2A-A-10 0

Revision 1, October 29, 1962 Revision 2, November 10, 1963 0

Page withheld as containing Export Controlled Information 167

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Page withheld as containing Export Controlled Information 169

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0 F f gu re 3. 1)a l Equipment Arrangement - Chemical Process Cell - Elevation Drawing 4413 15R-A-144

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Page withheld as containing Export Controlled Information 172

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Revision I, October 29, 1962 Revision 2, November 10, 1963 O*

Page withheld as containing Export Controlled Information 174

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0 Figure 3.15a Schematic Elevation - Eguipment Arrangement Extraction Cell 1 Drawing 4413 15A-A-146 0

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Page withheld as containing Export Controlled Information 177

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Page withheld as containing Export Controlled Information 181

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Page withheld as containing Export Controlled Information 183

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Revision 1, October 29, 1962 Revision 2, November 10, 1963 0

Page withheld as containing Export Controlled Information 185

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0 i 3.16 At the west end of these cells are three areas devoted to product purlfl~tlon and shipping: Product Purification Cell (PPC),

Uranium Product Cell (UPC), and Product Packaging & Shipping (PPS).

Equipment arrangement in these areas are shown in Figures 3.16a through 3.16e *.

3.17 In addition to the foregoing areas which are directly con-cerned with the main-line process, there are a number of supporting areas and functions. Acid recovery and treatment of process off-gases are carried out Jn cells located at the south end of the CPC. Process waste tankage Is located Jn a below-grade cell next to the CPC. Operating aisles are located al ongsl de most of the process cel 1s. Controls. and Instruments for much of the equipment are located in the control room.

3.18 Warm equipment aisles are located on the south side of the extraction cells and contain shielded pump niches. Pumps are located in these lndlvldually shielded niches. Each niche has a removable shield cover. The use of Individual shielding for pumps is expected to simplify the maintenance aspects of the plant.

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0 Figure 3.16b Plans - Equipment Arrangement Product Purfflcatfon Cell Drawing 4413 lSA-A-153 0

Revision 1, October 29. 1962 Revision 2, November 10, 1963 0

Page withheld as containing Export Controlled Information 192

F i gu re 3* 16c Equipment Arrangement - Uranium Product Cell Plan and Section Drawing 4413 lSA-A-162 Revision 1, October 29, 1962 Revision 2, November 10, 1963 0

Page withheld as containing Export Controlled Information 194

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Revision 1, October 29, 1962 Revlslon 2, November 10. 1963

Page withheld as containing Export Controlled Information 198

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IV. PROCESS DESCRIPTION 0 Before the UNITED STATES ATOMIC ENERGY COt.MISSI~

Washington, D.C.

In the Matter of the Application of NUCLEAR FUEL SERVICES, INC.

For Licenses for a Spent Fuel Processing Plant Under Sections o3, 63, 81, 104 (b), and 180 of the 0 Atomic Energy Act AEC Docket No.00-201 Submission No. 10 - Final Safety Analysis Report Revision of Section IV - Process Description June 30, 1964 0

Q IV DETAILED PRCCESS DESCRIPTION 4.1 In this section the entire processing sequence is described in some detail starting with the introduction of fuel into the plant from a shipping cask and carrying it through the process step by step to the shipment of final products. The description is based upon the handling of the base-line fueli low enriched U02 in stainless steel or zircaloy tubes. With the exception of some modifications to the head end treatment, the same f lowsheets used for low-enriched uo2 fuels are also used for SCRUP fuels (natural uranium clad in aluminum). At the conclusion of each subsection the differences in the process necessary to handle each of the following fuels are noted*s

a. Th02-uo2 in stainless tubing, average 8% U (93.5% enriched)--Indian Point Core A

b. U-Mo alloy in Zr, 25% U 235--Fermi Core A

c. Enriched Uranium-Aluminum alloy clad in Aluminum--MI'R

d. U-3% Mo Alloy 1.6% enriched clad in aluminum-Piqua 0 e. Enriched uranium-zirconium alloy clad in zirconium or zircaloy.

A process diagram for the base line fuel and for each of the above fuels is shown in Figure 4.2la. Flow rates and stream compositions for each fuel is given in Table 4.2.

Fuel Receiving and Storage 4.2 Fuel is received at the plant in shielded casks which will arrive on specially designed railroad flatcars and flat bed trailers.

The larger casks will be cooled with demineralized water. Each shipment must conform at the time of shipment to 10 CFR Part 72, 49 CFR Parts 71-78 and to the Cask Acceptance Criteria shown in Appendix 4.2.

4.3 The cask and car or trailer are brought inside the building and monitored. Road dirt is removed by hosing and additional decontamination is carried out, if necessary. The cask temperature is recorded, the cask coolant is circulated and sampled, and any gas pressure in the cask is relieved and purged into the ventilation off-gas system.

Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

0 4.4 The cask is then put into the cask unloading pool by the 100-ton overhead crane. The unloading pool contains demineralized water to a depth of 44 feet. The cask lid is removed using extension wrenches and the 5-ton hoist on the overhead crane. The fuel elements are then lifted out of the cask with grapplers attached to the 5-ton hoist and loaded into storage cans which are in temporary storage racks in the unloading pool. The 5-ton hoist has a limit switch which will prevent the fuel element from rising above a level 11 feet below the water surface. The crane operator must maintain a pressure on the crane controls in order for the crane to operate. The empty cask is transferred to the cask decontamination pit for additional cleanup and preparation for shipment. After it is monitored the cask is reassembled and taken to the storage area for routine maintenance before it is shipped out.

4.5 The storage cans containing fuel elements are then trans-ferred to the fuel storage pool. This is done with the storage pool crane which has a limited vertical lift so that a minimum of 11 feet of water shielding is maintained at all times. Only one storage can may be handled at a time. The storage racks are so spaced such that a critical condition cannot arise even when two of the most reactive arrays are stored adjacent to each other or when one such array passes another, as closely as possible, in the unloading operation. The location of each fuel element is carefully recorded in a log. A special basket tagging system is used for each fuel to avoid mixup. The tags are designed to be clearly visible under water. All storage cans and fuel movements are 0 controlled by the shift supervisor.

4.6 Casks containing fuel elements known to be ruptured will have had those elements sealed in cannisters before shipment. Such cannisters are removed from the cask and placed in storage cans which are placed in racks in the unloading pool. These cannisters are purged into the ventilation off-gas system, if necessary. A hood leading to the ventilation off-gas system may be placed over the cannisters as they are stored until it is certain that the cannister is not leaking. They are then transferred into the regular storage racks.

4. 7 If it i s determined in the course of unloading a cask that an element has ruptured in transit, such an element will not be canned.

The ruptured element will be placed, if nec essary, in a special ruptured fuel cannister and treated as specified in Paragraph 4.6.

4.8 When it is desired to process a particular fuel, the shift supervisor will determine the location of this fuel from the log referred to in Paragraph 4.5. He will see that the desired elements (in their storage cans) are moved, one at a time, to the end of the fuel storage pool and affixed to the underwater transfer conveyor for transfer into the Process Mechanical Cell (PM::).

Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 210

0 Figure 4.9a Process Mechanical Cell-Equipment List AMF Drawing SK-3462

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Page withheld as unreviewed potentially containing Export Controlled Information 212

0 Figure 4.9b Process Mechanical Cell-Transverse Section AMF Drawing SK-3465 0

0

Page withheld as containing Export Controlled Information 214

Figure 4.9c Mechanical Flow Diagram-Process Mechanical Cell AMF Drawing 103 --SK 0

Page withheld as containing Export Controlled Information 216

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0 Figure 4.2la Planf Flow Diagram of All Process Steps From Dissolution Through Product Handling Drawing 4413 15R-A-5 0

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Page withheld as containing Export Controlled Information 222

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V. EQUIPMENT DESCRIPTION Page withheld as containing Export Controlled Information 263

Figure 5.3 100-Ton Fuel Receiving and Storage Crane Harnischfeger Sketch 10050 Revision 1, October 29, 1962 Revision 2, May 30, 1964

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Page withheld as containing Export Controlled Information 265

Figure 5.5 Fuel Pool Gate Bechtel Drawing 4413-18-M-11 0

0 Revision l, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 267

Page withheld as containing Export Controlled Information 268

0 Figure 5.6 Fuel Pool Storage Cans Bechtel Drawing 4413-lB-T-6 0

0 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 270

0 Figure 5.Ba Fuel Pool Storage Can Crane Bechtel Drawing 4413-lB-T-3 0

0 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 172

0 Figure 5.Sb Fuel Pool Service Bridge Bechtel Drawing 4413-lB-T-5 0

Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 274

0 Figure 5.9 Fuel Storage Rack Bechtel Drawing 4413-lA-M-7 0

0 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 276

0 Figure 5.11 Underwater Transfer Conveyor Bechtel Drawing 4413-lB-T-8 0

0 Revision l, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 278

Page withheld as containing Export Controlled Information 279

Figure 5.12a Fuel Handling Bridge Crane Shepard Niles Drawing lB-44333 0

0 Revision 1, October 29, 1962 Revision 2, May 30, 1964

Page withheld as containing Export Controlled Information 281

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Figure 5.14 0 Disassembly Saw AMF Drawing SK 3494 0

0 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

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0 Figure 5 ~ 16 Bundle Shear Birdsboro Drawing 64718 0

Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 288

Page withheld as containing Export Controlled Information 289

Figure 5 ol9 0 Pin Shear AMF Drawing SK 3820 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 291

Page withheld as containing Export Controlled Information 292

Figure 5.20 Maintenance Table AMF Drawing SK 3809 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 294

Page withheld as containing Export Controlled Information 295

0 Figure 5.21 Chopped Fuel Basket Loading Station Bechtel Drawing 4413-2A-T-6 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 297

0 Figure 5.23a GFC 2-Ton Crane Bechtel Drawing 4413-2B-T-13 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 299

0 Figure 5.23b GFC Power Manipulator Bechtel Drawing 4413-2B-T-54 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 301

Page withheld as containing Export Controlled Information 302

Figure 5.25 ci:c Crane Bechtel Drawing 4413-3A-T-4 Revision 1, October 29, 1962 Revision 2, May 30, 1964

Page withheld as containing Export Controlled Information 304

Figure 5.26 0 Leached Hull Dumping and Sampling Station Bechtel Drawing 4413-2A-T-ll 0

Revision 1, October 29, 1962 Revision 2, May 30, 1964

Page withheld as containing Export Controlled Information 306

Page withheld as containing Export Controlled Information 307

Figure 5.29 CFC Shielding Door Bechtel Drawing 4413-15A-M-78 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 309

Page withheld as containing Export Controlled Information 310

Figure 5.30 0 Dissolvers Bechtel Drawing 4413-3A-C-5 0

0 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 312

Page withheld as containing Export Controlled Information 313

0 Figure 5.36a Silver Reactors Bechtel Drawing 4413-6B-C-l 0

0 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 315

Figure 5.36b Dissolver Off-Gas Scrubber Bechtel Drawing 4413-6B-C-3 0

0 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 317

Figure 5.36c Dissolver Off-Gas Condenser Bechtel Drawing 4413-3A-C-6 0

0 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 319

Page withheld as containing Export Controlled Information 320

Page withheld as containing Export Controlled Information 321

Figure 5.37 Pulse Columns Bechtel Drawing 4413-4A-C-2 0

Revision 1, October 29, 1962 Revision 2, May 30, 1964

Page withheld as containing Export Controlled Information 323

Page withheld as containing Export Controlled Information 324

c Figure 5.39b Decanters Bechtel Drawing 4413-4A-D-l 0

0 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 326

Page withheld as containing Export Controlled Information 327

Page withheld as containing Export Controlled Information 328

G Figure 5.42a High Level Waste Evaporator Bechtel Drawing 4413-DS-?C-l-2 Revision 1, October 29, 1962 Revision 2, May 30, 1964

Page withheld as containing Export Controlled Information 330

Figure 5.42b Low Level Waste Evaporator Bechtel Drawing 4413-DS-7C-2-2 Revision 1, October 29, 1962 Revision 2, May 30, 1964

Page withheld as containing Export Controlled Information 332

Table 5.42a High Level Waste Evaporator--Oata Sheet Bechtel Drawing 4413-DS-7C-l-l Revision 1, October 29, 1962 Revision 2, May 30, 1964

Page withheld as containing Export Controlled Information 334

c Table 5.42b Low Level Waste Evaporator--Data Sheet Bechtel Drawing 4413-DS-7C-2-l Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 336

Figure 5.42c Rework Evaporator Bechtel Drawing 4413-DS-7C-4-2 Revision 1, October 29, 1962 Revision 2, May 30, 1964

Page withheld as containing Export Controlled Information 338

Table o.42c Rework Evaporator--Data Sheet Bechtel Drawing 4413-DS-7C-4-l 0

Revision 1, October 29, 1962 Revision 2, May 30, 1964

Page withheld as containing Export Controlled Information 340

Figure 5.43a Low Enriched Uranium Product Evaporator Bechtel Drawing 4413-DS-~-4-2 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 342

c Figure 5.43b High Enriched Uranium Product Evaporator Bechtel Drawing 4413-DS-~-5-2 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 344

Table 5.43a Low Enriched Uranium Product Evaporator--Data Sheet Bechtel Drawing 4413-DS-:C-4-l Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 346

Table 5.43b High Enriched Uranium Product Evaporator--Data Sheet Bechtel Drawing 4413-DS-:C-5-l Revision l, October 29, 1962 Revision 2, May 30, 1964

Page withheld as containing Export Controlled Information 348

Page withheld as containing Export Controlled Information 349

0 Figure 5.45 Plutonium Product Evaporator Bechtel Drawing 4413-DS-~-2-2 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 351

c Table 5.46 General Purpose Evaporator--Data Sheet Bechtel Drawing 4413-DS-7C-5-l Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 353

Page withheld as containing Export Controlled Information 354

c Figure 5.47 Acid Fractionator Bechtel Drawing 4413-7B-C-2 Revision 1, October 29, 1962 Revision 2, May 30, 1964

Page withheld as containing Export Controlled Information 356

Page withheld as containing Export Controlled Information 357

Page withheld as containing Export Controlled Information 358

Page withheld as containing Export Controlled Information 359

Page withheld as containing Export Controlled Information 360

Figure 5.50a 0 Radioactive Waste Tanks 80-1 and 80-2 Drawing 4413-8A-D-3 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 362

c Figure 5.50b Details - Radioactive Waste Tanks 80-1 and 80-2 Drawing V.P. 4413-8-0-12-11-2 Revision 1, October 29,1962 Revision 2, May 30, 1964

Page withheld as containing Export Controlled Information 364

0 Figure 5.50c Details - Radioactive Waste Tanks 8D-1 and 30-2 Drawing V.P. 4413-8-0-12-12-1 0

Revision 1, May 30, 1964 0

Page withheld as containing Export Controlled Information 366

0 Figure 5.50d Plans - Vault for 8D-l and 8D-2 Drawing 4413-SA-Q-l Revision 1, October 29, 1962 Revision 2, May 30, 1964

Page withheld as containing Export Controlled Information 368

Figure 5.50e c Sections and Details - Vault for 80-1 and 80-2 Drawing 4413-SA-Q-2 0

Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 370

Page withheld as containing Export Controlled Information 371

Page withheld as containing Export Controlled Information 372

0 Figure 5.55 Section Through Waste Storage Tank Drawing 4413-BB-Q-8 Revision 1, October 29, 1962 Revision 2, May 30, 1964 0

Page withheld as containing Export Controlled Information 374

Page withheld as containing Export Controlled Information 375

Page withheld as containing Export Controlled Information 376

Page withheld as containing Export Controlled Information 377

Page withheld as containing Export Controlled Information 378

Page withheld as containing Export Controlled Information 379

Figure 5. 61 Plutonium Ion Exchangers Bechtel Drawing 4413-5B-C-l Revision 1, October 29, 1962 Revision 2, May 30, 1964

O

Page withheld as containing Export Controlled Information 381

c Figure 5.62 Silica Gel Columns Bechtel Drawing 4413-5B-C-2 0-Revision 1, October 29, 1962 Revision 2, May 30, 1964

Page withheld as containing Export Controlled Information 383

0- -

Figure 5.63 Solvent Wash Columns Bechtel Drawing 4413-1~-C-l Revision 1, October 29, 1962 Revision 2, May 30, 1964 o~

Page withheld as containing Export Controlled Information 385

ML22129A041

Text

SUMMARY

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